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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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l VIRGINIA ELECTRIC AND power COMPANY HIcnwonn,VInoINIA 20261 W.L.Srawaar x2c$*[.$".fr7.. October 18, 1984 Serial No. 253E EC:BSD:baj:2002N Docket Nos. 50-338 339 License Nos. NPF-4 NPF-7 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regu'ation Attention: Mr. James R. Miller, Chief Operating Reactoi s Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
GENERAL DESIGN CRITERIA 17 ANALYSIS VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNIT N05. 1 AND 2 Your letter of April 17, 1984 requested that Vepco provide a monthly status update for completing remaining open items regarding General Design Criteria 17 Analysis for North Anna Units 1 and 2. The attachment of this letter provides a complete report on our GDC-17 compliance for Units 1 and 2.
As we stated in our June 4,1982 letter, Serial No. 316, we plan to have completed the modifications by the second refueling outage of each unit after September 1, 1982. This means we will complete the regulatory commitments, except motor control center contactor coils, by the end of the present Unit 2 outage.
The control circuitry for the new load sheds, the blocking of auto starting of large non-1E motors, tripping of the 34.5 KV reactors and the bypassing of the time delays on the load tap changers (LTCs) of the Reserve Station Service Transformers (RSSTs) is integrated as a single installation and is cross tied between the two units. The work presently being completed on Unit 2, especially work within control cabinets, could result in unnecessary accidental activation of these systems. Therefore, the control circuitry for these modifications for units 1 and 2 will not be energized until Unit 2 begins its startup. The GDC-17 analysis for North Anna predicted worst case voltage profiles for a simultaneous Unit 1 Containment Depressurization Actuation and a ONo0b$g g\
g PDR '
l s\r
e VamormA Etscienc awn Pows COMPANY 70 trip of Unit 2 with the Unit 2 loads transferring from the Station Service Transformers to the RSSTs. Since any Unit 2 loads running prior to start up will already be loaded on the RSSTs, the LTCs of the RSSTs will have already adjusted for this load. The voltage fluctuation on the Reserve Station Service
-buses, based on our GDC-17 analysis assumptions, will be minimal due only to starting of emergency bus loads for Unit 1.
The motor control center contactor coil test results are scheduled to be available to Vepco in early February 1985 and our final report will be available in March 1985. This item is further discussed in the attachment to this letter.
We will continue to provide you with updates per your request.
Very truly yours,
% (w ~
W. L. tewart Attachment BSD/baj i cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. M. W. Branch NRC Resident Inspector North Anna Power Station i
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fiORTH ANNA UNIT 1 STATUS AND E HEDULE FOR GDC-17 ANALYSIS COP 911TMENTS Item I: Operating Restrictions:
Commitment A: Generator bus voltage must be maintained at an adequate level to ensure acceptable voltages are maintained on a "J" emergency bus fed frota a station service bus.
Status A: There is no "J" bus fed from a Unit 1 station service bus at present. If a tie is installed, an operating procedure will be implemented for Unit 1.
Commitment B: Load on a station service bus must be limited when a "J" emergency bus is fed from it.
Status B: There is no "J" bus fed from a Unit 1 station service bus at present. If a tie is installed, an operating procedure will be implemented for Unit 1.
Comitment C: If Vepco installs the Unit 2 emergency to station service bus ties, then, when the emergency bus 2H is transferred to and fed from station service bus 2C, emergency bus 2J must be transferred to a power source other than Reserve Station Service Transformer C within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Status C: This commitment does not affect Unit 1.
Comitment D: The existing load shed, which is initiated when both units load to the Reserve Station Service Transformers (RSSTs), will be enabled at all times when 1) one unit is on line and the other unit is in startup, 2) both units are on line, and 3) both units are in startup.
Status D: The existing load shed is enabled at all times when 1) one unit is on line and the other is in startup, 2) both units are on line, or 3) both units are in startup.
Comitment E: A program will be established to ensure station operations is consistent with the assumptions made in the GDC-17 analysis. The program will specify the appropriate corrective actions to be taken if transmission system voltage goes outside the range of 505 KV to 535 KV.
Status E: Vepco has implemented a system-wide operating procedure to address this comitment and has provided these procedures in our letter of July 1,1982 (Serial No. 374).
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Item II: Modifications Commitment A: Rerate all motor operated valves (MOVs) to assure starting at predicted voltages. Motors on certain MOVs may have to be replaced. (The full scope for M0V rerating/ motor replacement is still being developed.) In our February 26, 1982 letter, Serial No. 076, we stated 128 MOVs were involved. In January 20, 1984 letter, Serial No. 038, we stated only 56 MOVs would be required to operate dcring the period when voltage is between 80 and 90 percent.
