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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211J2211999-08-31031 August 1999 Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20210T0671999-08-13013 August 1999 Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML20209E3711999-07-0202 July 1999 Forwards Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.Violations Being Treated as Noncited Violations ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML20196G2581999-06-23023 June 1999 Discusses Closure of GL 92-01,rev 1,suppl 1,reactor Vessel Structural Integrity ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20196G2211999-06-21021 June 1999 Forwards Licensee Sampling & Testing Obligations Re Vpdes Permit VA0052451 Reissuance Application.Details of Requests for Sampling & Testing Waivers,Included ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML20195J1391999-06-11011 June 1999 Submits Addl Info as Addendum to Original Application Which Proposed Use of Three Chemicals in Bearing Cooling Tower at North Anna Power Station,Per Reissuance of Vpdes Permit ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20206U7441999-05-20020 May 1999 Informs That NRC Unable to Conclude That NAPS Has Met Intent of Supplement 4 to GL 88-20.RAI Re Fire Area of IPEEE Encl. Response Requested within 90 Days of Submittal Date ML20207A8541999-05-20020 May 1999 Forwards RAI Re Licensee Listed Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 90 Days of Submittal Date ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206L4661999-05-10010 May 1999 Forwards SE Accepting Request to Delay Submitting Plant, Unit 1 Class Piping ISI Program for Third Insp Interval Until 010430,to Permit Development of Risk Informed ISI Program for Class 1 Piping 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206H0221999-05-0303 May 1999 Informs That Licensee Changes Bases for TS 3/4.6.1.2, Containment Leakage. Changes Allow Use of Other NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing.Ts Bases Page,Encl ML20206G9481999-05-0303 May 1999 Informs NRC That Insp of 58 Accessible safety-related Pipe Supports Completed in Response to NOV from Insp Rept 50-338/98-05 & 50-339/98-05.Commitments Made Include Plans to Perform Assessment of Welding & Welding Insp ML20205T1181999-04-16016 April 1999 Requests NRC Approval Prior to Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit.Nrc Concurrence with Irradiation Program Requested by End of June 1999 ML20205P1891999-04-0808 April 1999 Forwards ISI Program for Third ten-yr ISI Interval for North Anna Unit 1 for Class 1,2 & 3 Components & Component Support.Third ten-yr Insp Interval for North Anna Unit 1 Begins on 990501.Page 2-26 of Encl Not Included ML20205K3631999-04-0505 April 1999 Requests That Relief Request IWE-3 Be Removed from 980804 Relief Requests Submitted to Nrc.Subject Relief Request Was Inadvertently Retained in Attachment 1 for Unit 1 ML20205K2191999-04-0101 April 1999 Forwards Response to NRC 990106 RAI Re Util Summary Rept on USI A-46 Program,Submitted 970527.Calculations & Corrected Table 11.1-1,encl ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML20205E2701999-02-25025 February 1999 Forwards Rept on Status of Decommissioning Funding for North Anna Power Station,Units 1 & 2.Trust Agreement Between Old Dominion & Bankers Trust Co,Effective 990301,attached ML20207A8741999-02-25025 February 1999 Draft Response to NRC Telcon Re Licensee Request for Approval of LBB Evaluation in Support of Elimination of Augmented Insp Program on RCS Loop Bypass Lines.Response Justifies Use of Less than One Gpm Detectable Leakage Rate ML18152B5401999-02-11011 February 1999 Requests Relief from Specific Requirements of Subsection Iwl of 1992 Edition with 1992 Addenda of ASME Section Xi,Per 10CFR50.55a(a)(3) ML20203C8181999-02-0505 February 1999 Forwards Response to NRC 981217 Telcon RAI Re risk-basis of Nitrogen Accumulator Action Statement to Complete NRC Review of 951025 Proposed TS Changes 1999-09-27
