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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: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 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 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 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 ML20055D4841990-07-0303 July 1990 Requests That Operator Licenses for Listed Individuals Be Cancelled.Licenses No Longer Required ML20055D4831990-07-0303 July 1990 Requests That Operator License for Bl Shriver Be Cancelled. License 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) 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) ML20055C8661990-06-15015 June 1990 Forwards Application for Reissuance of NPDES Permit 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 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. 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 ML18153C2501990-06-0808 June 1990 Confirms That Primary Policy Re Onsite Property Damage Insurance,Provided by Nuclear Mutual Limited 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 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. ML20012E5331990-03-29029 March 1990 Requests That Operator License for Listed Individuals Be Cancelled Due to Termination of Employment ML18151A4941990-03-29029 March 1990 Forwards Listed Info Re Licensee Guarantees of Payment of Deferred Premiums,Per 10CFR140.21(e) 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 ML20006E5991990-02-19019 February 1990 Forwards Rev 3 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20006E5971990-02-19019 February 1990 Forwards Rev 24 to Physical Security Program.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 ML20006D7021990-01-31031 January 1990 Suppls Response to 891211 & 22 Special Repts Re Inoperable Kaman Process Vent Radiation Monitors R1-GW-178 & R1-VG-179.Monitor R1-GW-178 Failed to Pass post-maint Calibr for Sample Flow & Will Not Be Returned to Svc by 900131 1990-09-07
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 20261 W.L.Srawaar Vaca Passionwr December 21, 1984 NectaAm OramArrown Serial No. 696 EC:BSD:baj:2003N Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attention: Mr. James R. Miller, Chief Operating Reactors Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNIT NOS. 1 AND 2 GENERAL DESIGN CRITERIA 17 ANALYSIS Your letter of November 13, 1984, provided a revised and updated Safety Evaluation for North Anna Units 1 and 2 with relation to GDC-17. In that letter, it was requested that the NRC be kept appraised of the status of the motor control center contactor coils until such time that the final report regarding this matter is submitted for NRC review.
In our letter of July 7,1983 (Serial No. 326), Vepco stated that tests would be performed on motor control center contactor coils to determine the effects of overvoltage. Based on our presently available information we anticipate the test report will be available to Vepco in February,1985. Based on the receipt of the report in February, Vepco will submit the results to you in March, 1985.
Based on the aging which has been completed, the life of the contactor coils exceeds 10 years. We do anticipate that the replacement of some size 1 coils may be required at some future date. Since most loads fed from size 1 starters operate intermittently and operate less than 20 percent of the time, most size 1 coils will not require replacement. A review of the duty cycle of size 1 contactors is in progress.
In our letter of May 15, 1984, we stated that, "The continuing work which extends into 1986, as indicated in the Detailed Five - Year Summary Report B412280020 841221 pk PDR ADOCK 05000338
i VamoswtA Ex.zcTate Axn Powra CouPAwy To dated January 1,1984 and revised on April 1,1984 is to install new torque switch limiter plates on the MOVs." Therefore, we have not installed the new limiter plates during the 1984 refueling outages as you stated in your letter of November 13, 1984. As we have previously stated the motor operated valves have been reviewed and analyzed, and the results of the analysis indicate these valves will operate at reduced voltages predicted by our GDC-17 analysis. We will therefore continue to consider this item closed unless otherwise informed.
We will continue to provide you with updates on the motor control center
- contactor coil test results per your request.
Ve trul y o s, W. . St wart [
, BSD/WLS/baj cc: Mr. James P. O'Reilly Regional Administer Region II
- Mr. M. W. Branch NRC Resident Inspector North Anna Power Station E
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UNITED STATES *g gg NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 r, g
~s.,...../ NOV 131984 N0iG NOV 201964 wee Docket Nos. 50-338 and 50-339 Mr. W. L. Stewart Vice President - Nuclear Operations Virginia Electric and Power Company Post Office Box 26666 Richmond Virginia 23261
Dear Mr. Stewart:
SUBJECT:
ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGES (B-48),
UPDATED SAFETY EVALUATION: NORTH ANNA POWER STATION, UNIT NOS 1 AND 2 (NA-182)
Enclosed is our updated subject Safety Evaluation (SE) which was previously transmitted to you on January 11, 1983. The changes made to our original SE are highlighted by vertical lines in the right hand margin for ease of Our January 1983 SE was complete except for your deter-identification.
mination through the valve and motor operator manufacturers if Safety injection (SI) or Containment Depressurization Actuation (CDA) activated MOV originally specified to start at 90% of rated voltage could be rerated t start at 80% of rated voltage.
starter manufacturer the effect of overvoltage on the contactor coils.