Status A: Motor operated valves, which are required to operate during an emergency when the voltage on the 480 volt bus is predicted to be between 80 and 90 percent of the bus voltage, have been reviewed and analyzed. The results of the review and analysis indicated that the motors for these valves will operate at the reduced voltage predicted by our GDC-17 analysis.
Commitment B: Install a load shed scheme to remove certain motors when Unit 2 transfers to the RSSTs simultaneously with a Safety Injection (SI)orContainmentDepressurizationActuation(CDA) occurrence on Unit 1.
Status B: The installation of the new control circuitry for Unit I has been completed. The control circuitry for this item and items II C, E, F, and H is integrated and was issued as a single design. The control circuitry ties between Unit 1 and Unit 2.
The control circuitry affects loads on Unit 2 and initiating contacts come from both Unit I and Unit 2. Until Unit 2 completes its refueling and starts up, this circuitry does rot need to be energized since the Unit 2 loads will be fed from the Reserve Station Service Transformers (RSSTs). These loads will not be required to transfer to RSSTs. The RSST load tap changers, therefore, do not have to react to Unit 2 loads to return the voltage to the normal level.
Commitment C: Trip the 34.5 KV reactors in the switchyard when an SI or CDA occurs on either unit.
Status C: The installation of new control t.ircuitry for the Unit I has been completed. The control circuitry for this item and Items II B, E, F, and H is integrated and was issued as single design.
The control circuitry which initiates the trip of the reactors can be initiated in either the Unit 1 or Unit 2 control cabinet'..
Work on Unit 2 has not been completed and this work may cause accidental operation. Therefore, we will not energize this circuitry until Unit 2 begins its startup. Our GDC-17 analysis did not issume any benefit from tripping the 34.5 KV reactors since t..e reactors are not energized at all times. Therefore, voltage rise benefits due to tripping them were not included in the analysis, i
76-BSD-2000N-4
I Comitment D: Install overvoltage alarms on 4160 and 480 volt emergency buses I to alert station personnel to the need to protect equipment against high voltage.
Status D: The modification has been completed and placed in service on Unit 1.
Commitment E: Modify RSST load tap changer (LTC) control to eliminate all delays in LTC responses during the first three minutes of an SI or CDA event on either unit and on transfer of unit load to the RSS system.
Status E: The control circuitry for this item and items II, B, C, F, and H is integrated and was issued as a single design. The installation of the new control circuitry for Unit I has been completed. We have encountered some problems with the new LTC control cards and are actively pursuing resolution with the vendor.
The control circuitry which initiates the elimination of delays in the LTC responses can be initiated in either the Unit 1 or Unit 2 control cabinets. Work on Unit 2 has not been completed and this work may cause accidental operation. Therefore, we will not energize this circuitry until Unit 2 begins its startup.
Unit 2 will be fed from the Reserve Station Service during the time prior to its return to service. This means the LTC will not need to react to the addition of Unit 2 loads. The addition of Unit 2 loads to the RSSTs were assumed in our analysis and these additional loads are a primary reason for bypassing the time delays.
We believe the problems posed by accidental operation of the LTC time delay bypass exceeds the value of bypassing the time delay prior to Unit 2 startup.
Commitment F: Block the auto starting of large non-IE motors, when the station service bus feeding the motor is fed from the same source as an emergency bus of a unit experiencing an SI or CDA.
Status F: The installation of the new control circuitry for Unit I has been completed. The control circuitry for this item and items II, B, C, E, and H is integrated and was issued as a single design.
The control circuitry whir.h initiates the blocking of the auto starting of certain large non-IE motors is initiated based on signals from both units. Work on Unit 2 has not been completed, and this work may cause accidental operations. Therefore, we will not energize this circuitry until Unit 2 begins its startup.
This blocking of auto starts on Unit 1 would occur if Unit 1 loads transferred to the Reserve Station Service while Unit 1 or Unit 2 SI or CDA signals were activated. The blocking of auto starts for Unit I station service bus "B" would occur if emerg ncy bus "1H" is fed from it and Unit 1 SI or CDA signals were activated.
76-BSD-2000N-5
We believe the problems posed by accidental operation of the auto start blocking scheme exceeds the value of the auto blocking circuit.
Commitment G: Eliminate the automatic transfer of emergency buses from the Reserve Station Service to the Normal Station Service.
Status G: The modification of these control circuits has been completed and placed in service on Unit 1.
Commitment H: When a unit experiences an SI or CDA and the "G" bus tie breaker is closed, then all circulating water pumps on the unit experiencing the accident will be tripped.
Status H: The installation of the new control circuitry for Unit I has been completed. The control circuitry for this item and Items II B, C, D, and F is integrated and was issued as a single design.
