Letter Sequence Other |
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MONTHYEARML20138K1271997-02-12012 February 1997 Requests Addl Info for Review of 950509 Application for Approval of site-specific License for ISFSI at North Anna Nuclear Power Station Site.Response Requested within 60 Days from Date of Ltr Project stage: Approval ML20217H5721997-10-0909 October 1997 Forwards Info Which Supports Use of NUREG/CR-0098,dtd May 1978,as Part of ISFSI Liquefaction Analysis,In Response to NRC Question Raised at 970505 Meeting Project stage: Meeting ML20202B0011997-11-24024 November 1997 Forwards Response to NRC 971105 RAI Re Util 970509 Application for Review & Approval of site-specific License ISFSI at Plant.Response to Item 5 Will Be Forwarded to NRC in Separate Correspondence within 30 Days Project stage: Request ML20203A8411997-12-0404 December 1997 Forwards Draft Reformatted Proposed North Anna ISFSI TS, According to Improved Std TS Format,For Review.Comments & Addl Proposed Changes Requested by 980130 Project stage: Draft Other ML20203J9981997-12-16016 December 1997 Forwards Response to Item 5 to NRC RAI Dtd 971104,re North Anna ISFSI License Application Project stage: Other ML20198H7391997-12-29029 December 1997 Forwards RAI Re Application for North Anna ISFSI for Fuel Assemblies to Be Stored in Plant ISFSI Project stage: RAI ML20199A4921998-01-16016 January 1998 Forwards RAI Which Addresses Thermal Design Criteria of Fuel Assemblies to Be Stored in North Anna ISFSI & Concrete Pad Static Analysis Project stage: RAI ML20199D9331998-01-23023 January 1998 Forwards Rev 21 to North Anna Power Station Emergency Plan & Rev 6 to Corporate Emergency Response Plan. Revs Reflect Addition of Isfsi.Rev 30 to EPIP-1.01, Emergency Manager Controlling Procedure, Encl Project stage: Other ML20203H9691998-02-13013 February 1998 Forwards RAI Re 950509 Application for Review & Approval of site-specific License for Isfsi.Rai Addresses Concrete Pad Design,Transporter Design,Cask Loading Operations & Record Keeping Requirements Project stage: RAI ML20203B4071998-02-17017 February 1998 Forwards Response to 980116 RAI Re Application for Review & Approval of site-specific License for ISFSI Project stage: Request ML20216F7781998-04-13013 April 1998 Forwards Summary of Required Changes to Plant UFSAR Associated W/Isfsi Operation.Identified Changes Have Been Approved by Plant Nuclear Safety & Operating Committee & Do Not Constitute Unreviewed Safety Question Project stage: Other ML20217F0461998-04-23023 April 1998 Forwards Response to RAI Re North Anna ISFSI for Concrete Pad Design,Transporter Design,Cask Loading Operations & Record Keeping Requirements Project stage: Response to RAI ML20236H5081998-05-29029 May 1998 Responds to 980518 RAI Re Application for Review & Approval of site-specific License for ISFSI at Naps.Listed Commitments Made to Ltr Project stage: Request ML20248K9121998-06-0808 June 1998 Forwards Preliminary SER for North Anna Nuclear Power Station Isfsi,Per Util 950509 Submittal of Application for ISFSI Project stage: Other ML20236H4471998-06-30030 June 1998 Informs That Attachments to 980529 Response to NRC 980518 RAI Re Application for Review & Approval of site-specific License for ISFSI at NAPS May Be Placed in PDR Project stage: Request ML20236M6571998-07-0707 July 1998 Submits Preoperational Test Acceptance Criteria & Test Results for North Anna ISFSI Construction.Preoperational Test Results Acceptable Project stage: Other 1998-01-23
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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
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Y t Wmsir EixcTune ANi> POWEH CO%1PANY RscusinNo, %GINI A 2M61 December 16, 1997 Mr. Carl J. Paperiello, Director Serial No. 97-667A Office of Nuclear Material Safety and Safeguards NL&OS/MAE R1 U. S. Nuclear Regulatory Commission Docket No. 72-16 Washington, D. C. 20555 Gentlemen:
.YJBQlNIA ELECTRIC AND POWER COMPANY HQBTH ANNA INDFEENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
RESPONSE TO.REQUESI FOR ADDITIONAL INFORMAIJON (TACMOJ.21113)
Virginia Electric and Power Company (Virginia Power) submitted an application for the review and approval of a site-specific license for an independent spent fuel storage installation (ISFSI) at North Anna Power Station on May 9,1995 (Serial No.95-195).