15, 1984, you stated that recent studies and voltage By letter dated Mayanalyses show that SI or CDA activated YourMOVs letter originally 90% of rated voltage will also start at 80% of rated voltage.
further stated that various MOV enhancements, including installations of new torque switch limiter plates, would be implemented during the 1984 refueling outages for NA-182.
The installation of the new limiter plates further i
ensures operation of the SI and CDA MOVs at minimum analyzed voltage, In addition, you stated in your May 1984 letter that additional testing would j
)
be required to determine the effect of overvoltage on the contactor coils and indicated the your However, testmonthly resultsstatus would not be updates for available for our B-48 now indicate review slippage in u 1984.
completing the contactor coil tests until February 1985 and 21,with 1984submittal
- o your final report until March 1985 (VEPC0 letter dated September Serial No. 2530).
l With the issuance of the enclosed updated SE, we are closing out the NA-182 However, completion of these NA-1&2 action multi-plant action items B-48.
items does not mitigate our concerns stated in our April 15, 1984 letter that l
etzquase syp.
_2-all aspects of B-48 be completed in a timely manner. Plant Specific Action Items are being assigned to NA-182 for our review of the contactor coil tests and final report. As stated in our April 15, 1984 letter, we request that you continue to provide us with a monthly update on the status of the contactor coil test until such time that your final report regarding this matter is submitted for our review.
Sincerely, fA/ ~
James R. Mil r, C e Operating Reactors anch #3 Division of Licensi g
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page l
l
Virginia Electric and Power Company cc: Mr. J. H. Ferguson Richard M. Foster, Esquire Executive Vice President - Power Musick, Williamson, Schwartz, Virginia Electric and Power Co.
Leavenworth & Cope P.C.
Post Office Box 26666 P. O. Box 4579 Richmond, Virginia 23261 Boulder, Colorado 80306 Mrs. Margaret Dietrich Michael W. Maupin, Esquire Route 2, Box 568 Hunton, Williams, Gay and Gibson Gordonsville, Virginia 22042 P. O. Box 1535 Richmond, Virginia 23212 Mr. W. T. Lough Virginia Corporation Comission Mr. Paul W. Purdom Division of Energy Regulation Environmental Studies Institute P. O. Box 1197 Drexel University Richmond, Virginia 23209 32nd and Chestnut Streets Philadelphia, Pennsylvania 19104 .
U.S. Environmental Protection Agency Region III Office Atomic Safety and Licensing Appeal ATTH: Regional Radiation Board Panel Representative '
U.S. Nuclear Regulatory Comission Curtis Building Washington, DC 20555 6th and Walnut Streets Philadelphia, Pennsylvania 19106 Ellyn R. Weiss, Esquire Sheldon, Haman, Roisman and Weiss Regional Administrator 1725 1 Street,'N.W., Suite 506 Nuclear Regulatory Commission Washington, DC 20006 Region !!
Office of Executive Ofrector Mr. E. W. Harrell for Operations P. O. Box 402 101 Marietta Street N.W.. Suite ?c00 Mineral, Virginia 23117 Atlanta, Georgia 30373 Mr. Anthony Gambardella Old Dnminion Electric Cooperative Office of the Attorney General c/o Executive Vice President 11 South 12th Street - Room 308 Innsbrook Corporate Center Richmond, Virginia 23219 4222 Cox Road, Suite 102 Glen Allen, Virginia 23060 Resident inspector / North Anna c/o U.S. NRC Mr. Richard C. Klepper Senior Resident Inspector
- Board of Supervisors Route 2, Box 78 Louisa County Courthouse Mineral, Virginia 23117 P. O. Box 27 Louisa, Virginia 23093 m- _ _ _ _ . _ _ _ _ _ _
_ _ - - ~ . _ _ _ _ _ _ _ _ . _ _ _ _ _ __ _ _
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UNITED STATES
! o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
$ . ,I SAFETY EVALUATION NORTH ANNA POWER STATION, UNITS 1 AND 2 DOCKET N05. 50-338 AND 50-339 ADEOUACY OF STATION ELECTRIC DISTRIBUTION SYSTEM VOLTAGE 5 INTRODUCTION AND
SUMMARY
Virginia Electric and Power Company (VEPCO) was requested by NRC letter dated August 8,1979 to review the electric power system at North Anna, Units 1 and
- 2. The review was to consist of:
a) Determining analytically the capacity and capability of the offsite power system and onsite distribution system to automatically start as well as operate all required loads within their required voltage ratings in the event of 1) an anticipated transient, or 2) an accident (such as LOCA) without manual shedding of any electric loads.
