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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
lAttcchment 4'
. ; x_.-
)
LWestinghouse i Power Generation - N' "^
- Electric Corporation - Group .e. t c eb : 0 -
- sr e m- n . , :
March 14,1980 Darrell G. Eisenhut, Acting Director
. Division of Operating Reactors
- U.S. Nuclear Regulatory Commission Washington, D.C. 20555 1
Dear Mr. Eisenhut,
LYour letters of February 25,1980, to licensees with operating Westinghouse steam turbines requested ee. tain site specific and generic information relativc to turbine dis _c integrity. You urged in your letter that the lleensees address the generic questions and coordinate the responses through an owners' group.
2 Licensees with nuclear power plants and Westinghouse steam turbines have formed a Turbino_ Dise Integrity Task Force, with Mr. Wayne Stiede of Commonwealth Edison Company selected as Chairman. Westinghouse has been working with this .
Task Force to generate responses to your generic questions.
At a Task Force meeting on March 12 and 13,1980, the utilities present prepared and approved. consesus responses to each of your generic questions. The Task Force further directed Westinghouse Electric Corporation to transmit these re-sponses directly to you. The purpose of this letter is to transmit that information
= to you.
It is our understanding that Mr. Wayne Stiede, Chairman of the Task Force, will ,
also confirm to you by separate letter, the Task Force's decision to have Westing- 1 house transmit these responses direct to you. We.also understand that each utilit-y, in their specific response to your letter to that utility, will discuss the extent to which they agree with these consensus responses.
If you have any questions on these, please contact me.
Sincerely,
. M. Schmerling,
)
b/pd -
Dise Integrity Prograr Manager '
- ec: W.~J. Ross, Operating Reactors Branch -
USNRC, Washington D.C 20555
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. s t GENERIC QUESTIONS -TO BE COMPLETED IN 20 DAYS
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- 1. j Describe what Lquality c'ontrolland . inspection- procedures are used for the ~ disc j bore and keyways. ;
~
ANSWER:
^ ~
s Chemical; analyses :aie~ made from each heat- ofIsteel. During ma_nufacture mechanical tests'are made from the disc bore regio'n. These include tensile and
- Charpy.v-notch impact tests. Each disc bore region is subject to ultrasonic and imagnetic particle inspections.' On later units, the disc keyways are inspected
- after machining, using liquid penetrant techniques.
- For in-s'ervico-inspection two ultrasonic techniques, namely -the tangential aim-and radial aim scans, have been developed to detect and determine the depth.of
" disc: keyway and bore cracks. ' The in-service ultrasonic inspection does not re-quire unshrinking discs from the rotor.
. The tangential. aim scan is used to locate cracks. The technique requires sound .
energy to be coupled. and' directed ~ tangentially towards the keyway from a precalculated position on the hub. This is accomplished by means of a compound angled plexQalass wedge. The wedge is machined to provide a contoured face which makes complete contact with the disc hub,' while ' aiming the sound energy
> at the disc bore / keyway. Crack indications occuring _in the vicinity of the key--
~
way apex and at the' bore will reflect the sound energy. The tangential aim scan is performed both in the clockwise and counterclockwise directions to permit
' locating crack indications with respect to the keyway apex.
A radial aim t'echnique'is used to. confirm cracks located by the tangential' aim
~
scan.- The. technique is also'used to determine the crack depth by comparing the-time lapsed in obtaining a-ultrasonic reflection from the crack with the time to obtain a reflection from the keyway or bore.
cII. Provide; details of1 the -Westinghouse repair / replacement. procedures for faulty dises. -
? ANSWER:-
p qWhen cracks are found b an inservice inspection their severity is evaluated by 7, ;means of an: allowable ~ life ceiculation. The allowable life is relatable to the time required for the crack to grow to cHtical size for fracture., Based upon the
. results of, this calculation,' the following actions may be taken:- .
TAL 5If!the-affected dise has a calculated allowable life greater than zero a -
. reinspection of the'~ disc is= recommended at approximately one-half of the allowable life.;
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JB. Ilf the ~affected disc ~ $s an~ allowable life less than or close to zero, one Cor more of the following may be employed:
11e LThe affected disc is removed by " machining", and is replaced with ia collar and pressure drop baffle.
- 2. ? Upstream keyways may be drilled oversize to remove cracks after.
.the downstream disc is removed.
< 3. The affected disc may be replaced . f This requires unstacking and restacking several discs on the rotor.
~
III.A. . ' What immediate 'and long term actions are being taken by Westinghouse to mini-
.mize future stress corrosion problems with turbine discs?
rANSWER:
The following sh' ort range actions are being taken:
'-1, lThose discs'which have been observed to be most susceptible-to-stress' corrosion cracking are being redesigned. The new designs will achieve lower bore stresses and utilize lower yield strength -
material. These changes will increase the margin against stress corrosion' eracking.
- 2. Designs that will' eliminate spacers and bore keyways are being explored.
