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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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VIROIMrA E r.ncTarc AND I- 7W E R CO M PA NY R i c asw o n o.V: mo r n A23261 ,,
o C b '
3 June 29, 1979 f- ,M w [J Mr. James P. O'Reilly, Director Serial No.
P0/NOS: jh 274B/041479 [
- Of fice of Inspection and Enforcement ..
U. S. Nuclear Regulatory Commission Docket Nos. 50-338 __ ,
Region II 50-339 am 101 Marietta Street, Suite 3100 License Nos. NPF-4 Atlanta, Georgia 30303 CPPR-78
Subject:
IE Bulletin 79-06A Revision 1 North Anna Power Station Unit Nos. I and 2
Dear Mr. O'Reilly:
Our letter of April 26, 1979, (Serial No. 274/041479), provided responses to items 1 through 13 of IE Bulletin 79-06A, " Review of Operational Errors and System Misalignments Identified During the Three Mile Island Incident." This letter provides addtional information on bulletin items 2, 3, 4, 7d, 8, 9, 10, 11, and 12 as requested by your staff.
Item 2 The primary operator action required to prevent the formation of voids continues to be to insure the proper initiation and continuing performance of the engineered safety features equipment. Abnormal procedur AP-44, "Luss of Reactor Coolant Systea Pressure", was written to provide specific operator actions for this type of transient.
Emergency procedures have been revised to provide guidance for insuring forced flow by verifying margin to saturation conditions and by observing reactor coolant pump amps, loop flow indications and loop delta T's. These procedures include specific precautions regarding maintenance of at least 50 F subcooling in the primary system.
Item 3 The pressurier level bistables which input to safety injection initia-tion are placed in the trip mode by an Abnormal Procedure (AP). Trip status lights on the control board confirm that the action has been completed.
Operating procedures will be revised by July 1, 1979 to include a verification that these bistables are in the trip mode prior to placing the unit in opera-tion. ,
Item 4 Containment isolation occurs automatically upon initiation of safety injection. Containment isolation also occurs manually from operator action.
Technical Specifications Table 3-6-1 is attached. This table lists valves that receive a Containment Isolation signal, and describes the function of each valve.
Slb 282
'4908 {gigKMAL COPY
. vanum. Euanic 4 o Powns courm to Mr. James P. O'Reilly Page 2 Item 7d Specific parameters are:
1.
Decreasing pressurizer pressure but not necessarily a decreasing pressurizer level.
- 2. Increasing pressurizer relief tank pressure, level, temperature, and pressurizer relief line high temperature.
- 3. Automatic Action.
- a. Pressurizer backup hea ;4 on
- b. PORV Isolation
- c. Reactor trip from Low Pressurizer Pressure (above P-7)
- d. Turbine Trip from Reactor Trip (above P-7)
- e. Sa fety Injection The applicable procedures have been cevised.
We are partic ws'ing, with other utilities, in a Westinghouse users group ef fort to review and improve all emergency and abnormal proce-dures based on lessons learned from the TMI incident. We will continue to revise and improve our procedures as part of this effort.
Item 8 The review as requ; red by Bulletin item 8 was conducted by reviewing valve posit;,ns concurrently with those procedures that check or mani-pulate those valves.
Thus, we believe we have performed the requested review.
Additionally, North Anna Technical Specifications already contain re-quirements to check valve position for valves not locked, sealed or othe rwise maintained in position. We do not beliese the periodic surveillance of locked valves will significantly enhance valve align-ment verification. Furthermore, many of our valves are locked because of inaccessibility.
Item 9 A review of Technical Specification Table 3.6-1 will provide the missing information to make our response complete.
Item 10 As stated in our response, the Shift Supervisor is the authority level for removing and returning equipment for service.
An example of equipment made inoperable for testing is the periodic testing of pumps. The test flow path is a recirculation path. Con-sequently, the normal discharge path is isolated. We do not believe this constitutes a significant problem and consider our initally proposed resolution to be acceptable. Our proposed resolution did require revision to appropriate procedures and they have been revised to imp!ement our proposal.