The control circuitry which initiates the tripping of circulating water pumps when the "G" bus tie breaker is closed and either unit experiences an SI or CDA can be initiated by control circuitry in either unit. Work on Unit 2 has not been completed and this work may cause accidental operation of this load shed.
We, therefore, will not energize this circuitry until Unit 2 begins its startup.
In order to minimize the need for this load shed prior to Unit 2 startup, the station will make all reasonable efforts to keep the "G" bus tie breaker open prior to Unit 2 startup.
l Item III: Additional Comnitments Commitment A: In our letter of July 7,1983 (Serial No. 326), Vepco stated that tests would be performed on motor control center contactor coils
'j to determine the effects of overvoltage. In our letter of March 26,1934 (Serial No. 326A), we stated our current schedule for i completing the overvoltage test by May, 1984, obtaining a test report in June, 1984, and providing results to the NRC in July 1984.
Status A: 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 the NRC in March, 1985.
Based on the aging which has been completed, the life of the j contactor coils exceeds 10 years. Three of the ten size 1 coils have failed during thermal aging. We are presently evaluating the effect of this on test completion. We continue to believe that this is not a serious concern and that no imediate corrective actions will be required. However, we do anticipate replacement of size 1 coils may be required at some future date.
t 76-BSD-2000N-6
NORTH ANNA"JNIT 2 ,
STATUS AND N17 MALYSIS 5e } , '
COPDilTMENT5 ;
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Item I: Operating Restrictions: '
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Commitment A: Generator bus voltage must be maintained'4t an adequate level t6/'
ensure acceptable voltages are maintained on a "J" emergency but, fed from a station service bus.
Status A: An operating procedure has been implemented to comply'with this -
requirement for Unit 2.
- Commitment 8: Load on a station service bus"nust be limited when a "J" m emergency bus is fed from it.'. i1 ,
Status B: An operating procedure has been implemented to comply with this requirement for Unit 2.
Commitment C: If Vepco installs the Unit 2^ emergency to station service bus -
I ties, then, when the emergency bus 2H is trantferred to and fed from station service bus 2C, emrgency bus 2J must be transferred to a power source other than Reserve Station Service Transformer C within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Status C: Vepco has not installed the Unit 2 Emergency to' stat'io service bus ties and their installation is not presently scheduled. ;
Vepco will implement an operating procedute to comply with ahis
, requirement if bus ties are installed as oesigned.
Commitment D: The existing load shed, which is initiated when both units load to the Reserve Station Service Transformers (RSSTs), will be
- enabled at all times when 1) cne unit is on line ind the other unit is in startup, 2) both units are on line, and 3) both units are in startup. ,
Status D: Theexistingloadshedisenabledatalltimeswhen1)oneunit is on line and the other is in startup, 2) both units are on !
j line, or 3) both units are in startup.
Commitment E: A program will be establish)d to ensure station operations is consistent with the assumptions made in the GDC-17 analysis. The program will specify the appropriate corrective actions to be taken if transmission system voltage goes outside the range of 505 KV to 535 KV. <
i Vepco has implemented a system-wide operating procldure to Status E:
address this commitment and has provided these procedures in our (:
letter of July 1, 1982 (Serial No. 374). v i
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76-BSD-2000N-7 /, '
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I Item II: Modifications Commitment A: Rerate all motor operated valves (MOVs) to assure starting at predicted voltages. Motors on certain MOVs may have to be replaced. (The full sco still being developed.) pe Infor ourMOV rerating/
February motorletter, 26, 1982 replacement Serial is No. 076, we stated 128 MOVs were involved. In our Januar) 20, 1984 letter Serial No. 038, we stated only 56 MOVs would be required to operate during the period when voltage is between 80 and 90 percent.
Status A: Motor operated valves, which are required to operate during an i emergency when t..e voltage on the 480 volt bus is predicted to be t'etween 80 and 90 percent of the bus voltage, have been reviewed and analyzed. The results of the review and analysis indicated that the motors for these valves will operate at the reduced voltage predicted by our GDC-17 analysis.
Commitment B: Install a load shed scheme to remove certain motors when Unit 2
[ transfers to the RSSTs (SI) or Containment simultaneously Depressurization with a(CDA Actuation Safety) Injection occurrence on Unit 1.
Status 8: The control circuitry for this item and items II C, E F, and H is integrated and was issued as a single design.
The control circuitry affects loads on Unit 2 and initiating contacts come from both Unit 1 and Unit 2. Until Unit 2 completes its refueling and starts up, this circuitry does not need to be energized since the Unit 2 loads will be fed from the
. Reserve Station Service Transfonners (RSSTs). Unit I outage i related work has begun and is scheduled to be completed during the refueling outage. The new circuitry will not be considered operable until the end of the Unit 2 outage.