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20043H9431990-04-27027 April 1990 Requests Withholding of Proprietary WCAP-12351, North Anna Unit 1 Evaluation for Tube Vibration Induced Fatigue, from Public Disclosure Per 10CFR2.790 ML20246D7521989-08-0404 August 1989 Requests That Proprietary Topical Rept WCAP-12349, North Anna Unit 1 Steam Generator Update Tube Bundle Structural Integrity Presentation, Be Withheld (Ref 10CFR2.790) ML20244B7031989-05-23023 May 1989 Requests That Rev 1 to North Anna Unit 1 890225 Steam Generator Leak Event Rept Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20012D7581989-05-0303 May 1989 Requests That Proprietary WCAP-12265, North Anna Unit 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20245K7281989-04-19019 April 1989 Requests That Proprietary Steam Generator Leak Event Rept, Be Withheld from Public Disclosure,Per 10CFR2.790(b)(4) ML20155D1571988-08-12012 August 1988 Requests That Proprietary WCAP-11929, Safety Evaluation: Zirconium Base Advanced Cladding Matls Usage in North Anna Unit 1 Demonstration Fuel Assemblies, Be Withheld,Per 10CFR2.790(b)(4) NRC-87-3280, Forwards Type I & II Ltrs Re Steam Generator Tube Rupture Event,In Response to Request for Info on Generic Implications of Tube Rupture for Use in Preparing Presentation to NRC on 871109.Part 21 Related1987-10-28028 October 1987 Forwards Type I & II Ltrs Re Steam Generator Tube Rupture Event,In Response to Request for Info on Generic Implications of Tube Rupture for Use in Preparing Presentation to NRC on 871109.Part 21 Related NRC-87-3266, Forwards Proprietary WCAP-11601 & Nonproprietary WCAP-11602, North Anna Unit 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation & Application for Withholding of Proprietary Info (Ref 10CFR2.790)1987-09-23023 September 1987 Forwards Proprietary WCAP-11601 & Nonproprietary WCAP-11602, North Anna Unit 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation & Application for Withholding of Proprietary Info (Ref 10CFR2.790) ML20235K4141987-09-23023 September 1987 Requests Proprietary WCAP-11601, North Anna Unit 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation, Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-87-3261, Forwards Proprietary North Anna 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation. Rept Withheld (Ref 10CFR2.790)1987-09-13013 September 1987 Forwards Proprietary North Anna 1 Steam Generator Tube Rupture & Remedial Actions Technical Evaluation. Rept Withheld (Ref 10CFR2.790) NRC-87-3208, Forwards Proprietary Info Re Plant Demonstration Fuel Assemblies.Encl Withheld (Ref 10CFR2.790)1987-03-11011 March 1987 Forwards Proprietary Info Re Plant Demonstration Fuel Assemblies.Encl Withheld (Ref 10CFR2.790) ML20207R9291987-03-11011 March 1987 Requests Withholding of Proprietary Info Re Plant Demonstration Fuel Assemblies from Public Disclosure (Ref 10CFR2.790) ML20205S4511987-03-10010 March 1987 Requests Withholding of Proprietary Viewgraphs from 870305 Meeting Re Steam Generator Tube Integrity from Public Disclosure Per 10CFR2.790.Affidavit Encl ML20210T0781987-02-0505 February 1987 Requests That Encl Proprietary Viewgraphs of Facility Demonstration Assembly Irradiation Program Be Withheld (Ref 10CFR2.790) NRC-87-3201, Forwards Nonproprietary & Proprietary Viewgraphs of Facility Demonstration Assembly Irradiation Program,Per NRC Request for Info Re Use of Advanced Fuel Rod Cladding.Proprietary Viewgraphs Withheld (Ref 10CFR2.790)1987-02-0505 February 1987 Forwards Nonproprietary & Proprietary Viewgraphs of Facility Demonstration Assembly Irradiation Program,Per NRC Request for Info Re Use of Advanced Fuel Rod Cladding.Proprietary Viewgraphs Withheld (Ref 10CFR2.790) NRC-86-3160, Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P1986-09-0808 September 1986 Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P ML20213D7921986-08-20020 August 1986 Requests Proprietary WCAP-11163, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for North Anna Units 1 & 2, Be Withheld (Ref 10CFR2.790) ML18142A0481984-08-0707 August 1984 Requests