~ ,
ai3 ') 0 b
ViuotwsA ELECW C AMD Put EM COMPANY fo Mr. James P. O' Reil 1Y Page 3 Item 12 A preliminary review of Hydrogen Recombiner operation after . LOCA will be conducted with an anticipated completion date of July 31, 1979 and a scheduled completion date for final review of August 31, 1979.
We are required by Technical Specifications to maintain thz hydrogen removal equipment operable. Revisions to operating procedures for removal of hydrogen will be completed by August 31, 1979.
Very truly yours, f
C. M. Stallings Vice President Power Supply and Production Operations cc: NRC Office of Inspection and Enforcement Division of Reactor Operations Inspe tion Washington, D.C. 20555 3 _ ..)
. j TABLE 3.6-1 d= .
CONTAINMENT ISOLATION VALVES h
ISOLATION TIME N VALVE FUNCT!0r; (SEC.)
E NUMBER
[ A. PHASE "A" ISOLATION Reactor Coolant Pump Seal llater Return 10
% 1. MOV-1380 Reactor Coolant Pump Seal Watec Return 10
- 2. MOV-1381 Reactor Coolant Letdown Line 10
- 3. IICV-1200A Reactor Coolant Letdown Line 10
- 4. IICV-1200B Reactor Coolant Letdown Line 10
- 5. IICV-1200C Reactor Coolant Letdown Line 10
- 6. TV-1204 Nitro 0eq to Pressurizer Relief Tank and SI 60
- 7. TV-S 1100 u .
Accumulators Primary Dra sfer Tank Pump Discharge 60
[ 8. TV-DG100A Primary Drai ,1ransfer Tank Pump Di:, charge 60 h 9. TV-0G1008 Containment Sump Pump Discharge to Waste 60
- 10. TV-DA100A' Drain Tanks Containment Sump Pump Discharge to Waste 60
- 11. TV-DA1008 ui Drain Tanks 60 h 12. TV-BD100A Steam Generator Blowdown 60
- 13. TV-DD1008 Steam Generator Blowdown tv 14. Steam Generator Blowdown 60 00 TV-00100C p
- 15. TV-DD1000 Steam Generator Blowdown 60 4 u-
- 16. TV:00100E Steam Generator Blowdown 60 i
- 17. TV-BD100F Steam Generator Blowdown 60
S y VALVE _ TABLE 3.6-1 { Cont.)
3 NUMBER E.'
fg G.
STEAM LINE ISOLATION fuNCTI0t{
ISOLATION TIME (SEC.)
- 1. . J -MS-101 Af G' Main Steam Line Trip Valve m 2 TV-MS-1018# 5 Main Steam Line Trip Valve
- 3. TV-MS-101C# 5 Main Steam Line Trip Valve 5
M u
r i
ai
<v
'N (
.}
\:
t
~ ,; r . . .
.c., m ..,, , , . :, , . .-
a :
TABLE 3.6.-l (Cont.)
b VALVE 150LATI0ti TIME 5! NUMBER FL'ilCTION (SEC.)
E H. RELIEF
- l. RV-1203 Letdown Line Relief Valva NA
= -
G M
a k!
# Valve not subject to Type "C" leakage test.
*ValvepositionmaintaI,iedbyadministrativecontrol ilA - Not applicable
** Weight loaded check valve tri m . A co m N
h O O 63
TABLE 3.6-1 (Cont.)
ISOLATI0tt TIME h VALVE (SEC.)