b) Determining if there are any events or conditions which could result in the simultaneous or consequential loss of both required circuits from the offsite network to the onsite electric distribution system and thus violating the requirements of GDC 17.
The August 8,1979 letter included staff guidelines for performing the required voltage analysis and the licensee was further required to perform a test in order to verify the validity of the analytical results. VEPC0 responded by letters dated August 7, 1979, August 16, 1979, October 29, 1979, January 20, 1982, February 26, 1982 May 20, 1982, June 4, 1982, July 1, 1982, October 26, 1982, June 7, 1983, October 14, 1983, January 20, 1984 and May 15, 1984.
A detailed review and technical evaluation of the submittals was performed by EG&G under contract to the NRC, with general supervision by NRC staff. This work is reported by EG&G in Technical Evaluation Report (TER), " Adequacy of Station Electric Distribution System Voltages, North Anna Power Station, Units 1 and 2 " dated July 1982 (attached). We have reviewed this report and concur i
in the conclusions that the offsite power system and the onsite distribution system, except for startup voltage for some MOVs and operating voltage for some contactor coils, are capable of providing acceptable voltages for worst case station electric load and grid voltages.
By letter dated May 15, 1984, VEPCO stated that recent studies and voltage analyses show that SI or CDA activated POVs originally specified to start at 90% of rated voltage will start satisfactorily at 80% of rated voltage. With regard to contactor coils, the licensee states that additional testing is reouired to determine the effect of overvoltage on these coils. VEPC0 stated that these test results would not be available for NRC review until October 1984. The NRC staff will review the contactor coils test results under Plant Specific OR Action Items when this information becomes available.
T-- o C 6pf-
EVALUATION CRITERIA The criteria used by EG8G in this technical evaluation of the analysis includes GDC 5 (" Sharing of Structures, Systems, and Components"), GDC 13
(" Instrumentation and Control"), and GDC 17 (" Electric Fower Systems") of Appendix A to 10 CFR 50; IEEE Standard 308-1974 (" Class IE Power Systems for Nuclear Power Generating Stations"), ANSI C84.1-1977 (" Voltage Ratings for Electric Power Systems and Eouipment - 60 Hz"), and the staff positions and guidelines in NRC letter to VEPC0 dated August 8, 1979.
ANALYSIS AND TEST FEATURES VEPCO analyzed each offsite power source to the onsite distribution system under maximum grid voltage (535 Ky) and minimum load and minimum grid voltage (505 Kv) and maximum load conditions. To insure that the worst case conditions were analyzed, various conservative assumptions and scenarios were postulated. The following is a list of the major assumptions used for the analysis:
- 1) All Unit 2 loads, Unit 1 accident shutdown loads, and intake structure loads were assumed to be supplied by Reserve Station Service Transformers (RSSTs). Shutdown loads for Unit I can be supplied via Unit Station Service Transformers (USSTs) through backfeeding from the switchyard.
- 2) No delay in transfer of non-safety buses from USSTs to RSSTs was assumed under reactor trip condition. A delay of 30 seconds is experienced under actual condition.
- 3) All motors required to start on a safety injection (SI) or containment depressurization actuation (CDA) signal were started at t = 0. None were assumed to be running prior to the analysis.
- 4) No manual load shedding or reduction in motor current due to decreased pump load was assumed.
- 5) All anticipated modifications were incorporated into that analysis.
The worst case Class IE equipment terminal voltages occur under the following conditions:
! 1) The minimum steady-state voltage occurs at 4160V eouirment when the offsite grid voltage is at its anticipated minimum (505 Kv), containment depressurization actuation (CDA) in Unit 2, and Unit 1 generating at 21.5 Kv.