The NRC provided a Request for Additional Information to Virginia Power on November 4,1997. Virginia Power responded to the Request for Additional Information, with the exception of item 5, in a letter dated November 24,1997 (Serial No.97-667). The response to item 5 is attached.
Please contact us if you have any questions or require additional information.
Very truly yours, M
James P. O'Hanlon Senior Vice President - Nuclear Attachments Commitments made by this letter:
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cci *Mr. J. W. Shea -
Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission, Mail Stop 0-6-G 22 Washington, D. C. 20555 United States Nuclear Regulatory Commission Attention: Document Control Desk ,
Washington, D. C. 20555.
Mr. M. J. Morgan
- NRC Senior Resident inspector
> North Anna Power Station yw,-e- "
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. Al CHMENT1 Response To A Reque; For AdditionalInformation NRC Ouestion 5:
Background:
With regard to your soil liquefaction analysis, NUREG/CR-0098, NUREG-1407, and Generic Letter 88-20, Supplement 4, were developed and used to support the IPEEE and SEP programs but do not represent licensing standards for new facilities.
Request: Please provide a soll liquefaction analysis for the ISFSI based on the North Anna site design earthquake, in accordance with 10 CFR 72.102 requirements and the Standard Review Plan guidance (e.g., NUREG-0800 criteria on response spectra).
Altematively, demonstrate that the results of your previously submitted NUREG/CR-0098-based analysis is comparable or exceeds that obtained from an analysis based on Part 72.102 requirements and SRP guidance.
Virginia Power Response:
The NRC provided clarification in a November 18,1997 telephone conversation that the analysis based on Part 72.102 requirements and SRP guidance would be an analysis done in accordance with Regulatory Guide 1.60 using a .18g earthquake. The results of a comparison of our previously submitted NUREG/CR-0098 based response spectra to a Regulatory Guide 1,60 response spectra is provided in Attachment 2. The attached plot and the associated data points for the comparison of the response spectra for a Regulatory Guide 1.60 earthquake normalized to .18g and a NUREG/CR-0098 earthquake normalized to .3g shows that the NUREG/CR-0098 response spectra envelopes the Regulatory Guide 1.60 response spectra.
Therefore, the liquefaction analysis that was previously submitted is conservative with respect to the requirements of Part 72.102 and SRP guidance.
Page 1 of 1
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I Attachment 2 Comparison of NUREG/CR-0098 Based Response Spectra To Regulatory Guide 1.60 Based Response Spectra -
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Control Palats for the RG I.60 and NUREG/CR-0098 Spectra RG 1.60 The RG 1.60 control points are obtained from the amplification factors given in this Reg. Guide.
A pga value of 0.18g is used. For 5% damping, the control points are as follows:
Frequency (hz.) Amplification Factor Amplified Acceleration (g) 2.5 3.13 0.56 9.0 2.61 0.47 33.0 1.0 0.18 NUREG/CR-0098:
The control points for the NUREG/CR-0098 median centered (50%) horizontal spectra are determined from the following information given in the NUREG:
v/a= 36 in/sec/g (for soil, where v is the velocity, a is acceleration); and ad/v2 = 6.0 (d is the displacement)
Based on this, the control Points for the median-centen.d spectra at 5% damping are as follows:
Frequency (hz.) Amplification Factor Amplified Acceleration (g) 1.678 2.12 0.636 7.886 2.12 0.636 33.33 1.0 0.30
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e.se s.ee se.ee see.ee Frequency, Hz h: Avt.tGlCf cott Sott. Hokt. Skck/1, fl bbefM, 0 3g fp 6; 0./Pg fj*.