FUNCTION g hul' ale R tiA
- 30. 1-QS-ll** Quench Spray Pump Discharge NA
- 31. 1-RS-27** Recirculation Spray Pump Discharge ,
E Rectruclation Spray Pump Discharge tiA
(; 32. 1-RS-18**
- NA
- 33. 1-VP-12 Air Ejector Vent
- 34. 1-S1-90 High liead Safety Injection to RCS Except Baron NA Injection Line
- 35. 1-51-201 High lleod Safety Injection to RCS Except Doron tiA Injection Line M. 1-SI-85 High ite. Safety injection to RCS Except Boron R Injec*.ian Line flA T fiA g 37. 1-FW-47# Feedwater to Steam Generators flA
- 38. 1 -FW-lll # Feedwater to Steam Generat' ors tiA
- 39. 1-FW-79# Feeawater to Steam Generators NA
- 40. 1 rd-50# Chemical Feed Lines NA
- 41. 1-WT-66# Chemical Feed Lines ,
f.A
- 42. 1-WT-38# Chemical feed Lines w Auxiliary Feedwater to Steam Generator NA
- 43. 1-FW-68#
w Auxiliary feedwater to Steam Generator liA
- 44. 1 -FW-100# ,
HA i
',j 45. 1-FW-132# Auxiliary Feedwater to Steam Generator w CD
O ~
O M VALVE TABLE 3.6-1 (Cont.)
g NUMBER FUNCT10tl ISOLATION TIME
}" 14. 1-itC-18 _
(SEC.)
y; Discharge from Containment Atmosphere Clean-up System (llydrogen Recombiner)
=
- 15. 1-itC-14 NA w Discharge From Containment Atmosphere Clean-up System (llydrogen Recombiner)
~
- 16. 1-Cil-380s NA Reactor Coolant Pump Seal Water Supply
- 17. 1-C11-336# NA Re.ator Coolant Pump Seal llater Supply
- 18. 1 -Cit-3 Cu f fiA Reactor Coolant Pump Seal Water Supply g 19. 1-IA-149 NA Air Radiation Monitor Return T 20. 1-RC-149 NA lE Primary Grade Water to Pressurizer Relief Tank
- 21. 1-CH-330 NA Loop Fill Header
- 22. 1-IA-SS NA Instrument Air Line 23 1-S1-106 NA 24.
Nitrogen to Pressurizer Relief Tank and SI Accumulators 1-SI-206 NA d'
25 1-SI-207 LilSI Pump Discharge to Reactor Coolant SystemNAliot 1egs i
u' i ,j LilSI Pump Discharge to Reactor Coola'nt Systhm liot Legs 26 1-S1-195 HA i
$27 1-51-197 -
LilSI Pump Discharge to Reactor Coolant" System NA Cold Legs 1.
w 28 l'-SI-199 LilSI Pump Discharge to Reactor Coolant Syst'em' flA Cold Legs
- 29. 1-QS-19**
LilSI Pump Dircharge to Reactor Coolant System NA Cold Legs i h.
4 Quench Spray Pump Discharge - M.
6 j
NA
rd ... t. r e~ . ~ n " -
TABl.E 3.6-1 (Cont.)
ISOLAT10li TIME VALVE FutiCTI0ff (SEC.)
t1 UMBER M F. CliECK
!? 1. 1-CC-193 Component Cooling Water to Rl(R System and Excess Letdown lieat Exchanger tiA 5
- 2. 1-CC-198 Component Cooling Water to RilR System and Excess c- flA 5 .
Letdown lieat. Exchanger _ i,.i.., . , , . i i..,
a ,
liigh llead Safety Injection, '8oron 'Injdctfon to RCS '" tiA
~
- 3. 1-SI-79 ,,
i i,.. i ..
o
- 4. 1-CC-572 Component Cooling Water to Co,n,tairpept,Atr Recirgn i... ..
tiA lation Coils', i i.
- 5. 1,CC-559 ,, Component Cooling Water to C'ont ainment' Air 'Recircu' ' ' '
i.
tiA R lation Coils.. .i
+ i... ...
i ...... ..
? 6. 1-CC-546 ' Component Cooling Water to, Containment Air- -Recircu- '-
lation Coils; i i - .6 - ' ' liA M i I laa
Charging Line ',,
tiA
- 7. 1-Cil-322 i. r .... i. l .1 *
- i. n .