Proprietary Comparison to Alternate Code Calculations Be Withheld (Ref 10CFR2.790).Affidavit Encl ML18139B4851981-07-28028 July 1981 Requests That Vendor Proprietary Info Forwarded in Util 810724 Ltr Re High Pump Burnup Radiological Consequences Be Withheld (Ref 10CFR2.790).Authorizes Use of Original Affidavit AW-76-51 Dtd 761018 ML20040C2661980-12-23023 December 1980 Application for Withholding Proprietary Summary Rept: Westinghouse Reactor Vessel Level Instrumentation Sys for Monitoring Inadequate Core Cooling (Microprocessor Sys). ML19320A9631980-06-25025 June 1980 Lists Topical Repts for Which Responses to Outstanding Questions Will Be Provided to Allow SER to Proceed & to Avoid Delays in Approval of Full Power Operation.Includes WCAP-9226,-9230 & -9236 ML18082A4921980-05-12012 May 1980 Forwards Schedule for Evaluation of Westinghouse Steam Generator Row One U Bends.Requests Delay of NRC Issuance of Generic Ltrs to near-term OL Plants Requiring Plugging of Row One Tubes,In Confirmation of 800415 Meeting ML19312D1861980-03-14014 March 1980 Forwards Turbine Disc Integrity Task Force Concensus Response to Generic Questions Contained in NRC 800225 Ltr Re Turbine Disc Integrity.Portions Withheld (Ref 10CFR2.790) ML19296C4721980-02-20020 February 1980 Forwards Corrected Copy of Matl Properties of Facility Disc 4 & Tables of A/Acr.Encls Withheld (Ref 10CFR2.790) ML19305B9591979-11-0707 November 1979 Discusses Undetectable Failure in Engineered Safety Features Actuation Sys.Failure of P-4 Permissive Circuit in Both Redundant Protection Trains Could Result in Failure of Sys to Automatically Initiate Protective Function.Details Encl ML20125B9391979-11-0505 November 1979 Notifies That Westinghouse Briefed Utils Re Problems W/ Stress Corrosion Cracking in Westinghouse Low Pressure Rotors & Problems w/1,800 Rpm Low Pressure Turbines, Reportable Per 10CFR50.55(e) or 10CFR21.W/lists of Plants ML20150D3441978-11-28028 November 1978 Advises NRC That Due to Extension of Date for FSAR Submission,B&W Will Defer Submission of Revs to Topical Repts BAW-10026 & 10026P Reactor Vessel Model Flow Tests for 145 Fuel Assembly Cores 1990-04-27
[Table view] |
Text
. .. _ _ . ._ _ _ _ _ _ . _ _
r a
. Westinghouse PowerSystems (ug,g3ff s
n Electric Corporation Box 355 Pittsburgh Pennsytvania 15230-0355 i
February 5, 1987 AW-87-009 Dr. 'Dxanas M.trley Office of Nuclear Reactor Regulation i U.S. Nuclear Regulatory rwanisudrwt Washington, DC 20555 APPrlCATION RR WIDlHOIDING PROPRIEIARY INPWMATICN FRCN PUBLIC DISCICSURE ,
Subject:
Information on North Anna 1 Demonstration Fuel Assenblies t (Proprietary)
Ref.: Westirv*n== Istter No. NS-NRC-87-3201, Johnson to Rubenstein, dated February 5, 1987
Dear Mr. Erley:
'Ihis application for withholding is subnitted by Westinghouse Electric Corporation ("Westingin=a") pursuant to the provisions of paragraph (b)
(1) of Section 2.790 of the (W=4= ion's regulations. It contains 4
commercial strategic information proprietary to Westingin== and cushunarily held in confidence.
'Ihe proprietary material for whids withholding is being requested is of the same tedinical type as that proprietary material previously subnitted with affidavit, AW-76-21, signed by the owner of the proprietary information, Westingin=a Electric Cwywaticm.
Accordingly, it is relilly requested that the subject information which is proprietary to Westinghouse be withheld frun public disclosure in accordance with 10CER Mien 2.790 of the rW=imien's regulations.
Corraspccders with respect to this application for withholding or the as-pHying affidavit should reference AW-87-009 and should be addressed to the undersigned.
V truly yours,
~
,/
8702180053 870205 '/ (jl(d.gg PDR- ADOCK 05000338 PDR Robert A. Wiesemann,-Manager P
_ Regulatory & Iagislative Affairs .,
/kph 4
oc: E.C. Shcanaker, Esq.
< Office of the General Council, NRC 1
i 1
PROPRIETARY INFORMATION NOTICE V .
TRANSMITTED HEREWITH ARE PROPRIETARY AND/OR NON-PROPRETARY V DOCUMENTS FURNISHED 70 THE NRC IN CONNECTION WITH REDUEST PLAhT SPECIFIC REVIEW AND APPRWAL.
