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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML20216E6661999-09-10010 September 1999 Forwards Analysis of Capsule W Virginia Power North Anna Unit 1 Nuclear Power Plant Reactor Vessel Matl Surveillance Program, for Capsule Withdrawn on 980922 ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl 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 ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18151A6301999-09-0101 September 1999 Submits Summary of 990812-13 Training Managers Conference on Recent Changes to Operator Licensing Program.Meeting Covered Changes to Regulations,Examination Stds,New Insp Programs & Other Training Issues.List of Attendees Encl 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 ML18152B3701999-08-30030 August 1999 Informs That Virginia Electric & Power Co Hereby Granted Approval to Submit Original & One Paper Copy & 6 CD-ROM Copies of Updates to FSAR as Listed,In Response to ,Requesting Exception to 10CFR50.4(b)(6) 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 ML18152B3811999-08-23023 August 1999 Forwards Safety Evaluation,Granting Relief Request IWL-3 Re ISI Programs,Per Util 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 ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B3731999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006 at North Anna & Surry. Requests Info Re Individuals Taking Exam,Personnel Who Will Have Access to Exam.Sample Registration Ltr Encl ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines ML20209E3711999-07-0202 July 1999 Forwards Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.Violations Being Treated as Noncited Violations ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B3951999-06-30030 June 1999 Informs That Effective 990706,GE Edison Has Been Assigned as Project Manager,Project Directorate II-1,for North Anna Power Station.Edison Will Continue in Assignment as Project Manager for Surry Power Station 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 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 ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196G2211999-06-21021 June 1999 Forwards Licensee Sampling & Testing Obligations Re Vpdes Permit VA0052451 Reissuance Application.Details of Requests for Sampling & Testing Waivers,Included ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML20195J1391999-06-11011 June 1999 Submits Addl Info as Addendum to Original Application Which Proposed Use of Three Chemicals in Bearing Cooling Tower at North Anna Power Station,Per Reissuance of Vpdes Permit ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML20207C9851999-05-28028 May 1999 Requests Regrading of RT Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable 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 ML20216E6661999-09-10010 September 1999 Forwards Analysis of Capsule W Virginia Power North Anna Unit 1 Nuclear Power Plant Reactor Vessel Matl Surveillance Program, for Capsule Withdrawn on 980922 ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 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 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 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 ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 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 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 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
MONTHYEARML18153C3661990-09-20020 September 1990 Forwards Topical Rept VEP-NE-3-A, Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code ML20065D5671990-09-20020 September 1990 Forwards Rev 15 to Security Personnel Training & Qualification Plan.Rev Withheld ML20059H7391990-09-10010 September 1990 Forwards Rev 15 to ISFSI Nuclear Security Personnel Training & Qualification Plan.Rev Withheld ML20059H2931990-09-0707 September 1990 Advises of Review & Approval of ASME Section XI Inservice Insp Program Interval 1 Repair & Replacement Program Change to Applicable Code Edition & Addenda ML20064A5201990-09-0707 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-338/90-15 & 50-339/90-15.Corrective Actions:Procedures Revised to Include Tolerance Bands for Temp Control Switch Setpoints & Involved Personnel Counseled ML20059E5481990-08-31031 August 1990 Forwards