Component Cooling Water to Reactor Coolant Pu.nps t1A
- 8. 1-CC-154
. . . ... . i .:
' Component Cooling Water to Reactor Coolant Pumps itA
- 9. 1-CC-119 Component Cooling Water to ReactoriCoolant'Pusps' ilA m 10. 1-CC-8_4 ,.
Reactor Cnolant Pumps., Seal W,ater Return, i .i...,i .. . flA
& 11. 1-Cit-402 ,
Safety Injection Accumulator Hake Up tiA
- 12. 1-SI-110
, , , . i . I- .i p
- 13. 1-SI-185 liigh llead Safety Inj99 tion to RCS except Doron 4 a ,
In.1cction Line tiA m
,,, .. ,_i . . . ii.n, t;.. . . lot.4. 4 8
n,...i....i i.., in: .inon. h." " ("I-
i..:
m U O u
- i. Ii i i, I (i .. i t )
t i
I s el .1 .. . i 11 i TABLE 3.6-l_(Cont.) '
- i. . .ii.. .,u r,i,..i.,,,,,,, ,,,,,,, .,,,,
ISOLATION TIME e
(SEC.)
8 VALVE _
l -
- i. i t a" i FUNCT I0t{ te. . i i . ., i .. l i ..., ,.,,p,,,,,
y NUMBER _
itA x '- Containment Air Ejector. Suction., t.,.,,. , , . ,
i' i
- 17. TV-CV100*
g to RCS Except Doron NA 3
5 18. .MOV-1869A* ,,,.2
,iligh llead Safety Inject ion
'"8"i'"" - , '- .
J Injection'Line" IfA MOV-1836*
liigh llead Safety Injection to RCS Except Boron
- 19. Injection Line NA
- High llead Safety Injection to RCS Except Baron
- 20. M0V-1869B*
Injection Li1e NA l Reactor Coolant Letdown Line From RHR System 21 IlCV-ll425 NA Residual Heat Removal System Sample Lines
- 22. TV-SS107A* NA Residual Heat Removal System Sample Lines
/3. TV-SS107f,* NA LHS1 Pump Discharge to Reactor Coolant System I
$ 24. H0V-1890A* llot Legs cn NA LHSI Pump Discharge to Reactor Coolant System b 25. H0V-1890B*
{ llot Legs NA
.i LHSI Pump Discharge to Reactor Coolant System S_ 26. H0V-1890C*
Cold Legs 3
m LilSI Pump Discharge to Reactor Coolant System NA 1 27. MOV-1890D* Cold Legs
; ia NA FCV-ll60* Loop Fill lleader f
I 28.
Charging Line NA
! 29.' H0V-1289A* NA High Head Safety injection. Doron Injection
- 30. M0V-1867C*
a Tank NA
{ High llead Safety Injection. Baron Injection
- 31. M0V-1867D*
r Tank
2 TABLE 3.6-1 (Cont.)
o ISOLATION TIME h VALVE FUNCTION (SEC.)
3 NUMBER -
E Casing Cooling to Outside Recirculation Spray Pump flA -
> 32. M0V-RS-100A*
i Casing Cooling to Outside Recirculation Spray Pump NA
@ 33. MOV-RS-100B*
G Casing Cooling to Outside Recirculation Spray Pmp NA
- 34. MOV-RS-101A*
Casing Cooling to Outside Recirculation Spray Pump NA
- 35. MOV-RS-101B*
, e. .i n e s . .ss i1
- t. i ' ..
N
. .l...:
O .. . .- . 1 6.
~ ., .. ., ..
y , . .. . .
. .i .. .
. ......i... . .. .: , ,,,
i .
(J L
- . .a m
o , ..
a, ,o i i i .i.... . . . . . . . i,.i. .. .. g w .L N -
.. . i n . . . . . . .. . . . . i,.,. , .
f w
O @ _
0
O O Gd TABLE 3.6-1 (Coit.)
g VALVE ISOLATION TIME x
NUMBER FUNCTION (SEC.)