IN ORDER 10 CONFORM 70 THE REQUIREMENTS W 10CFR2.790 W THE COM RIDULATIONS CONCERNING 1HE PROTECTION & PROPRIETARY DIFVRET 70 THE NRC, THE INFORMATION WHICH IS PROPRIETARY IN THE PROPRIETARY VERSIONS CONTAINED WITHIN BRACKETS AND WHERE THE PROPRIETARY INFORMATION *
. DELEIED IN 1HE NON-PROPRIETARY VERSIONS WLY THE BRACKETS RDIAIN, THE -
INFORMATION THAT WAS CONTAINED WITHIN THE BRACKETS IN THE PR HAVING BEEN DII.ETED. THE JUSTIFICATION FOR II. AIMING THE INFORMATI DESIGNATED AS PROPRIETARY IS INDICATED IN BCTIH' VERSIONS BY MEANS, W LN LEITERS (a) THROUGH (g) CONTAINED WITHIN PAREhTIESES LOCATED AS A SUPERSCRIPT IMMEDIATELY FOLLOWING THE BRACKETS BQ.2ING EACH ITD4 0F INFORM IDENTIFIED AS PROPRIETARY OR IN THE MARGIN OPPOSITETHESE SUCH INFORMA LOWER CASE LEITERS REFER 70 THE TYPES & INFORMATION WESTINGH HUS IN CONFIDENCE IDENTIFIED IN SECTIONS (4)(ii)(a) through (4)(li)(g) 0F THE AFFIDAVIT ACCOMPAhTING THIS TRANSMITTAL PURSUANT 1D 10CFR2.79 j l
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AW-76-21 i
- AFFIDAVIT ea COMMONWEALTH 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, de -
poses and says that he is authorized to execute this Affidavit on behalf ,
of Westinghouse Electric Corporation (" Westinghouse") and that.the aver-ments 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. Wiesemann, Manager Licensing Programs Sworn to and subscribed before the this ,?/k day of L-/4 9t/ 1976.
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Notary Public I,r .-- - .. . 7 d4 e 0 4. . ,,.
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AW-76-21 (1) ~I am Manager, Licensing Programs, in the Pressurized Water Reactor Systems 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 Westinghouse Water Reactor Divisions.
(2) I am making this Affidavit ~in conformance with the provisions of 10 CFR 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 commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission'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 withheld.
l (i) The information sought to be withheld from public disclosure is owned and has been held in confidence b;y Westinghouse.
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-AW-76-21 (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 the 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 system constitutes Westinghouse policy.and provides the rational basis required.
Under that system, information is _ held 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 companies.
(b) It consists of supporting data, including test data, relative to a process (or' component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
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AW-76-21 (c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(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.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.
There are sound policy reasons behind the Westinghouse system which include the following:
3(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its com-petitors. It is, therefore, withheld from disclosure
- to protect the Westinghouse competitive position.
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- (b) Itisinformationwhichismarketable.inmanywbys'.
-The extent to which such information is'available to competitors diminishes'the Westinghouse ability.to.
sell products and services involving the-use of the information.
(c)~ Use by our competitor would put Westinghouse at a competitive 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 acquire components of proprietary info.-
mation, any one component may be the key to the entire s 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 in those countries. ,
' (f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success-in obtaining and maintaining a competitive advantage.
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AW-76-21 (iii) The information is being transmitted to the Commission in .
confidence and, under the provisions of 10' CFR Section 2.790, it is to be received in con'fidence by the Commission.
(iv) The information is not available in public sources'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 at-tachment to Westinghouse letter number'NS-CE-1100, Eiche1dinger to Vassallo, dated June 11, 1976, concerning THINC II/THINC IV code comparisons. The letter and attachment are being sub-mitted in response to the NRC request at the May 28, 1976 NRC/ Westinghouse meeting.
, This information enables Westinghouse to:
(a) Justify the Westinghouse design correlations.
(b) Assist its customers to obtain licenses.
(c) Obtain preliminary design approvals.
.(d) Meet warranties.
(e) Provide greater flexibility to customers assuring them of safe and reliable operation.
(f) Reduce plant and fuel costs.
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- i (g) Optimize ~ performance'while maintaining high'1evellof~
fuel integrity.
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Further, the infonnatio'n gained from the THINC IV development-l f
-program is.of commercial value and is sold'for considerable -
sums of money as follows: ;
(a) Westinghouse sells the use of this information-to foreign licensees.
(b) Westinghouse uses the information.to perform and justify analyses which are sold to customers.
(c) Westinghouse sells testing services based upon the 4
experience gained and the test equipment and methods
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developed.
Public disclosure of this information concerning THINC II/
THINC IV code comparisons is likely-to cause substantial harm to the competitive position of Westinghouse because
- competitors could utilize this information to assess and.
justify their own designs without commensurate expense.
i
! The comparisons performed and their evaluation represent l
a considerable amount of highly qualified development effort.
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This work was contingent upon a THINC IV development program which has been underway during the past'six years. Altogether, a substantial amount of money and effort has been expended i
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. -l by Westinghouse which could only be duplicated by a com- .
petitor if he were to invest similar sums of money and -
provided he had the appropriate talent availa'ble. _
Further-the deponent sayeth not.