Supplemental Info Re Deletion of Pressurizer Safety Valve Requirement During Mode 5.Current Tech Spec Requiring One Operable Safety Valve in Mode 5 Unnecessary & May Be Deleted ML18153C3451990-08-29029 August 1990 Forwards Proprietary Semiannual Fitness for Duty Program Performance Data Rept for 900103-0630.Rept Includes Summaries of Mgt Sanctions Imposed,Actions Taken to Correct Program Weaknesses & Events Reported to Nrc.Encl Withheld ML18153C3391990-08-22022 August 1990 Requests Approval for Use of Plugs Fabricated of nickel- chromium-iron Uns N-06690 Matl (Alloy 690) to Plug Tubes in Steam Generators for Mechanical & Welded Applications ML20063Q1241990-08-15015 August 1990 Provides Supplemental Info for 900115 Tech Spec Change Request Re Max Allowable Control Rod Drop Time.Retained DNBR Margin Tracked & Documented by Calculational Note ML20058N5941990-08-0808 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-338/90-11 & 50-339/90-11.Corrective Actions:Procedure Revised to Limit Applicablity to Small Refueling Cavity Leaks & Listed Evaluations & Revs Will Be Made to EOP ML18153C3171990-08-0101 August 1990 Resubmits Synopsis of Changes to Updated Operational QA Program Topical Rept Vep 1-5A ML18153C3101990-07-26026 July 1990 Forwards Decommissioning Financial Assurance Certification Rept..., Nuclear Decommissioning Trust Agreement & Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement, Per 10CFR50.75 ML20055H5651990-07-20020 July 1990 Requests for Temporary Waiver of Compliance from Requirement of Tech Spec 3.3.1.1,Table 2.3-2 Re Response Time Testing. Request Does Not Pose Significant Hazards Consideration ML18153C2901990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Listed Transmitters Compiled.Transmitters Found Installed within Reactor Protection or ESFAS Have Been Replaced ML20055F9361990-07-16016 July 1990 Advises That No 30-day Rept Will Be Made Re Degradation of Seismic Support Bolts of post-accident Hydrogen Recombiners 1-HC-HC-1 & 2-HC-HC-1 ML20044B3501990-07-13013 July 1990 Forwards Monthly Operating Repts for June 1990 & Corrected May 1990 Rept Pages for North Anna Power Station ML20055E8121990-07-0909 July 1990 Requests Cancellation of Licenses Listed ML18153C2851990-07-0606 July 1990 Forwards Response to Generic Ltr 90-04 Re Status of Generic Safety Issues ML20055D4831990-07-0303 July 1990 Requests That Operator License for Bl Shriver Be Cancelled. License No Longer Required ML20055D4841990-07-0303 July 1990 Requests That Operator Licenses for Listed Individuals Be Cancelled.Licenses No Longer Required ML20055D7701990-06-29029 June 1990 Submits Supplemental Response to Violations Noted in Insp Repts 50-338/90-04 & 50-339/90-04 Re Failure to Take Timely Corrective Action for Repair of B Low Head Safety Injection Pump (1-SI-P-1B).No Addl Purchasing Procedure Required ML20043H9421990-06-21021 June 1990 Forwards Proprietary WCAP-12351, North Anna Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Rept Withheld (Ref 10CFR2.790) 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) ML20043H1131990-06-15015 June 1990 Concludes That Removal of Temporary Loose Parts Monitoring Sys Does Not Increase Probability of Acccident,Create Possibility of New Kind of Accident & Does Not Reduce Margin of Safety ML20055C8661990-06-15015 June 1990 Forwards Application for Reissuance of NPDES Permit ML20043G8731990-06-14014 June 1990 Discusses Evaluation of ASME Section XI Testing for Outside Recirculation Spray Pumps ML20043H2091990-06-13013 June 1990 Forwards List of Corrective Actions & Current Status in Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss ML18153C2501990-06-0808 June 1990 Confirms That Primary Policy Re Onsite Property Damage Insurance,Provided by Nuclear Mutual Limited ML20043F4531990-06-0808 June 1990 Forwards, Core Surveillance Rept for North Anna 2,Cycle 7 W/Extended License Burnup Limit. Rept Contains Specific Power Distribution Limits Applicable for Cycle 7 Operation W/Burnup Limit Extension ML20043D1661990-05-30030 May 1990 Requests Withdrawal of 860321 Request for NRC Review & Approval of Engineering Evaluations 7 & 8 Re App R Fire Protection Features at Plant,Based on Establishing 60-minute Interval Prior to Requiring Reentry Into Fire Area ML20042H0571990-05-11011 May 1990 Responds to NRC 