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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 ML20216E6661999-09-10010 September 1999 Forwards Analysis of Capsule W Virginia Power North Anna Unit 1 Nuclear Power Plant Reactor Vessel Matl Surveillance Program, for Capsule Withdrawn on 980922 ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit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 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. 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 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 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 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 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 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 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) 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 ML20216E6661999-09-10010 September 1999 Forwards Analysis of Capsule W Virginia Power North Anna Unit 1 Nuclear Power Plant Reactor Vessel Matl Surveillance Program, for Capsule Withdrawn on 980922 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 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) 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 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:UTILITY TO NRC
MONTHYEARML20065D5671990-09-20020 September 1990 Forwards Rev 15 to Security Personnel Training & Qualification Plan.Rev Withheld ML18153C3661990-09-20020 September 1990 Forwards Topical Rept VEP-NE-3-A, Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code. ML20059H7391990-09-10010 September 1990 Forwards Rev 15 to ISFSI Nuclear Security Personnel Training & Qualification Plan.Rev Withheld ML20059H2931990-09-0707 September 1990 Advises of Review & Approval of ASME Section XI Inservice Insp Program Interval 1 Repair & Replacement Program Change to Applicable Code Edition & Addenda ML20064A5201990-09-0707 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-338/90-15 & 50-339/90-15.Corrective Actions:Procedures Revised to Include Tolerance Bands for Temp Control Switch Setpoints & Involved Personnel Counseled ML20059E5481990-08-31031 August 1990 Forwards Supplemental Info Re Deletion of Pressurizer Safety Valve Requirement During Mode 5.Current Tech Spec Requiring One Operable Safety Valve in Mode 5 Unnecessary & May Be Deleted ML18153C3451990-08-29029 August 1990 Forwards Proprietary Semiannual Fitness for Duty Program Performance Data Rept for 900103-0630.Rept Includes Summaries of Mgt Sanctions Imposed,Actions Taken to Correct Program Weaknesses & Events Reported to Nrc.Encl Withheld ML18153C3391990-08-22022 August 1990 Requests Approval for Use of Plugs Fabricated of nickel- chromium-iron Uns N-06690 Matl (Alloy 690) to Plug Tubes in Steam Generators for Mechanical & Welded Applications ML20063Q1241990-08-15015 August 1990 Provides Supplemental Info for 900115 Tech Spec Change Request Re Max Allowable Control Rod Drop Time.Retained DNBR Margin Tracked & Documented by Calculational Note ML20058N5941990-08-0808 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-338/90-11 & 50-339/90-11.Corrective Actions:Procedure Revised to Limit Applicablity to Small Refueling Cavity Leaks & Listed Evaluations & Revs Will Be Made to EOP ML18153C3171990-08-0101 August 1990 Resubmits Synopsis of Changes to Updated Operational QA Program Topical Rept Vep 1-5A ML18153C3101990-07-26026 July 1990 Forwards Decommissioning Financial Assurance Certification Rept..., Nuclear Decommissioning Trust Agreement & Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement, Per 10CFR50.75 ML20055H5651990-07-20020 July 1990 Requests for Temporary Waiver of Compliance from Requirement of Tech Spec 3.3.1.1,Table 2.3-2 Re Response Time Testing. Request Does Not Pose Significant Hazards Consideration ML18153C2901990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Listed Transmitters Compiled.Transmitters Found Installed within Reactor Protection or ESFAS Have Been Replaced ML20055F9361990-07-16016 July 1990 Advises That No 30-day Rept Will Be Made Re Degradation of Seismic Support Bolts of post-accident Hydrogen Recombiners 1-HC-HC-1 & 2-HC-HC-1 