1; 17. TV-CV100* Containment Air Ejector Suction NA .
5 18. MOV-1869A* High Head Safety Injection to "CS Except Boron NA
' Injection Line
! 19. MOV-1836* High Head Safety Injection to RCS Except Boron NA H Injection Li' m
- 20. MOV-1869B* High llead Safe;.y Injection to RCS Except Baron tM Injection Line
- 21. HCV-ll42* Reactor Coolant Letdown Line Fr: RHR System NA
- 22. TV-SS107A* Residual Heat Removal System Sample Lines NA
- 23. TV-SS107B* Residual Heat Removal System Sample Lines NA
$ 24. MOV-1890A* LHS1 Pump Discharge to Reactor Coolant System NA Hot Legs 7
y 25. H0V-1890B* LH$1 Pump Discharge to kcactor Coolant System NA Hot Legs
- 26. MOV-1890C* LHSI Pump Discharge to Reactor Coolant System NA Cold Legs y 27 MOV-18900* LHSI Pump Discharge to Reactor Coo'. ant System NA
_ Cold Legs W 28. FCV-ll60* Loop Fill Header NA
- 29. MOV-1289A* Charging Line NA _
N 4 30. MOV-1867C* High Head Safety Injection Baron Injection NA' 4, u Tank p
- 31. MOV-1867D* High Head Safety Injection, Doron Injection NA D Tank
TABLE 3.6-1 (Cont.)
ISOLATION TIME
-, VALVE (SEC.)
FUNCTION
$ tjuMBER M
> E. REMOTE MANUAL E NA 5 -1. MOV-QSl al A
- Quench Spray Pump Discharge ,
s Quench Spray Pump Discharge NA g 2. M0"-QS101B*
Q Recirc. Spray Pump Suction NA
- 3. H0V-RS155Af
- Recirc. Spray Pump Suction NA
- 4. MOV-RS1558#
- LHS1 Pump Suction from Containment Sump NA
- 5. H0V-1860Af
- LHS1 Pump Suction from L'ntainment Sump NA w 6. M0V-1860D# *
'2: Recirculation Spray Pump Discharge NA m 7. '
MOV-RS156A
- hm Recirculation Spray Pump Discharge it
- 8. H0V-RS156B *
- 9. HOV-SW103A* Service Water to Recirculation Spray Coolers NA
- 10. MOV-SW103B*
Service Water to Recirculation Spray Coolers NA
- 11. M0V-SW103C* Service Water to accircualtion Spray Coolers NA
- 12. H0V-SWiO30* Service Water to Rec'rculation Spray Coolers NA Ln Service Water to Recirculation Spray Coolers NA G 13. MOV-SW104A*
- 14. MOV-SW1048* Service Water to Recirculation Spray Coolers NA rv
'irculation Spray Coolers j 15. MOV-Sul04C* Service Water t; NA
- 16. Mov ' :040* Service Water to Recirculation Spray Coolers HA y 0
0 8 O
O U U
' TABLE 3.6-1 (Cont.)
5 ' ' " ' - ' . I o. i t. . . ISOLATI0f1 T!!4E N VALVE (SEC.)
tW!4BER futlCTION Reactor Coolant Pump Seal Water Supply 8 ', o. , 11A f- 12. 1-Cll-314#* .
c- f(A 5 13. 1-SA-57* Service Air H i ...e .,.i...
f(A Service Air
- 14. 1-SA-58*
' ' '- fiA
- 15. 1-{A-54* b.;trument Air ,
tiA
- 16. lU.< fyel Transfer (Tube Penetration #65)-
.,. i.: , . i . a.
flA
- 17. 1-CV-4* is .
Ejector Suction R 'c tiA
- 18. 1-RC-176* Dead Weight Pressure Calibrator ' /*....