The following long range solutions are being examined:
~
- 1. , - Bore Heating Ways and means to keep the dise keyways dry are
~
being explored.-
2.- Sealing ~- ' Ways .of ' sealing the hub and bore from the steam environment are being studied.
'3. Coatings - Another method of sealing is to apply a protective
~
coating. nWe are continuing to experiment with different coatings,-
but extensive' work is still required to develop processes for their
' application and to demonstrate their benefits.
- 4. Partial Integral Rotors - Since one piece forgings cannot be pro-cured:at this time,twe are exploring the possibilities of. partial integral rotors 'wh'ere;the first two or three discs qre made a part
- of the shaft. 'Only the last few discs will'have to be shrunk on. '
w 5.- - Integral Rotors -[A welded rotor design is being evaluated as a means to produce'an integral rotor.
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- , ;III.B.' . LWhat Lactions are being recommended .to utilitiesito ' minimize stress corrosion
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. icracking? :
m ANSWER:1 (Westinghouse has developed recommended limits for steam purity. When these.
" limits are1 exceeded corrective actions should be taken.
- MIV.A; fidentify the' impurities lknown.to cause cracking in the low pressure turbines, and
, itheir sources.-
JANSWER:-
(The main [ chemical:speel'es known to 'cause or contribute to stress corrosion of steam turbine materials in steam environments are:-
Sodium. hydroxide
-Sodium chloride .
Sodium sulfate
- Oxygen i
< ' The sources of these impurities are under study.
lIV.B. 1 Discuss the relationship between steam gererator chemistry and steam chemistry
- relative to ~ the introduction ~of corrosive impu-ities into the ' turbine, including aphosphate,' AVT, and BWR chemistry.
ANSWER:
~
. Analyses of material within LP disc cracks from PWR units shows the. presence -
- of Na, K,-Ca, SliC1, OH, and C together with~Fe, Co, V, Al and Ni ions.
!In1PWR. units .with recirculating steam generators, the total carry-over of non-s volatile dissolved solids, such as NaOH_ and Nacl depends mainly on.the mechani-cal carry-over. . However,' where ammonia is used for pH control such as with the
~
_ all volatile water treatment, carry-over of anions may increase due to a forma-tion of volatile' ammonium salts..
J in the PWR: units with once-through steam generators, the high pressure turbine
' steam. p.urity-is similar to the feedwa+ :r purity. Most impurities entering the .
steam generator are carried directli .ato the turbine.
~
- The publishedinformation on.BWR systems indicates the concentration of oxygen tin the:steamlis'in the' range of 10 to 30. ppm. :With respect to other elements,
- . ?however, it-is likely that.high steam' purity standards will be maintained for con'-
trolLof radioactivity.WTo achieve this, BWR' reactor ' water is generally double . -
fdemineralized. -
. . _ i IV.C.t : Discuss the1 mechanism of deposition'of these impurities that can lead =to'their- l
$~ . concentratio'n in certain areas of keyways and bores.
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The impurities from' steam can get into shrunk-on disc bores and keyways in sev -
- eral possible ways:1
~1. : Af ter ' deposition._in the. steam' path during ~ operation, corrodents can wash into disc keyways during layup due to moisture condensation.
J 2. - 1In:the wet ~ steam regions, the moisture can dry on hot metal surfaces.
( 3. LAs .long as the disc 1 retains. its shrink fit we are not aware of any-mechanism 'which can concentrate impurities on the bore.
~
V 1.' :What 'r' ole does the refluxing action in the s_ team separation portion of the steam generator have on scrubbing corrosive. impurities from the steam?
- ANSWER:n
' Two modes of transport of corrosive impurities from the steam generator. to the 1 turbine are mechanical entrainment and volatility.
The, non-volatile. chemical species are transported by mechanical entrainment which is normally. expected to be small.
.The steam generator scrubbing equipment has minimum effectiveness in preven-1 ting the transport of volatile impurities, such as ammonium chloride, to the' tur-bine. The' concentration of volatile impurities in turbine steam is determined by
, l their concentration in the steam generator bulk water and their specific volati-
.lity coefficient which differs with each species.
VL - To what extent can the buildup of corrosive impurities-in the LP turbine be alle-
'viated? What would be' the effects of the following action:
- A. - Pumping moisture separator condensate to condenser?
ANSWER:
Pumping moisture separator condensate to the condenser would be beneficial in-units with condensate polishing . In units without condensate polishing, there will
- be no effect.-
- B. -
- Periodically: moving (the) point-of condensation to prevent locallized. buildup of
~
corrosive impurities.
3 ANSWER:. _
l 1 Conceptually, dilution'of contaminants by increased levels of moisture and their i subsequent. transport to the condensate system: could substantially' reduce the -
buildup of ' impurities. -However,(the . cffectiveness of this technique and. the means-for_ successful control of the local environment of particular turbine parts lmust be developed and experimentally verified.