ML20044B3501990-07-13013 July 1990 Forwards Monthly Operating Repts for June 1990 & Corrected May 1990 Rept Pages for North Anna Power Station ML20055E8121990-07-0909 July 1990 Requests Cancellation of Licenses Listed ML18153C2851990-07-0606 July 1990 Forwards Response to Generic Ltr 90-04 Re Status of Generic Safety Issues ML20055D4831990-07-0303 July 1990 Requests That Operator License for Bl Shriver Be Cancelled. License No Longer Required ML20055D4841990-07-0303 July 1990 Requests That Operator Licenses for Listed Individuals Be Cancelled.Licenses No Longer Required ML20055D7701990-06-29029 June 1990 Submits Supplemental Response to Violations Noted in Insp Repts 50-338/90-04 & 50-339/90-04 Re Failure to Take Timely Corrective Action for Repair of B Low Head Safety Injection Pump (1-SI-P-1B).No Addl Purchasing Procedure Required ML20043H9421990-06-21021 June 1990 Forwards Proprietary WCAP-12351, North Anna Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Rept Withheld (Ref 10CFR2.790) ML20043H1131990-06-15015 June 1990 Concludes That Removal of Temporary Loose Parts Monitoring Sys Does Not Increase Probability of Acccident,Create Possibility of New Kind of Accident & Does Not Reduce Margin of Safety ML20055C8661990-06-15015 June 1990 Forwards Application for Reissuance of NPDES Permit ML20043G5711990-06-15015 June 1990 Forwards Response to Request for Addl Info Re Insp Rept 50-339/89-20 Concerning Plant Safety Sys Outage Mod Insp. Response Withheld (Ref 10CFR73.21) ML20043G8731990-06-14014 June 1990 Discusses Evaluation of ASME Section XI Testing for Outside Recirculation Spray Pumps ML20043H2091990-06-13013 June 1990 Forwards List of Corrective Actions & Current Status in Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss ML18153C2501990-06-0808 June 1990 Confirms That Primary Policy Re Onsite Property Damage Insurance,Provided by Nuclear Mutual Limited ML20043F4531990-06-0808 June 1990 Forwards, Core Surveillance Rept for North Anna 2,Cycle 7 W/Extended License Burnup Limit. Rept Contains Specific Power Distribution Limits Applicable for Cycle 7 Operation W/Burnup Limit Extension ML20043D1661990-05-30030 May 1990 Requests Withdrawal of 860321 Request for NRC Review & Approval of Engineering Evaluations 7 & 8 Re App R Fire Protection Features at Plant,Based on Establishing 60-minute Interval Prior to Requiring Reentry Into Fire Area ML20042H0571990-05-11011 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Repts 50-338/90-04 & 50-339/90-04.Corrective Actions:Leak Test Procedures Will Be Reviewed & Revised to Specify Appropriate Test Boundaries & O-ring Obtained ML20042G2081990-05-0808 May 1990 Forwards List of Issues Requiring NRC Review & Approval to Support Upcoming Plant Refueling Outages.Issues Include Tech Spec Change Request to Increase Fuel Enrichment to 4.3% & Use of Improved Westinghouse Fuel Assembly Design ML20034B9461990-04-24024 April 1990 Forwards Results of H-3 Spiked Sample Analysis Completed on 900321.Analysis Performed W/Liquid Scintillation Counter ML18153C1971990-04-24024 April 1990 Responds to Unresolved Items Noted in Insp Repts 50-338/89-12,50-339/89-12,50-280/88-19 & 50-281/88-19 Re Secondary Sys Containment Leakage & Concludes Leakage Need Not Be Quantified & Not Included in as-found Leakage ML18153C1671990-03-30030 March 1990 Submits Supplemental Response to 10CFR50.63, Loss of All AC Power. Understands That Load Mgt Schemes for Both Blackout & Nonblackout Units Allowed by Station Blackout Rule ML18151A2551990-03-30030 March 1990 Forwards Rev to, Corporate Emergency Response Plan & Rev to, Corporate Plan Implementing Procedures. ML18151A4941990-03-29029 March 1990 Forwards Listed Info Re Licensee Guarantees of Payment of Deferred Premiums,Per 10CFR140.21(e) ML20012E5331990-03-29029 March 1990 Requests That Operator License for Listed Individuals Be Cancelled Due to Termination of Employment ML20012D7551990-03-20020 March 1990 Forwards Nonproprietary WCAP-12266 & Proprietary WCAP-12265, North Anna Unit 2 Evaluation for Tube Vibration Induced Fatigue. Deferral of Potential Sentinel Plug Removal Workscope Requested.Proprietary Rept Withheld ML18153C1511990-03-19019 