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 ML20034B9431990-04-24024 April 1990 Responds to NRC Re Violations Noted in Insp Repts 50-338/89-35 & 50-339/89-35.Corrective Action:Escape Hatch Inner Door Operator Closed to Ensure Containment Integrity & Outer Door Opened,Inspected & Sealing Surface Cleaned ML20034B9461990-04-24024 April 1990 Forwards Results of H-3 Spiked Sample Analysis Completed on 900321.Analysis Performed W/Liquid Scintillation Counter ML20033G7391990-04-0202 April 1990 Responds to NRC Re Violations Noted in Insp Repts 50-338/90-02 & 50-339/90-02.Corrective Actions:Test Procedures Developed to Include Testing of Svc Water Supply Check Valves to Charging Pump Lube Oil Coolers ML18151A2551990-03-30030 March 1990 Forwards Rev to, Corporate Emergency Response Plan & Rev to, Corporate Plan Implementing Procedures 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 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 ML20033E4181990-03-0101 March 1990 Advises of Proposed Change in Steam Generator Tube Rupture (SGTR) Operator Training Commitment,As Result of Unit 1 870715 Sgtr.Revised Commitment Will Increase SGTR Training Per 10CFR50.55.59(c) 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 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 ML20006E5971990-02-19019 February 1990 Forwards Rev 24 to Physical Security Program.Rev Withheld (Ref 10CFR73.21) 1990-09-07
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V1HOINIA E1.ECTHIC AND POWER COMi%NY Ricnxoxu,Vinoisir 20201
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March 20, 1990 l
' U.S. Nucleu Regulatory Commission Serial No.:
90-104 j
Attention: Document Control Desk NL&P/JYR:jbl R3 Washington, D.C. 20555 Docket No.: 50-339 License No.: NPF-7 1
Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 STEAM GENERATOR TUBE PLUG REPAIR Currently, Virginia Electric and Power Company plans to take appropriate action to remove the plugs affected by NRC Bulletin 89-01, dated May 15, 1989, entitled "Fallure of Westinghouse Steam Generator Tube Mechanical Plugs." However, as -
stated in Attachment 1 it may be necessary to approach the NRC and request approval for one fuel cycle relief to defer the plug removal workscope to the next refueling of North Anna Unit 2 so that other steam generator remedial activities may be performed during the 199.0 refueling outage. Deletion of the sentinel plug workscope from the l
1990 refueling outage schedule will enable us to focus resources on the remedial l
measuras almed at addressing steam generator tube integrity considerations and to l
minimize radiation exposure during the outage while still preserving the option to E
recover (return-to-service) most of these sentinelly plugged tubes. A technical basis, L
as well as a basis for considering plug removal deferment is provided in Attachment 1.
L We intend this letter to provide notice of the technical basis for a potential sentinel plug 1
removal deferral request.
' of this letter contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the
' considerations listed in paragraph (b) (4) of 10 CFR Section 2.790 of the Commission's regulations.
@A Acccrdingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section l
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2.790 of the Commission's regulations.
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$8' Correspondence with respect to the proprietary aspects of the Application for 88 Withholding or the supporting Westinghouse Affidavit should reference CAW-89-067
'* O and should be addressed to R. A. Wiesemann, Manager of Regulatory & Legislative Q-Affairs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania gg
-15230-0355.
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q Should you have any other questions or desire to arrange a meeting to discuss this r
L topic, please do not hesitate to contact us.-
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. Very truly yours,.
. W. L. Stewart
- Senior Vice President - Nuclear 4
Enclosures 1.
- Attachment I, Basis for Deferring Plug remo' val 2.
10 copies of WCAP-12265 entitled " North Anna Unit 2 Evaluation For Tube l
Vibration Induced Fatigue" (Proprietary).
. 3.
10 copies of WCAP-12266 entitled " North Anna Unit 2 Evaluation For Tube Vibration Induced Fatigue" (Non-Proprietary).
4.
