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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17313B0991999-10-14014 October 1999 Forwards LER 99-005-00 Reporting Findings & Corrective Actions Taken as Result of Out of Tolerance MSSV Condition in Unit 1 Which Was Discovered During pre-outage Testing ML17313B0881999-10-12012 October 1999 Forwards Response to NRC 990831 RAI Re Several Relief Requests That Accompanied Second ten-yr Interval ISI Program Submitted on 980317.Revised Relief Request 6 Is Provided in Encl 2 ML17300B3501999-09-29029 September 1999 Forwards Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7,in Response to NRC RAI Re Proposed Amend to TS 3.8.1 & 3.3.7 ML17300B3551999-09-28028 September 1999 Responds to Aministrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. Proposed Palo Verde Operator Licensing Exam Schedule & Estimated Number of Applicants Planning to Take Exams Encl ML17313B0851999-09-24024 September 1999 Requests Approval of Alternative to Repair Requirements of 10CFR50.55a,authorizing Alternative Use of Mechanical Nozzle Seal Assemblies,As Described in Encl,For RCS Hot Leg Instrumentation & Sampling Nozzles for Two Operating Cycles ML17313B0781999-09-20020 September 1999 Forwards Rev 22 to PVNGS Emergency Plan. Summary Description of Changes,Included ML17300B3331999-09-14014 September 1999 Forwards MOR for August 1999 & Revised MOR for Jul 1999 for Pvngs,Units 1,2 & 3 ML17300B3351999-09-0808 September 1999 Informs That Repairs to Plant EDG 2A Jacket Water Cooling sub-sys Were Completed & EDG Was Declared Operable on 990903 at Approx 21:45 Mst.Noed Was Not Necessary,Since 72 Hour Completion Time Was Met ML17313B0761999-09-0303 September 1999 Requests Enforcement Discretion to TS Section 3.8.1, AC Sources - Operating. Enforcement Discretion Would Allow,On One Time Basis,Extension of Completion Time in Required Action B.4 of TS 3.8.2 from 72 H to 108 H ML17313B0731999-08-31031 August 1999 Informs That RR Bean (License OP-50452-1) Has Been Permanently Reassigned to Position That Does Not Require License & Requests That Individuals License Be Expired Per 10CFR55.55 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML17313B0581999-08-0606 August 1999 Forwards Rev 1 of Changes to TS Bases Implemented Between Aug 1998 & Jul 1999.Insertion Instructions & List of Affected Pages Included ML17313B0311999-08-0303 August 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17313B0431999-07-30030 July 1999 Advises of Listed Senior Mgt Changes That Have Taken Place at Plant ML17313B0441999-07-30030 July 1999 Forwards Comments on Draft NRC Repts Evaluation of AOVs at Us Light-Water Reactors (1999) & Idaho Natl Engineering & Environ Lab Rept (INEEL)EXT-98-00383,Study of AOVs in Npps. ML17313B0151999-07-20020 July 1999 Submits Request to Obtain All Data Previously Sent by PVNGS & Currently in REIRS for OLs NPF-41,NPF-51 & NPF-74.Data Is Requested in Electronic Form (Ascii Format) as It Currently Exists in REIRS Sys ML17313B0091999-07-20020 July 1999 Forwards Requested Calculations Performed to Verify That Increase in Max Radially Averaged Enrichment for Fuel Assemblies from 4.3 Weight Percent to 4.8 Weight Percent Did Not Affect Requirements for TSs 3.7.15,3.7.17 & 4.3.1 ML17313B0171999-07-16016 July 1999 Forwards LER 99-005-00,re Automatic Rt Which Occurred on 990618,following Sensor Failure in Core Protection Calculators.Corrective Actions Described in LER Are Not Necessary to Maintain Compliance with Regulations ML17300B3111999-07-15015 July 1999 Forwards PVNGS Unit 