! 2) The minimum steady-state voltage occurs at 480V equipment when the offsite grid voltage is at its minimum (505 Kv), CDA in Unit 2, and Unit I trips.
l i
i j
i i, -
The minimum transient voltage occurs on Class IE equipment when offsite i f 3)
' grid voltage is at its minimum (505 Kv), CDA in Unit 1 and concurrent transfer of Unit 2 non-safety load to the reserve transfomers.
j The maximum steady-state voltage occurs at 4160V and 480V load center
- 4) buses when gru voltage is at its maximum (535 Ky), Unit 1 in refueling I
mode and Unit 2 is at 100% power; all safety buses are fed via preferred offsite feeder through the RSSTs. All non-safety buses are fed from l their respective USSTs.
The voltage analysis showed that, under the worst case minimum grid v'oltage i and maximum load condition, the voltage to Class IE motor operated valves ,
- (MOVs) did not meet the minimum starting voltage (90% of 460V) requirement. ;
The licensee is presently in the process of determining through the valve and i 1
' motor operator manufacturers if the SI or CDA activated MOVs originally specified rated voltage.
to operate at 90% rated voltage can be rerated to ope cannot be rerated below 90% with motor operators that are rated for 80%
starting voltage. .In addition, VEPC0 is comitted to determine through the valve manufacturer the compatibility between the 80% starting voltage and the l
- valve's torque requirement. It is possible that, under the worst condition j anal ~yzed, when starting large motors, these MOVs could become subjec "
i voltage transient as low as 68.1% at T=0.
i MOVs that are rated for 80% starting voltage will start within a 4 second time
- period. Starting within this time frame ensures MOVs operation and would not cause any equipment damage.
j By letter dated May 15, 1984 VEPC0 stated that completed studies and voltage analyses show that the SI or CDA activated MOVs originally specified to start l
at 90% of rated voltage will start satisfactorily at 80% of rated voltage.
l
' The licensee also stated that various MOV enhancements including installation of new torque switch limiter plates are planned for implementation in the near t l
future. Installation of new limiter plates further ensures operation of the above MOVs at the minimum analyzed voltage, l
Under the maximuen grid voltage and light load condition, the voltage analysis i
i showed ratings. that all 4 XV and 480V buses are within 10% of 4000 i
the 110% maximum rating by 7%.
The impact of this overvoltage on the service life of those contactors which supply power to MOVs would be minimal due to
! the short time (a few minutes for the MOV to change state) exposure of these coils to overvoltage. This short time exposure to overvoltage minimizes the i
Also, a number of i probability of contactor coil or motor insulation damage.MCCs ar I
temperature below 40'C, thereby further reducing the possibility of coil
, As an added precaut'on, the licensee conducts l, damace caused due to heat.
resistance and insulation tests during each refueling period to monitor coil I failure.
l I____ . _ _ _ _ _
The licensee, through the starter manufacturer, is continuing to investigate the effects of overvoltage on contactor coils. By letter dated May 15, 1984, VEPCO stated that additional tests are reouired to determine the effect of overvoltage on contactor coils and stated that the test results would not be available to NRC for review until October 1984. The NRC staff will review the above test results under Plant Specific OR Actions when this information becomes available.
In view of the above and the licensee's established procedures to maintain the 500 Kv grid voltages below 535 Kv (max. voltage used for the analysis), the staff concludes that, even under the rare instances that overvoltage could be present, the damage to the Class IE equipment would be minimal. Therefore, we find the present overvoltage surveillance program to be acceptable subject to the submittal of the licensee's finding of overvoltage impact on the contactor coils from starter manufacturer or through testing and/or analysis.
DESIGN CHANGES As a result of voltage analysis VEPC0 has proposed to implement the following design changes:
- 1) Rerate or replace if necessary motor operators of valves that are activated by an SI or CDA signal to assure their starting within acceptable time frame at minimum voltage conditions. VEPCO's investigations into the operating characteristics of these MOVs indicate that 68 units may be rerated for starting at 80% voltage, two may be rerated for 84% - 86%, one cannot be rerated below 90%, and 57 units are still under investigation. Prior to any rerating, VEPC0 must determine the compatibility between the motor operator rerating and valve torque requirement through the valve and motor operator manufacturers. VEPCO's analysis indicates that 80% rated motor operators will start within 4 seconds after the initial accidenc. Starting within this time frame will preclude any equiperent damage. VEPCO has completed the above investigation and concludes that the above MOVs will start satisfactorily at 80% of rated voltage. The licensee also stated that they plan to install in the near future new torque switch limiter plates on the MOVs.