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- AW-76-21 (iii) .The information is being transmitted to the Commission.in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.
(iv) The information is not available in public' sources-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 at-tachment to Westinghouse letter number NS-CE-1100, Eiche1dinger to Vassallo, dated June 11, 1976, concerning THINC II/THINC IV code comparisons. The letter and attachment are being sub-mitted in response to the NRC request at the May 28, 1976 NRC/ Westinghouse meeting. ,
This information enables Westinghouse to:
(a) Justify the Westinghouse design correlations.
(b) Assist its customers to obtain licenses.
(c) Obtain preliminary design approvals.
(d) Meet warranties.
(e) Provide greater flexibility to customers assuring them of safe and reliable operation.
(f) Reduce plant and fuel costs.
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.. I AW-76-21 (g) Optimize performance while maintaining high level of fuel integrity.
Further, the information gained from the THINC IV development program is of commercial value and is sold for considerable sums of money as follows:
(a) Westinghouse sells the use of this information to foreign licensees.
(b) Westinghouse uses the information to perform and justify analyses which are sold to customers.
I (c) Westinghouse sells testing services based upon the
. experience gained and the test equipment and methods developed.
Public disclosure of this information concerning THINC II/
THINC IV code comparisons is likely to cause substantial harm to the competitive position of Westinghouse because competitors could utilize this information to assess and justify their own designs without commensurate expense.
The comparisons performed and their evaluation represent a considerable amount of highly qualified development effort.
This work was contingent upon a THINC IV development program which has been underway during the past six years. Altogether, a substantia 1' amount of money and effort has been expended l
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AW-76-21 !
by Westinghouse which could only be duplicated by a com-petitor if he were to invest similar sums of money and provided he had the appropriate talent available.
Further the deponent sayeth not.
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NORTH ANNA 1 DEMONSTRATION ASSEMBLY IRRADIATION PROGRAM .
1 I
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l MEETING AGENDA
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- 1 INTRODUCTION l l
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I 2 DEMO ASSEMBLY. FEATURES 3 CLADDING CORROSION REVIEW
, 4 FUEL R0D PERFORMANCE REVIEW PRIOR IRRADIATION EXPERIENCE
- DESIGN ANALYSIS
! 5
SUMMARY
/ CONCLUSIONS a
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! IRRADIATION PROGRAM .
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I OBJECTIVE 1 i
- DEMONSTRATE THE OPERATION OF ADVANCED ZIRCONIUM BASE ALLOY IN A COMMERCIAL PWR ,
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NORTH ANNA DEMONSTRATION PROGRAM TWO 17x17 STANDARD FUEL ASSEMBLIES WITH REMOVABLE TOP N0ZZLE EACH ASSEMBLY CONTAINS A NUMBER OF FUEL RODS CLAD WITH THE FOLLOWING:
WESTINGHOUSE ADVANCED ZIRCONIUM BASE ALLOY l
ZIRCALOY-4
CORE LOADING OF DEMO ASSEMBLIES SYMMETRIC LOADING ON ONE OF THE MAJOR AXES l
HIGHEST POSSIBLE LINEAR POWER (WITHOUT BEING 2
A LEAD ASSEMBLY)
- THREE 18 MONTH CYCLES OF IRRADIATION l
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DEM0 ASSEMBLY IRRADIATION SCHEDULES 1
l l PROJECTED l i
!. ROD BURNUP PROJECTED
- CYCLE GWD/MTU TIME BOC-7 LOAD DEMO 05/87 '
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! EOC-7 11/88 9, c) ,
i 1 l EOC-8 05/90 l EOC-9 ._
11/91 I
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[ [ADVANCEDALLOYPROGRAM (a b c)!
1 IRRADIATION PERIOD 7/74 - 11/85 l
~*GWD/MTU ROD AVERAGE (a b c)
GWD/MTU PEAK PELLET KW/FT PEAK PELLET LHGR .
TOTAL RESIDENCE TIME:
- ~*MO. - 3 CYCLES (a b c)
M0. - 4 CYCLES
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SUMMARY
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FUEL R0D PERFORMANCE REVIEW 1 PRIOR IRRADIATION EXPERIENCE I
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SUMMARY
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ADVANCED ALLOY CLAD FUEL RODS SATISFY ALL DESIGN CRITERIA
- IN NORTH ANNA 1 DEMO, THE ADVANCED ALLOY FUEL RODS WILL PERFORM AT LEAST l i
AS WELL AS REFERENCE ZIRCALOY-4 I
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