&.G. l.f 0 RAlf Skc11#, Tj ppfM, RG 1.60 hori . ground ARS with 0.189 pga, NUREG CR-0098 ARS with 0.3g pga
9
- l' DOCUMENT TYPE: REPoaf SHEET NO.t OF PROJECT NORTE ANNA DOO, NO. REV.
NS$[MM POWEff
SUBJECT:
CCatrARISON OF RG 1.50/NUR3G 0098 PREFARID BY DATE:
LY%
SYSta r CHECKED BY N DATE: /1~ bi 7 AMPLIFIED RESPONSE SPECTRUM VALUES
-FREQ(Hz) ACCEL (g) PERIOD FREQ (Hz) ACCEL (g) PERIOD 0.100 0.010 10.000 0.200 0.060 5.000 1.000 0.270 1.000 2.500 0.560 0.400 9.000 0.470 0.111 33.000 0.180 0.030 50.000 0.180 0.020 100.000 0.180 0.010 hI'lO, W 0' A
&tN f, N*f' SURRY/ NORTH ANNA RESPONSE SPECTRA DATABASE--ARS MODEL INFORMATION RG 1.60 Horiz. Ground ARS normalized to 0.189 pga and NUREG CR-0098 ground ARS normalized to 0.3g pga. Both at 5% Damping STRUCTURE: RG1.60 EQUIP DAMPING: 5.0%
UNIT: RG1.60 CURVE TYPE: Broadened DIRECTION: Horizontal FACTOR: 1.000
-ELEVATION: Free-Field (Ground) PEAK ACCEL (g): 0.560 EQ TYPE: Design basis earthqua::e EVAL ACCEL (g) :
SOURCE: RG1.60 NUM POINTS: 8 l PLOT LABEL: UXXXXHGRDD050B0050
' ENGINEERING WORK BHEET ;
- P cocua n Tyrei astokt suser no., or raoarer, nokru anon poc, no. msv.
NMMM SUBJECT COMPARISON OF RO 1.60/wUREQ 0098 PREPARED DY DATE: h
/'
hf g 3 srstax, caserID BYt M7NDATEt81*Y~i7 AMPLIFIED RESPONSE SPECTRUM VALUES FREQ(Hz) ACCEL (g) PERIOD FREQ(Hz) ACCEL (g) PERIOD 0.100 0.015 10.000 0.200 0.062 5.000 0.506 0.196 1.976 1.020 0.394 0.980 1.678 0.636 0.596 7.886 0.636 0.127 10.120 0.561 0.099 17.090 0.425 0.059 23.065 0.363 0.043 29.604 0.318 0.034 33.333 0.300 0.030 100.000 0.300 0.010 Nutec C9-a#, nenkudf 0 3y & (g;l heiamkl,Yj.'def}
SURRY/ NORTH ANNA RESPONSE SPECTRA DATABASE--ARS MODEL INFORMATION RG 1.60 Horiz. Ground ARS normalized to 0.18g pga and NUREG CR-0098 ground ARS normalized to 0.3g pga. Both at 5% Damping STRUCTURE: NUREG 0098 EQUIP DAMPING: 5.0%
UNIT: NUREG 0098 CURVE TYPE: Broadened DIRECTION: Horizontal FACTOR: 1.000 ELEVATION: Free-Field (Ground) PEAK ACCEL (g) : 0.636 EQ TYPE: NUREG/CR-0098 EVAL ACCEL (g) :
SOURCE: Nt' REG 0098 NUM POINTS: 12 PLOT LABEL: UYYYYHGRDN050B0060