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47. Operability & Surveillance Requirements for Steam Generator Overfill Protection Sys Will Be Incorporated in Tech Spec Change ML20012B8171990-03-0909 March 1990 Advises That Util Plans to Simplify Plant Liquid Radioactive Effluent Sampling Sys to Increase Reliability & Reduce Exposure.Mods Expected to Occur by Apr 1990 ML20012C0091990-03-0808 March 1990 Forwards Topical Rept WCAP-12497, Analysis of Capsule U from VEPCO North Anna Unit 2 Reactor Vessel Radiation Surveillance Program ML20012A0581990-03-0202 March 1990 Advises That Util Intends to Revise Emergency Diesel Generator Bushing Gap Measurement Insp Frequency to Each Refueling Outage in Order to Detect Extruded Bushings & Prevent Generator Failure ML18153C1261990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re NRC Regulatory Impact Survey.Survey Covers Type of Insp,Audit or Evaluation by NRC Resident,Nrc Regional Ofc,Nrc Teams & INPO ML20011F6191990-02-26026 February 1990 Forwards Analysis of Small Steamline Break Performance W/O Low Pressurizer Pressure Safety Injection North Anna Units 1 & 2 & Proposed Amends to Licenses NPF-4 & NPF-7 Re Rupture of Main Steam Pipe Analysis ML20011F7451990-02-26026 February 1990 Forwards 1989 Annual Steam Generator Inservice Insp Rept,Per Tech Specs 4.4.5.5.b & 6.9.1.4 ML20006E5971990-02-19019 February 1990 Forwards Rev 24 to Physical Security Program.Rev Withheld (Ref 10CFR73.21) ML20006E5991990-02-19019 February 1990 Forwards Rev 3 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20006E8141990-02-13013 February 1990 Requests Cancellation of Operator License OP-20521-1 for Jd Whitworth Due to Termination of Employment ML20011F5581990-02-0909 February 1990 Responds to NRC 900112 Ltr Re Violations Noted in Insp Repts 50-338/89-33 & 50-339/89-33 on 891211-15.Corrective Actions: Radiological Incident Rept Prepared to Document Release of Contaminated Equipment from Restricted Area 1990-09-07
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vincia ss a e n.t giseic aw.s poe t a e omea aasv. #icatmos*L. vinaissa 79 APft25 Al0: 2D April 24, 1979
]
L P. 0Wh Jr marmuur ,
';r. .grwis ?. O'Relliy c. M. UPRiad Serisi No. 289 ref f 't e of Inr.pection and F.ofor cernent P.o.cHtnetta F5EbC/WCS:bkr W. S. KENW
.S. Nuclear *etegulatory Cesarisalon
- .tgion I1 ((D MURPHY Doeket No 338 )
I:1 *istletta Strcet. Su*te 3300 J.T. suit.tetAso Lu.cwtn . ., License lio. NPF-4 Atl nta Georrin 10303
e, Mr . O' T:e 11 t y :
"IE BULLY.11N MO. 74-07 N0r.Tli 5I. iia ~55iUTATIOfi'tINIT 1 IE Pu))et in 79-0; recuented certein infornation concerning seismic No computer endes have been identified inie sis ef . s t e t y-rcinted piping. (S&W) which used any of the methods that w. rc u sied by St: ne & Web'it er Nuclear Services Corporation (NSC) leur$btJ in item 1 of the Bulletin. 1) did not use ban conftracJ that their version of N1* PIPE (see AttacismentFurther. Toledyne any of the m. thods described in item 1 of the Bulletin. 2) that their "ngiwer ing .tervices (TET.) has confirmed (see Attaclewnt f
. i 'i t of ADI.PifE did not simploy any of the methods dameribed in 3 tem 1 o t'n Itu lle t in. Westinghouse has confirmed that the WESTDYN analysis combined
'n r tzontal and ver tical shocks absolutely, which is dif f erent from Ites I ut 1E Mullet in 79-07. This method is Theidentical WESTDYN to the method seismic that would analysis is limited be *w.ed oday for a 2D evaluation. loop, pressur f rer surge line, loop stop valve, bypas r.a t b". reactor coci ant
.ir.a ar+d t ha w,in branch noceles. The North Anna analysis was performed
..ibsequent tn 1973 arsi the computer cods used is documented in WCAP-825?,
it. vinirm 1 accumentation of Selected Westinghcose Structural Analysis c.wputer Code *.". May.197 7, and is discussed in the TSAR.
In respense to 1tre 3, the following compu*er progra t he r:t is21e_
- 3. l'ST R E G E / SHOCK 111 03/03 - Steine & Webster THIS DOCUMENT CONTAINS
- 2. str1PE D3/03 - Stons 8. Webster
.l .
NL7 f f'E - %eje ar Services Corpt. ration 4, Atil ;'i rt (4-1-7 2) - Teledyne Engineerios Services S. WTFTDYN - Westinghouse Verif trut ton of coat. uter pregrams (NUP:PE 03/10. PSIMSS/SIFKKl III 2nd
.t e4*) .