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~:Several of the less volatile active corrodants,~such as sodium chloride and sodium 1 m i sulphaWprecipitate ss cone'entrated liquid solutions in' a_ region.slightly above
- the.. equilibrium'~ saturated vapor.lin'e of pure water. This region occurs locally-
-within 'a given. stage 'during normal operation 'and m.igrates .toward the turbine
- 2. exhaust'as load reduces. iControl of the zone' can be affected by changes in load -
L and nioisture separator ' reheater (MSR) outlet' temperatu're.
-- VIl ~' . Describe? fabrication 'and heat; treatment sequence for' discs, including thermal.
4 exposure during shrinking operation.
6 ANSWER:
- [The typical sequence for producing a disc forging includes the following opera-
<- L tions, not all of which are necessarily applicable to any given disc.
! A. Melting and casting of Ingot. Most discs manufactured since the early 1960's 1are.made using basic electric furnace steel which is vacuum stream degassed or
- vacuum-carbon-deoxidized.-- .
LB.; Forging The ingot is heated to forging temperature, block forged and cut into 2 to 4 pieces from which the individual _ disc forgings are made.
I" C.: Preliminarv Heat Treatment This step consists of austenitizing and t.emper- .
ing the forging' to promote structure uniformity, grain refinement, and good machineability.
D. . Preliminary Machining The forging is machined to the disc contour.
. E. : 2 Preliminary . Ultrasonic Inspection Typically the supplier makes a partial ultrasonic inspection of the forging to assure that the quality warrants ~ continued !
manufacturing effort.
. F. JHeat Tree' tent for Propertig The forging is austenitized and tempered at
. approprir , ..mperatures to achieve the desired mechanical properties. Cooling from the austenitizing treatment is achieved by water quenching. After temper-ing the forging is. cooled in the furnace at a controlled rate.
G.. Mechanical Properties Tensile properties _are tested to determine if the re-quired strength level ~has b'een achieved. Since about 1960, Charpy v-notch im-
_ pact tests are made on each forging.
H. NDE Inspection _ The forgings'are rough machined to the Westinghouse draw--
ing requirements and'an ultrasonic inspection of the flat surfaces of the hub, Lweb, and rim _of the disc is performed.
LI.S Stress' Relief This treatment is requir'ed when a.significant-amo~unt of metal is t -
, machined off of.the forging'after it has been heat' treated for properties. Thei
~ stress relief.' treatment is 50-100 0, F. below the tempering temperature. ' Cooling -
~
< is accomplished by a controlled furnace cool. ~
' lJ.EMechanical Properties'- When a stress relief is.used, the mechanical properties-
-are tested aft er the stress relief treatment. -(Reference Step G)'
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(KNDimensional ChecklThe forging is machined to a cle'an surface, the balance
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- of; test prolongations- are removed, and the' dimensions checked.- The' forging is -
Jthen shipped.to.Wastinghouseifor final machining and ass.embly onto the rotor.
m L 'NDE Inspection-l A fluorescent magnetic: particle inspection is performed Tafter finish machining (This inspection.was n,t applied during the early 197.0's.)
M.' Shrinking Discs On the Rotor Shaft Thel assembly operation consists of four-parts; namely, preparation.of the shaf t, preparation of the discs, assembly of the rotor and pinning of the discs to the shaft. :
- 1 ; ' Preparation of the Shaft? After final shaft machining and inspec-tions artcomplete the shaft is cleaned:with degreaser and dry -
-_ lint-free cloths, and is mounted in a vertical position. The surface
- of the: rotor that,will.be .in contact-with the disc is coated with-lubricant
- 2. - : Preparation of the Disc. After final machining and inspections'
- are complete. the disc surfaces and blades are cleaned to remove fore ~ ign material. Prior.'.to ' heating ior . assembly : the : disc bore
! diameter 11s measured and compared to that of the drawing to-assure :a correct shrink fit. The disc is placed on an assembly
, fixture, leveled and~ loaded into a furnace which is at '3000 F or -
_ -less.
!3; Assembly of the Rotor The disc.is slo.wly heated to the required-shrink temperature between'6000 and.750 0 F. When the shrink temperature'is reached-the disc is removed from the furnace and lowered onto the shaft.
4.- Axial Aligning and Pinning: of Discs. Liners are placed at. the-
' exhaust face of each disc to assure the proper axiallocation. The keyways.are then drilled. Since the early 1970's, a penetrant in-spection is performed in the keyway prior _ to inserting the key.
/ VIII) : Discuss the 'effect of any local residual stresses on the cracking mechanism.
< ANSWER:
- < D'epending'on their' nature'and magnitude,' residual surface stresses can have'an L T . effect on crack initiation.~ Proper contro1~ exercised in the selection of machining K ~_ : parameters results in compressive stressesiwhich .are~usually beneficial. LAt the
. apex of-the keyway,;the residua 1' stresses may. be influenced by local yielding as'a result _of the ' stress .cencentrating action o,f the key'way. -
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