[1 t1A Cl 19. 1-RC-178* Dead Weight Pressure Calibrator Refueling Purification Inlet f(A tn 20. 1-RP-26*
f(A J 21. 1-RP-28* Refueling Purification Inlet i.. ..i,.r, Refueling Purification Inlet itA w 22. 1-RP-6* ' i i>i......pi, w flA U7 23. 1-RP-8* Refueling Purification Inlet
!1A
- 24. 1-WT-354#* Chemical Feed Lines 5 e',
tiA
- 25. 1-WT-357#* Chemical Feed Lines i flA d
- 26. 1-WT-351#* Chemical Feed Lires
- - TABLE 3.6-1 (Cont.)
0 2 VALVE ISOLATION TIME u t;U?!BER fullCTICfl (SEC.)
D. MAtJUAL E .
A 1. i-SI-58* Safety Injection Accumulator Make Up flA
- 2. 1-RH-36* Residual ileat Removal System to Psefueling Water Storage Tank flA
- 3. 1-Ril-37* Residual 11 eat Removal System to Refueling Wate.-
Storage Tank flA s
- 4. 1 -tic- 12
- Discharge from Atmosphere Clean-up System (llydrogen Recombiner) flA a
- 5. 1 -IIC-31
- Discharge From Atmosphere Clean-up System (llydrogen Recombiner) NA
- 6. 1 -if C-16
- Discharge From Atomsphere Clean-up System (flydrogen Recombiner) ilA
- 7. 1-llc-28* Discharge From Atmosphere Clean-up System (llydrogen Rcombiner) f1A
- 8. 1-63-39* Primary Vent Pot Vent t<A
- 9. 1-DA-41* Primary Vent Pot Vent f1A ul
- 10. 1 -Cll-310f
- Reactor Coolant Pump Seal Water Supply flA u,
- 11. 1 -Cil-318#
- Reactor Coolant Pump Seal Water Supply tiA r0 W p w
b m
b b
* .i.....
4 O
s
' i. .
TABLE 3.6-1 (Cont.)
ISOLATI0ti TIME VALVE ,
(SEC.)
FUNCTION , , , ,
$ NUMBER 5 C. C0tiTAltlMENT PURGE AND EXHAUST (VENTILATION DUCTS)
> h.A.
Purge Supply
- 1. H0V-IlV100A*
[
= N.A.
Purge Supply .
- 2. M0V-IIV100B*
] Alternate Supply li . A .
- 3. fl0V-IIV102*
N.A.
Purge Exhaust
- 4. H0V-IIV100C*
ti . A .
Purge Exhaust S. HOV-HV10uu*
N.A.
Bypass
- 6. H0V-ilV10l*
t tr -
CL m
W '
N n
h a
TABLE 3.6-1 (Cont.)
ISOLATI0t.: TIME M VALVE (SLC.)
4 x
NUMBER FUNCTIO!!
. .. i i , i .. . e :
- 12. TV-CC104B Reactor Coolant Pumps, Cooling Water In 60 E! , , , , ,
5 Reactor Coolant'P' umps. Cooling Water In
'60 a- -
- 13. TV-CC104C ,
- 14. TV-CC102A- ' Reactor Coolant Pumps, Bearing and Shroud, 60 Cooling Water Out
/ 4 i .. .
i
,,a i .. i. t . .1ai. .o l I
- 15. TV-CC102B ' ' Reactor ' Coolant Pumps, Bearing and Shroud, 60 Cooling Water Out ..t .
i., i.n.- f i. . .
- 16. TV-CC102C Reactor Coolant Pumps, Bearing and Shroud, 60 Cooling Water Out
. . ,, s. . .. .. . ,.s. .: s.1 lis a i 1. :6 i .I6n, .l.. .
- 17. TV-CC1020 - ' Reactor Coolant Puinps, Bearing and Shroud, 60
? Cooling Water out -
m . : i ....i c..i.. .. 1i i .. .
N
- 18. TV-CC102E Reactor Coolant Pumps Cooling Water Out 60
- 19. .TV-CC102F '-
c Reactor Coolant 'Pudps ,"Coolinh- Wat'eF Dut" ' '60
.i . ..