- s. cd ty Stone & Ws hater is being addressed in respense te the Apri 7906160D'7 ()4 ,
i e
)
SH E E T 99.
venama euciv c an o roasa coupaw, to Mr . Jazze s F. O' Re fily addendum of the March 13th order To show Cause for Surry Units 1 and 2. S&V's in-house benelmarking between all major versitens of NUFIPE link versions -
03/03 to version 03/20.
As indicated in Attachment 1, NSC is currently ccepleting modelic6 and executicm of the MRC verification benchr. ark set for their version of NUP1FK. The results slould be available by the end of April.' It is our Under standing that the NRC has been in direct contact with REC on this subject.
As indicated in Attactment 2,1TS has completed a cooperisen analysie of ADLPIPE with THRSAP. ,
The Westinghouse WCAP-8257. Revision is containe results of the verification of WESTDTR against bencimark problems.
This should complete our respones to IE Bulletin 79--07. If etwre are any additional questions, please contact us. .
Very tr y yours, C
W. C. Spencer Vico Freefdent - Powar Station Engineering and Construction Services
, i ,
Attac tm ents ,
cc: Mr. John G. Davie, Acti:ig Director Of fioe of Inspection and Enforcenent , ,
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April 19, 1979 TELEC0PIEC y.-
T.1ups sw- 4lVITI We . c. Ten Milley Store and ' ebster Engineering Corporation N5 Sierr>er Street - Bth Floor P.0 t on t4A 02101 w Det- S'.r. Milley; Bulletin Ti It it.
h:
s letter is in response to questions concerning pr.inces a su-r.sry of pertinent infornation aboutAttach-ent I de ar. : verification.
- f. - ',cisnic analysis while Attachment. 2 describes the s a7t.ese of ' love-ter,1973.* m ?d by Stone er.d v'ebster or. fiorth Anna Unit 1.
ed sigebrait l
Mta: bet 1 states that no version of NUPIPE has ever ierv oy is always r.et tan fer intra-Ndal or inter-modal combination of se c ";c ents. The cortribution of each cod!rectional co@dnent ,
t eined to trecrease the total response. ADLP2PE was used to verify 1:tei.hr<ni 2 indi:stes that the computer code The intra-redal verif f-combined
' . ; D i f or sirgte direction earthonake response. i lts.
t.v t. nd for ce,parison with tauPIPE r.ultidirectio
. . nc t 1973, the set of verification problems his expanded In addition. to twe
. "istituting a clicrough tep t of the various FWPIPE features.f the 11RC verifica
.ntinark set tt.e results of which should be ava. are t
.s e t r 5 by the end of April .
Very truly yours, g-h C. A. RandsVice Prerident and Of rvc
. Engineering ifcchanics J1/cg M ischte nts e
F' IlUCLEHR SEHWEES CORPDHHilull 4%to t ADR,EX cvneor. .a u .
I Attachment 1 Mthods enployed by NUPIPE fer seismic analysis ftUPIr!.. as initially issued in 1972. perfornd Response Spu.true analypt, as irollows:
- 1. Obtain eigenvectors h Hg = 1 for i = j
-o f or i / j
- 2. 04epute all responses 'rg' (forces. rionents, support.1 cads) for each vector q,/Wg 2
- 3. CtxTute nast participation factors and take absolute ve tues.
l ix*![*gxg! M E gy
- 4. 'Ctriute response in rnode 1(81
, 9
) due to three-directions 1 earch-quake wit.h Spectral Accelerations 5,(W,). Sy (W g ). Sg(Wg )
Rg - r; (t g S,)2 + (Lg ,5 ,)2 + t ,$ .
- 5. The rrspense for all rwdes is then calculated as the trot-se 5,quan of tIIe individual redes, eacept for "close rede grr.ups wMch are ab' salute sur.rcif before RSS with other trdes and groups.
Labseq ent to 1972. the Step 4 calculation has been altered to ap' pear ast Rg a rg (Lg ,5 ,)r 4 (L g y5y)? 4 (Lg ,5,)
.i o
i
.] ! stuut,esn ot,rtve'4.s bunrunts s suas . . .
f b g M .s .
J WU'!DREX c os.r unianose .
l 1
Attactre.nt. 2
[
7, WF3PE Dyrmc Verification b
b Dacuriented verification of early versions of h'JP,.>E is contained in Exlear Services Corporation report liSC-73D1 (June 10'3) fi) PIPE I Coscuter Prograr. VerH ice tion" and the Nowerter 1973 Addenda.