. Westinghouse authorization letter, CAW-89 067, Proprietary Information Notice,
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and accompanying Affidavit.
cc:
U.S. Nuclear Regulatory Commission Region II-101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 1
Mr. J. L. Caldwell i
NRC Senior Resident Inspector North Anna Power Station t
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ATTACHMENT l BASIS FOR DEFERRING PLUG REMOVAL I
i' NORTH ANNA POWER STATION UNIT 2 I
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INTRODUCTION NRC Bulletin 89 01, dated May 15,1989, entitled " Failure of Westinghouse Steam Generator Tube Mechanical Plugs," required licensees to determine whether certain mechanical plugs supplied by Westinghouse were installed in steam generators and, if so, implement an action plan to ensure that these plugs would continue to provide adequate assurance of reactor coolant system (RCS) pressure boundary integrity under normal operating, transient, and postulated accident conditions. NRC Bulletin 89-01 identified the plug failure susceptibility as a result of the investigation into the North Anna Unit 11989 tube leak event. During the North Anna Unit 21989 refueling outage, extensive maintenance activities were completed to resolve the plug degradation issues raised as a result of both the North Anna Unit 1 1989 tube leak event and NRC Bulletin 89-01. Activities performed at North Anna in response to Bulletin 89-01 were completed consistent with the North Anna Plug Top Release Event Report submitted to the NRC on May 26,1989.
Reauested Consideration During the North Anna Unit 21987 refueling outage, a total of 118 tubes across the three steam generato7s were sentinelly plugged as a preventive measure which would provide early warning of a fatigue failure similar to the Unit 1 1987 tube rupture event.
Each of these tubes was removed from service with mechanical plugs later determined to be susceptible to the degradation described in NRC Bulletin 89 01.
During the North Anna Unit 21989 refueling outage, hot leg plugs with the suspect heat numbers (identified in NRC Bulletin 89 01) were removed and replaced as part of the corrective actions performed following the North Anna Unit 1 1989 tube leak event.
Each of the hot leg plugs with suspect heat numbers installed in conventionally plugged tubes were removed and replaced, in addition, five (5) of the 118 hot leg plugs in sentinelly plugged tubes were removed and replaced because evaluations determined these tubes to be potentially susceptible to U bend fatigue. The remaining 113 susceptible hot leg plugs in sentinelly plugged tubes were evaluated and l
determined acceptable for continued operation. Our technical justification for leaving l
these plugs installed and our action plan for final removal of the plugs were provided j
in the North Anna Plug Top Release Event Report submitted May 26,1989.
Consistent with our action plan, we intend to address the remaining 113 sentinelly L
plugged tubes in the upcoming 1990 refueling outage. However, it is now our intent to 1
- remove the susceptible hot leg plugs and their companion cold leg plugs, then return i
these tubes to service after performance of appropriate eddy current testing.
L Additionally, we Intend to remove the plugs from three (3) of the five (5) sentinelly plugged tubes previously determined to be potentially susceptible to U bend fatigue.
1 Further analysis performed has reduced the number of tubes with fatigue concerns to two (2), thereby, permitting recovery of the remaining three (3) tubes. Each of these tubes will also be returned to service following performance of appropriate eddy current testing.
The total number of tubes being considered for return to service per steam generator is i-l listed below:
I 1
L 1
i
- t Steam Generator Number of Tubes A
44 B
28 C
44 Table I contains a Row, Column listing of the tubes sentinelly plugged in 1987. We intend to return each of these tubes to service with the exception of the two tubes designated. The technical basis for returning these tubes to service is contained in Westinghouse WCAP 12265, entitled " North Anna Unit 2 Evaluation for Tube Vibration Induced Fatigue," enclosed.
An additional activity under evaluation for the North Anna Unit 21990 refueling outage is steam generator tube support plate stress relief. We have performed extensive qualification efforts on this endeavor and have concluded that the process may ameliorate the condition that exists at dented tube support plate locations. These conditions have eventually led to degradation and tube plugging on our North Anna Unit 1 steam generators. We believe that through the performance of the tube support plate stress relief effort, future tube plugging rates due to primary side stress corrosion induced by denting at the tube support plates can be reduced. This is supported by extensive laboratory testing comparing the corrosion performance of stress relieved and nonstress relieved intersections.
In the event that either significant technical problems or mechanical plug removal problems occur during the outage, we may approach the NRC requesting a deferral of the remaining plug removal efforts in favor of performing the stress relief program.
This will enable us to more effectively manage radiation exposure during the outage and at the same time maximize the long term benefit to the steam generators. The technical basis for deferring the sentinel plug removalis provided below.