- 20. TV-BD100A Steam Generator Blowdown .. ,i.
60
. :. ......ii 2. i.
- 21. TV-BD1000 Steam Generator Blowdcun 60 8 '*
- 22. TV-BD100C -
Steam Generator BloWdcod ""'"" ' "' '' 60
- i. .I
- 23. TV-BD1000 60
,, Steam Generator ulowdown...
. .. .. .... ri. i. ..
g 24. TV-80100E iiSteam Generator 810wdown 60
~
u, 25. TV-80100F .
S teant Genera to r' Bl okdowri ""' ' '"'"' "' ' ' ' ' B0
..i .i...i :I p
- ,L iv .. ., . .4 i
.. , '. . ii... 6...: . t i .. .i t J is 1. . s . . y w .i......i .ii. 3 T' .
i1 , . . . . e. 4...I .il ! ....l...) ll. 6 .. i I.. . .
U U U.
TABLE 3.6-1 (Cont.)
ISCLATICri TIME 5 VALVE (SEC.)
FUNCTI0ft h hu!43ER .
B. PHASE "B" ISOLATION Component Cooling Water From RHR System and E/ cess 60 i 1. TV-CC103A Letdown Heat Exchanger g
Q 2. TV-CC103B Component Cooling tlater from RHR System and Excess 60 Letdown Heat Exchanger Reactor Coolant Pump Thermal Barrier Cooling Water 60
- 3. TV-CC101A Re turn Reactor Coolant Pump Thermal Barrier Cooling Water 60
- 4. TV-CC1018 Return Component Cooling Water From Containment Air Recir- 60 R 5. TV-CC100A
- culation Colls Component Cooling llater from Containment Air Recir- 60
- 6. TV-CC100B culation Coils Component Cooling Water from Containment Air Recir- 60
- 7. TV-CC100C tn culation Coils Component Cooling Water from Containment Air Recir- 60
- 8. TV-CC105A culation Coils N 60 w 9. TV-CC1058 Component Cooling Water from Containment Air Recir-m culation Coils 10 T.V-CC105C Component Cooling Water from Ccntainment Air Recir- 60 P culatua Coils g
- 11. TV-CC104A Reactor Coolant Pumps, Cooling Water In 60 b
'..l TABLE 3.6.-l (Cont.)
ISOLATION TIME VALVE I (iont.) (SEC.)
__ FUNCTION n g NUMBER 1,ui60 t i.o i it .i N Containment Vacuum Pump Suction i.gi
- 48. TV-CV150B i o n. i ni; 3
g .. 60' ,
Containment Vacuum Pump Suction p 49. TV-CV150C i . o.. . i. i....i.. ..i 1.. .i .i.i. ti,,n i ( ,,i i n9 : in, 60
,.n g Containment Vacuum.PurnplSuction 5 50. TV-CV1500 60 t.o
- Residual Ileat Removal Systern Sampl.eilines1 in .
- 51. TV-SS103 nn 1.. ni. i. , . .
i..oro 60 Reactor Containment Leakage Monitoring Lines TV-LM10 6 s.o
- . 2 .
' ' ' ' " ' to Reference System : l " l' il"n i t ori ou I s oc:,
- i. i i, i.l., ni. 1. p s 60 Reactor Containment Leakage Monitoring Lues i .o
- 53. TV-LM1010
' ' ' - '" to Referonce System 1 ul'.ic IL n 8 8 oi inu i ".o i ora 1.. . . . . i. p. 60 Reactor Containment Leakage Monitoring Lines i .o
- 54. TV-LM101C ,
to Reference System i .!"i" 11 o.t i ni i n ; I s oc:.
Rc.
..n .. 1. ,. i. g 60 Reactor Containment Leakage Monitoring Lines t 55 Til e., ylD to Reference System ' .i a se it. nit toring i in .,
i -
g ' .
i, o,. i.. :. i n , i. ;.
10
- 56. TV-1859 Safety Injection Test Line .,
. i. . .. ...i...p.it., nit..rIn.,iiin.