The tsmtents of this docuvnt with respect to dynamic analysis are it.e following.
- 1. A fRIPIPE venus ADLFITE corparison of frequencies, forccs, sxmacnts, displace:xnts, rotations and stress for X carthqua Ae l
and Y eart1;ouake excitJtion as separate Toad cases (thus, intre 2da'
" codircitional cteparison was net exac.ined in this enamole).
o p Torce tiene history analysis carparison of NUPIPE with the pubib!cd
, 2.
b sol > tion in the ASMI ' Pressure vessel and Pfping: 1972 Cor:Puttr Frogre.ms Verification- (A5NE Benchrerk Problem fio. 5).
)s 4 3. A saA;.1c problte in which individual coda! responses for X, Y.
5, 7, A*Y, Y+1 and 14Y42 were cair.ulated by TAJPIPE and by P.ard
- (unno iter individuet K. Y. I results) to check bot.h in
- ra-coja .
vs .iot s.at icn and int e -rn sis 1 c o 4.sistat ion wi th c lo.te t>> des .
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N 'O Exa:elnation of 11:15 procedure sha1, that the contributwn of estri of the three codirectional excitations always results in an increase in the total endal response.
If a NUPIPF user erploys the ground motion -
- history capability of h1JFIPE to represent a seismic event, NUPlh ould perfore a respc,nse analysis for the X and/or Y and/or Z accelcration-histories as supplied i by the user. The (signed) swent corponents at the time the resultar.t e moment was maxipus are saved (when the load case is finished) for use in stress calculstions. It is possible for a user to purposely run X, Y, and I time histories separately and coceine the thee separate (sicr.cd) )
results algebraically, bt.t this would be a rather unusual procedure, certainly not a " coded in" f ault of the ccaputer program. ;
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'l /0 Mr. E. F. Shave -.
Suptryt:,or, Pf pe Stress 5 tone & IIebster Engineerir.o Corporation P.O. Box 2325 f;oston Massachusetts 02107 subject: U$f1RC Of fice of instection and Enfortement Bu11ctin Nurber 79-07
Dear Mr. Shave:
Teled.me Engineering Services has perfomed seisnic analysis of piping for your plant and therefore we are submitting the attached infomation to assist you in responding to the subject bulletin.
Essentially, TES did not use any of the rnethods listed in iten 1.
The nethods used by TES on your plant are described in Attactrnent 1.0.
The computer progran used on your plant was Aci p!PE, which f s cc rvrcially available through CDC. TES carmot Sr.1d a f ortran 11 stir.c of the ADI.plPE prosram since it is proprietary to Arthur D. Little.
A ctvrison analysis of ADLPIPE and TIMSAP is given in Atteclunt 2.0. This cow:parison is done for the snethod used by TES. rvnnino carthqual:e t'irections separately and cor.bining outside of the pregran.
lie hope that this inforrution will assist you in your response.
If you have any questions concerning this, please contact the writer er P.r. Daniel van Duyne.
~ .
Very truly yours3 T[ttDYNE EllGIllE ERING SCRVICES p.f(d b WAdt.tt M t:d Donald F. !.ariders inclosures Vice President sNGINCE Rs AfdD METAttVRGISTS
. s e
1).r. Sv ?.m.*y' . sj:f3_q_}.*i.? ?WT
$ /b c h c.f t t.re e c; the g:: n d c . r p n er. . . i sp : A..
P. p . r. ? :ysto.s ve re nr-1fred Tc r n y e , r. ( 2 hi ri:. r.6 ' v e r t.. ) a,'t- rnely.
1he represerstative ray.irum value of the t5rce roments Mx , Hy , and ; M. at any point in the oipir.g systera subjecteri to each of the three ind?per:dini sp=tial co ponent response spectra was obtained by taking an SP.55 so r.atiori of the rudal respons,es for 411 significant rtdes of the sys ter.
- M3 thematically, this is erpressed as follows:
1 N 1/2 #
[t M ] (1)
' 3 ke l k w*iere H) is the repres entative noxirsum value of rmwnt, j is the termnt corpanent direction x, y, or 2. H is the peak value of rronent ccrpons.t 3k due to,the k" rude, and N is the nuter of significant rnodes.