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Comitment C: Trip the 34.5 KV reactors in the switchyard when an SI or CDA
,/ occurs on either unit.
Status C: The control circuitry for this item and items !! B, E, F, and H is integrated and was issued as a single design.
Unit 2 outage related work has begun and is scheduled to be
- /'
.j
' completed during the refueling outage. The new circuit ~ will
$ not be considered operable untti the end of the Unit 2 ge.
The control circuitry which initiates the trip of the reactors can l,e initiated in either the Unit 1 or Unit 2 control cabinets.
Work on Unit 2 has not been completed and this work may cause i r, accidental operation. Therefore, we will not energize this
- e ,. circuitry until Unit 2 begins its startup. Our GDC-17 analysis
, did r.ot assume any benefit from tripping the 34.5 KV reactors
. since the reactorr are not energized at all times. Therefore,
/,d voltage rise benefits due to tripping them were not included in the analysis.
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) 76 850-2000N-8
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Commitment D: Install overvoltage alanns on 4160 and 430 vol.d emergency buses to alert station personnel to the need to protect equipment against high voltage.
Status: D The Design Change Package for Unit 2 is at North Anna and outage related work has begun and is seneduled to be completed.during the present refueling outage. '
Commitment E: Modify RSST load tap changer (LTC) control to eliminate all delays in LTC responses during the first three minutss of an SI or CDA event on either unit and on transfer of unit load to the RSS system.
1 Status E: The control circuitry for this item and items II B, C, F, and H is integrated and was issued as a single design.
Unit 2 outage related work has begun and is scheduled to be completed during the refueling outage. The new circuitry will not be considered operable until the end of the Unit 2 outage.
We have-encountered some problems with the new LTC control cards and are actively pursuing resolution with the vendor.
The control circuitry which initiates the elimination of delays in the LTC response can be initiated in either Unit 1 or Unit 2 control cabinets. Work on Unit 2 has not been completed and this work may cause accidental operation. Therefore we will not '
energize this circuitry until Unit 2 begins its startup. Unit 2 will be fed from the Reserve Station Service during the t_ime prior to its return to service. This means the-LTC will not need to react to the addition of Unit 2 loads.
We believe the problems posed by accidental, operation of theLLTC time delay bypass exceeds the value of bypassing the time delay prior to Unit 2 startup.
Commitment F: Block the auto starting of large non-IE motors, when the station service bus feeding the motor is fed from the same source as an emergency bus of a unit experiencing an SI or CDA.
Status F: The control circuitry for this item and items II B, C, E' and H ,
is integrated and was issued as a single design. .
Unit 2 outage related work has begun and is scheduled.to be completed during the refueling outage. The.new! circuitry will not be considered operable until the end of the Unit 2 outage.
The control circuitry which initiates the blocking of the auto starting of certain large non-IE motorr is initiated based on signals from both units. Since work on Jnit 2 has not been completed, and this work may cause accidental operations, we will not energize this circuitry until Unit 2 begins its startup.
- Commitment G
- Eliminate the automatic transfer of emergency buses from the Reserve Station Service to the Normal Station Service, s
s 76-BSD-2000N-9 m
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l Status G: This does not apply to_ Unit 2.
Commitment H: When a unit experiences an SI or CDA and the "G" bus tie breaker is closed, then all circulating water pumps on the unit experiencing the accident will be tripped.
Status H: The control circuitry for this item and items II B, C, E, end F is integrated and was issued as a single design.
Unit 2 outage related work and testing is nearly completed and is scheduled to be completed during the refueling outage. The new circuitry will not be considered operable until the end of the Unit 2 outage.
The control circuitry which initiates the tripping of circulating water pumps when the "G" bus tie breaker is closed and either unit experiences an SI or CDA can be initiated by control circuitry in either unit. Since work on Unit 2 has not been completed and this work nay cause accidental operation of this load shed, we will not energize this circuitry until Unit 2 begins its startup.
Item III: Additional Commitments Commitment A: In our letter of July 7,1983 (Serial No. 326), Vepco stated that tests would be performed on motor centrol center contactor coils to determine the effects of overvoltage. In our letter of March 26,1984 (Serial No. 326A), we stated our current schedule for completing the overvoltage test by May,1984, obtaining a test report in June, 1984, and providing results to the NRC in July 1984.
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Status A: 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 the NRC in March, 1985.
Based on the aging which has been completed, the life of the contactor coils exceeds 10 years. Three of the ten size 1 coils have failed during thermal aging. We are presently evaluating the effect of this on test completion. We continue to believe that this is not a serious concern and that no immediate corrective actions will be required. However, we do anticipate replacement of size 1 coils may be required at some future date.
6 76-BSD-2000N-10 4
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