. 4 10
- 57. TV-1842 Safety Injection TestILine~
en 6 0. . .
Steam Generator. Surface.Sampleli.nii.. ring iin...
- 58. TV-SSll2A i
] i e . . c.
Steam Generator Surface Sample u.. i.,.
60
- 59. TV-SSll2B .. , i. ,
. .s.
w 60 o 60. TV-MS1091 Main Steam Drains to Condenser ,
o .. . . .. . 4 , .. .i. . n.i . i ..
60 p
- 61. TV-MS110,# Main Steam to Blowdown ,., 4
. i
. . . . i .. . . . . ,
60 p TV-SV102-2 Condenser Air Ejector Vent y
- 62. r,. <, .... ..i 60 .
- 63. FCV-AS100A#
Condenser Air Ejector steam Supply '
- 64. FCV-AS10008 Cond'ensEr A r hjec[o'r 'Sleam$p' ply 60 ' '
h
Q b 9 0
TABLE 3.6.-l_(Cont.)
ISOLATI0tl TIME b VALVE futJCTIOt1 (SEC.) _
2 fluMBER_
> 60 Reactor Containment Leakage Monitoring Lines 5
- 35. TV-LH100A to Open Pressure Taps s
60 Reactor Containment Leakage Monitoring Lines E 36. TV-LM1000 to Open Pressure Taps 60 Reactor Containment Leakage Itanitoring Lines
- 37. TV-LM100C to Open Pressure Taps 60 Reactor Containment Leakage Monitoring Lincs
- 33. TV-LM1000 to Open Pressure Taps 60 feactor Containment Leakage Monitoring Lines
- 39. TV-LM100E m
to Open Pressure Taps L 60
- Reactor Containment Leakage Monitoring Lines
- 40. TV-LM100F to Open Pressure Taps 60 Reactor Containment Leakage Monitoring Lines
- 41. TV-LM100G to Open Pressure Taps 60 Reactor Containment Leakage Monitoring Lines
- 42. TV-LM100ll to Open Fressure Taps 60 Pressurizer Vapor Space Samplc i 43. TV-SS101A 60 Pressurizer Vapor Space Sample
- 44. TV-SS1018 60 g TV-SV102-1 Condenser Air Ejector Vent e v~ 45.
O Condenser Air Ejector Vent 60 h
- 46. TV-SV103 60 Containment Vacuum Pump Suction
- 47. TV-CV150A
TABLE 3.6-l_(Cont.)
ISOLAT!0tl TIME 5 VALVE FUt1CTI0tl (SEC.)
A x
IduMDER 60
- 18. TV-RM100A Air Radiation Monitor Return
$ 60 5
E 19. TV-RM100D Air Radiation Monitor Return ,
25 Air Radiation Monitor Supply 60
- 20. TV-RM1008
] - 60 Air Radiation Monitor Supply 2i. TV-RM100C 10
- 22. TV-1519A Primary Grade Water to Pressurizer Relief Tank 60
- 23. TV-VG100A Primary Vent lleader 60 4 24. TV-VG1008 Prim ky Vent licader 60 T 2S. TV-S!101 Safety Injection Accumulators to Waste Gas Charcoal Filters
[ Safety Injection Accumulators to Waste 10
- 26. IICV-1936 Gas Charcoal filters Pressurizer Relief Tank Sample 60
- 27. TV-SS104A Pressurizer Relief Tank Sample 60
- 28. TV-SS1048 wT\ 60 Pressurizer Liquid Space Sample y, 29. TV-SS100A 60 Pressurizer Liquid Space Sample
- 30. TV-SS1000 va Primary Coolant ilot Leg Sample 60 cD 31. TV-SS1064 N 60 Primary Coolant ilot Leg Sample
- 32. TV-SS106B 60 i
- 33. TV-SS102A Primary Coolant Cold Leg Sampic d Primary Coolant Cold Leg Sampic 60
- 34. TV-SS1028}}