Technical Basis for Deferrina Plua Removal In order for a plug top release event to occur, sufficient potential energy (in the form of a pressure differential) must exist to propel a degraded tube plug with sufficient velocity to perforate a tube in the U-bend region. For tubes with sentinel plugs, this pressure differential is equal to the small difference between the hot and cold legs of the steam generator (approximately 35 psi). Additionally, the fluid above the plug must be air to permit the plug top to obtain tne required velocity for tube perforation. As noted above, use of a sentinel plug assures the presence of water behind the plug l
which resists movement of the plug top through the tube precluding perforation of the I
inactive tube.
Reanalysis of these plug locations shows that the tubes are not susceptible to fatigue identified in NRC Bulletin 88 02 entitled " Rapidly Propagating Fatigue Cracks in L
Steam Generator Tubes." The potential for primary-to-secondary leakage due to plug degradation was also reviewed. The sentinelly plugged tubes were plugged as a i
L preventive' measure during the 1987 refueling outage. No pluggable eddy current indications were identified in any of these tubes prior to plugging. As these tubes are not operating under heat transfer conditions and are not believed to be susceptible to l
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fatigue, no active tube degradation phenomenon is expected.
Furthermore, any leakage through a potentially. degraded hot leg plug would be bounded by the leakrate through the existing cold leg sentinel plug.
. Finally, the potential for plug degradation to generate a primary system loose object was assessed. A total of 65 plugs have been removed and metallographically examined from 16 operating units. Of the total number of plugs removed,19 exhibited some form of degradation.
Circumferential degradation was noted below the
. expander in 7 of the 19 plugs. No plugs exibited 2SO degree circumferential degradation below the expander.
Two plugs exhibited semi-continous cracking extending approximately 150 to 180 degrees, while the remaining five showed short, intermittent degradation below the expander. One of the two plugs exhibiting the large extent of circumferentialindications below the expander has been discounted as an anomaly in the plug evaluation effort. This plug is from a heat generally regarded in France and the U.S. as being highly resistant to PWSCC based on its microstructure and otherwise consistent field performance.
No primary side loose parts have been seen to date due to mechanical plug degradation. This includes over 1200 domestic plugs which have operated beyond their lifetime, which is measured in effective full power days (EFPD), without generating a loose part in the primary system. Loose parts generation during the additional cycle of operation is considered unlikely.
If it is necessary to implement corrective actior.s at North Anna Unit 2 during the projected 1992 refueling outage, it is estimated that these plugs will go from a -650 EFPD (negative sign indicates these plugs are beyond their lifetime) to minimum ligament (estimated at the end of Cycle 7 operation) to approximately -1055 EFPD to minimum ligament remaining (estimated at the end of Cycle 8 operation). These calculations reflect a T-hot reduction of approxmiamtely six degrees implemented at the end of October 1989.
Summarv Currently, Virginia Electric and Power Company plans to take appropriate action to remove the plugs affected by NRC Bulletin 89 01. However, as stated above, we may approach the NRC and request approval for one fuel cycle relief to defer the plug removal workscope to the next refueling of North Anna Unit 2 so that other steam l
generator remedial activities may be performed during the 1990 refueling outage.
1 Deletion of the sentinel plug workscope from the 1990 refueling outage schedule will enable us to focus resources on the remedial measures aimed at addressing steam generator tube integrity considerations and to minimize radiation exposure during the L
outage while still preserving the option to recover (return-to service) most of these l
sentinelly plugged tubes at a later refueling outage.