The co.:bined ef fcct of the three spatial corgonents of earthauale The represer.totive wz !, deterr.ined subsequently by the folicaing procedure. M and M ) fro.v.
r:.-r.irvm values of the codirectinaal froments (either M,, y z thr- t*:0 hori7nntal components of earthqualc were conbined by the ERS!
r(fl od and this SR55 value then added absolutely to the representathe re).in.ra value of the codirection roment for the vertical comonent of Ihthtratically, this is expressed as cor t hqtral.c.
(Hj ) ]Il + (Hj )y (2)
Ej * [(Hj ) 4 is the total scistnic monent enrponent R,, R y or R (Hj )y,y,7 where My are tt.e r epr esent ative traxirvn values of codirectional twents (Sp.SS valur!.) for each of the X, Y, Z earthquel.e directions, respectively.
51* ce all tems are SR55 values, they all possess a positive sign.
This, is besically the equation given in the rwthods reports (References 1 a..:. ?) f or the plants in question.
r The only alternPtive to any of the steps described above that TES used in the piping selsr. tic evaluation in sort of the plants was a
'lir6tly conservative but rore e>pedient This alternativenethod consisted to evaluate of stress taking in the Clatt ? and 3 piping syster-5. and H, rrrents repi c s.e ri t a t i ve ra r.ir vn va l ue s ( $ P.5 5 o f riode s ) of the M, , My cr.:f co-bining thtra by the SR55 r.ctbod to detemine the ASME Code resultant l The tetal resultant rov:r,t tg for each spatial corponent of esrthauske.
t r ert P.8 was then deterr.ined .
by cosbining. _the
_ . . . . _ _ . . . _ _ individuel
. _ _ _ . . . . .resultant
.. rust.nts
A (0 e
. # . i k-W TB_EDYNE TES Seismic Analysis M$thod DEMEWT1 ONClII' P4 rJe 2 for tach Spatial co conent of earthquake in a similar r. inner as dc5crIbed above in Lquetion 2.
Rg * [(Mg) + (H g )ff 4 (Hg )y D)
/.gsin, all terns on the rfpht side are SP.SS values and hence are ptsitive.
One ten see from the above procedures that there are no algebraic r.or.nstions (nvolved which could lead to unconservative results.
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._v-. b f Attneh:.ent. 4.0 I ccm uuren c:r.ys;s.
I u a f cr P l .SY;; .
C a ; 3r3 eun o." E.1.P:) E IV nanupt.
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nd exempic pruolem tnat. is easo usco in SAP
"_t? Z /.F c a:: r. J c ::tr e neous, Su,1w ry 5
X - Direction seismic Spectral topdino, 831.1 Stress .
( ADIPIPE Intensification $ tress, psj. _5
't M'ade factor _
Component
{ Nr.bor e 411 1.00 Run 1122 3
2.80 I Elbow 1105 3
[ .
2.80
,. Elbow 397 4 4 1.00 Run 806
) 4 1.00 Branch 537 8 1.00 Run 144B b 9
' 2.71 Elbow 9
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4 ll Vi vress w s A E s.nr:T ais A mu Powee n Cou rA > v Rsern ie rin o.Va noi s sa s u m os si b
April 2.1, 1079 s
(
4 Hr. James P. O'Reilly, 111 rector Serial No. 2%
/
y 81' f ice of 3r speect ton and F.nferc emer.c FS'MC/VCS:cwh 5, ').S. Nuclent Regulatory Conninsien
< Mcgion II 1)o rket N s. 30 . 3f.
{ 101 Jtarlett e St reet, Guite 3100 %-TM
) Atlanta, Georgia 30303
.f 1.is cus e Ne. PR i 1 Drnr Mr. O'Re!!iyt D14- 3 I J IE BUL).ETIN NO. 79-07 .
SURin T 0WLR S1 AIION UNITh 1 AND 2
{
IE Bulletin 79-07 requestcad certain inferination concerning scis?'.(
analysis of safety-reinted piping. Information regarding thin request har.
been and will he provided to you in conjunction with the NRC Order To Shw
. Cause of March 13, 1979.
Very tru yours, L .
FW I
W. C. pt.ncer Vice President - Fever Station
- Engineer ing and Cent t ruction Services t,I cc Mr. Jahr C. Davis, Acting. Director Of fice of inspection and F.af ors.tweent
.{
W '
ff' Mr. lisrosa r Denton, Dire ctor Of fice of Nuclear Reactor Rn gulation p
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