- 2) Install overvoltage monitors and alarms en all 4 Kv and 480V Class IE buses.
- 3) Modifytheloadtapchangers(LTCs)ontheRSSTstoeliminateresponse delays in the LTCs for the first three minutes following either an SI or a CDA in either unit or on transfer of the Unit ? non-safety loads to the reserve transformers.
- 4) Install a generator breaker on Unit 1 to provide an additional inanediately available source of offsite power through the Unit station transformers. This has been completed.
J 4
- 5) Modify the existing control logic for Unit I and Unit 2 nonnal to emergency bus ties to eliminate the automatic transfer feature of the '
emergency buses from the reserve station service (RSS) feeders to the normal bus feeders supplied by the USSTs for Unit 1 and delete the i proposed automatic transfer of Unit 2 emergency buses from the RSS a feeders to the normal bus feeders.
- 6) Remove automatic switchina between offsite power sources in order to provide direct transfer from offsite power to the respective diesel generators under loss of voltage / degraded voltage conditions. All transfers between normal and alternate offsite power sources will be manual.
4
- 7) Install throwover switches in the secondary leads of 34.5 Kv switchyard transformers to provide redundancy of power source in case of loss of one transformer. This has been completed. l
- 8) Provide automatic tripping of 34.5 Kv current limiting reactors following an SI or CDA on either unit when a unit's normal buses are fed by Reserve
- Station Service Transformers.
- 9) Install disconnect switches in all secondary leads of 34.5 Kv switchyard service transformers and remove the secondary leads of one transformer
.! from the common trough and install it in a conduit to prevent the possibility of sinultaneous loss of both offsite power sources. This has l been completed.
- 10) Provide automatic load shedding capabilities when all of Unit 2 loading is on the Reserve Station Service Transfonners and SI or CDA occurs on Unit 1.
- 11) To prevent overloading the RSST B or C due to loss of one or the other '
when the tie breakers on the secondary sides of these transfonners are l
closed, all circulating water pumps of the unit experiencing the accident i are automatically shed when an SI or CDA occurs. I i 12) Block the auto starting of large non-IE motors, when the station service bus feeding the motors is supplied from the same source as the emergency bus of a unit experiencing an SI or CDA.
4 CONCLUSION i
We have reviewed the EG&G Technical Evaluation Report and concur in the findines that: .
- 1. The proposed modifications will insure North Anna 1 & 2 compliance with GDC 17 requirements.
- 2. The test used to verify the analysis was valid and showed that analysis to be conservative.
b =
. . _ _ , . - _ _ _ _ ._..m.._ . - _ _ , _ . . _ , . . _ _ . . _ _ _ _ _ - , _ . _ . - . . - . _ . , _ _ . . . . _ .
- 3. All SI or CDA activated motor operated valves motor operators need to be rerated or replaced to ensure proper valve operation under some In addition, worst case condition analyzed. This has been completed.
contactor coils may be subjected to overvoltage of approximately 7%
beyond the maximum 110% design rating under the above worst case condition. Other than the above, all Class IE equipment will be supplied with acceptable voltages under all projected combinations of plant load and normal offsite power grid conditions, including an accident in one unit and the safe shutdown of the other unit.
Due to the voltage problems associated with the above mentioned HOVs and contactor coils the licensee has connitted:
A)
To determine through the valve and motor operator manufacturers the possibility of rerating or replacing if necessary those motor operators which may not be provided with sufficient starting voltage in order to l ensure proper valve actuation. This has been completed.
B)
To determine through the starter manufacturer the effect of overvoltage on the contactor coils. The licensee will be conducting tests to determine the effect of 20% overvoltage on the contactor coils, and the results will be submitted for staff review in the near future.
We require that the licensee provide the results of the completed studies or findings to NRC for review. In addition, if these studies show that replacement is required for any motor operator, we require that an Licensee implementation schedule for these replacements also be provided.
studies and analyses show that the MOVs discussed under item 3A above are Therefore, motor operator capable of starting at 80% rated voltage.We, therefore, find the North Anna 1 & 2 replacement was not necessary.
' design to be acceptable with respect to adequacy of station electric distribution system voltages sub,iect to completion and resolution of Item 38 discussed above, i
Principal Contributor:
H. Emami, DSI
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