I
TABLEl-NORTH ANNA UNIT 2 STEAM GENERATOR TUBES WITH SENTINEL PLUGS Steam Generator A
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Row Column Row Column Row Column 8
3 9
43 9
62 8
4 9
44 9
63 8
91 9
45 9-66 8
92 9
46 9
70 9
10 9
47 9
71 9
11 9
48 9
77 9-12 9
49 9
78 9
-13 9
50 9
79 9
14 9
51 9
80 9
-15 9
52 9
81 9
16-9 53 9
82 9
35 9
54 9
83 9
40 9
55 9
84 9
41 9
60
42 9
61 10 60 Steam Generator B Row Column-Row Column Row Column 8
3 9
35
4' 9
40 9
50 8
91 9
41 9
51 8-92 9
42 9
52 9
14 9
43 9
53 9
15 9
44 9
54 9
19 9
45 9
60 9
31 9
46 9
92 9-33 9
47 9
93 9
34 9
48 Denotes tubes that will remain sentinelly plugged due to potential susceptibility to fatigue.
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. TABLE I (Continued)
NORTH ANNA UNIT 2 STEAM GENERATOR TUBES WITH SENTINEL PLUGS E
i Steam Generator C Row.
Column Row Column Row Column 8
91 9
51 9
84
-8 92 9
52 9
85 9
35 9
53 10 35 9
39 9
54 10 42 9
40 9
55 10 43 9
41 9
56' 10 44.
9 42 9
57 10 45 9
43 9
60-10
-46 9
-44 9
61 10 47 9
45 9.
62 10 49 9
46 9
79 10 50 9
47 9
80 10 53 9
48 9
81 10 56 1
9 49 9
82 10 60 9
50 9
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@seeme cenan p" 'if Box 355 g
3 Pmstup Pomsykenia 15230 0355 YRA-89 557
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May 3, 1989 NS-0PLS-OPL-11-89-282 Mr. W. R. Cartwright, Vice President i
Nuclear Operations-Virginia Power.
Innsbrook Technical Center a
5000: Dominion Boulevard Glen Allen, Virginia 23060 a
VIRGINIA POWER NORTH ANNA POWER STATION - UNIT 2 CONTRACT RELEASE NO. PM-CL6001-012 STEAM GENERATOR._T.UBE FATIGUE ANALYSIS
Dear Mr. Cartwright,
- This letter transmits (10) copies each of proprietary'(WCAP-12265) and l
non-proprietary (WCAP<12266) versions of the " North Anna Unit 2 Evaluation For Tube Vibration Induced Fatigue", dated May,1989 for your submittal to the NRC for review an.1 approval.
l In addition-to.the' proprietary and non-proprietary WCAPs, there are two other enclosures for. your use:
- 1. - Information which should be included in your NRC transmittal letter.
'2.
Westinghouse letter " Application _ for Withholding Proprietary Information from-Public Disclosure" (CAW-88-067)~ with Affidavit CAW-88-124.
Please transmit the original of item (2) to the NRC in your transmittal.
If you have any questions, please do not hesitate to contact us.
Very truly yours, 1.
WESTINGHOUSE ELECTRIC CORPORATION 4 txtelR h M
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R. N. Easterling, Manager Steam Generator Maintenance Agreement RH0/mlt 0157M:RHD:050389 t--
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W. R. Runner, Jr.
- t R. F. Saunders/9 copies W' A.:Thornton
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J. L. Wilson W..M. Adams-M. L. Bowling /l copy i
R. O. Enfinger D. A.,Heacock-G. E. Kane
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a ATTACMENT TO VRA-89 557 s
VIRGINIA POWER Letter for Transmittal to the NRC g
Enclosed are:
-1.
10 copies of WCAP-12265 entitled ' North Anna Unit 2 Evaluation For Tube Vibration 's. iced Fatigue" (Proprietary).
2.
10 copies of WCAP-12266 entitled " North Anna Unit 2 Evaluation For Tube Vibration Induced Fatigue" (Non-Proprietary).
Also enclosed is a Westinghouse authorization letter, CAW-89-067, Proprietary Information Notice, and accompanying Affidavit.
THE FOLLOWING PARAGRAPHS SHOULD BE INCLUDED IN YOUR LETTER TO THE NRC:
As item 1 contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information, f
The affidavit sets forth the basis on which the information may be withheld from l
public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b) (4) of Section 2.790 of the Commission's regulations.
'Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Connission's regulations.
Correspondence with respect to the proprietary aspects of the Application for l
Withholding or the supporting Westinghouse Affidavit should reference CAW-89-067 and should be addressed to R. A. Wiesemann, Manager of Regulatory & Legislative Affairs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania (4
15230-0355.
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