2 ISI Rept for Eighth Refueling Outage. No Commitments Made to NRC by Ltr ML17300B3141999-07-15015 July 1999 Forwards Corrected Electronic Files for Individual Monitoring Repts for 1998.Original Electronic Files Were Found to Have Two Administrative Errors,Which Has Been Corrected.Encl Withheld,Per 10CFR2.790 ML20209G6771999-07-0808 July 1999 Forwards Supplemental Info to Confirm That Decommissioning Funding Plans of Public Service Co of Nm for Interests in PVNGS Have Been Reviewed by Nm Public Regulation Commission. Final Order & Recommended Decisions in Case 2742,also Encl ML17300B2931999-07-0202 July 1999 Submits Withdrawal of Relief 5 for Second ISI Interval for Units 1,2 & 3.Proposed Alternative Is Related to Exam Requirements for Component Supports for Second ISI Interval ML17313A9951999-06-26026 June 1999 Provides Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML17300B2831999-06-26026 June 1999 Requests NRC Approval of Proposed Alternative IAW Provisions of 10CFR50.55a(a)(3)(i) to 10CFR50.55a(g) & Requirements of ASME Boiler & Pressure Vessel Code Section XI for Repairs & Installation.Description of Proposed Alternative,Encl ML17313A9901999-06-15015 June 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. No Commitments Being Made to NRC by Ltr ML17313A9521999-05-24024 May 1999 Notifies NRC That Ja Proctor,License SOP-50314,has Been Permanently Reassigned to Position That Does Not Require License.License Should Be Expired,Per 10CFR55.55 ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML17313A9311999-05-13013 May 1999 Notifies NRC That Rev 2 to COLR for Unit 2 Remains Applicable Following Recently Completed Unit 2 Reload ML17313A9481999-05-12012 May 1999 Informs of Change Needed in Order to Update Current Mailing List.Future Mailings for J Horne Should Be Forwarded to Listed Address ML17313A9261999-05-0707 May 1999 Forwards LER 99-004-00,per 10CFR50.73.LER Repts Findings & Corrective Actions Taken as Result of Unit 2 Out of Tolerance Pressurizer Safety Valve (Psv) Condition Which Was Discovered During Outage Testing ML20206H1931999-05-0303 May 1999 Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl ML17313A9091999-04-30030 April 1999 Forwards Proprietary Proposed Test Outlines for Initial License Exams to Be Administered at PVNGS in Aug/Sept 1999. No Commitments Are Contained in Ltr.Proprietary Info Withheld ML17313A9181999-04-30030 April 1999 Forwards Electronic File of Individual Monitoring Repts for 1998.Encl Withheld Per 10CFR2.790 ML17313A9191999-04-30030 April 1999 Forwards Special Rept 2-SR-99-001 Re SG Tube Plugging in PVNGS Unit 2,per TS Reporting Requirement 5.6.8.Complete Results of SG Tube Inservice Insp Will Be Submitted by 000422 ML17300B3751999-04-23023 April 1999 Forwards LER 99-003-00,reporting Condition Prohibited by TS 3.7.17 Where Spent Fuel Assembly Was Stored in Inappropriate Region in Spent Fuel Pool ML17313A9081999-04-23023 April 1999 Documents 990421 Telcon with E Emeigh,Which Requested Extension for Submitting Next Matl Balance Rept for Pvngs,As Required by 10CFR70.53 & 74.13.Required Info Will Be Submitted by 990531 ML20205T7421999-04-21021 April 1999 Forwards Partially Withheld Insp Repts 50-528/99-05, 50-529/99-05 & 50-530/99-05 on 990322-26.Determined That Security Program Properly Implemented.Insp Repts Details Withheld (Ref 10CFR73.21) ML17313B0271999-04-21021 April 1999 Forwards Proprietary Epec Pro Forma Cashflow Statement for 1999.Proprietary Info Withheld,Per 10CFR2.790.Affidavit Encl ML17313A9031999-04-21021 April 1999 Forwards Rev to Relief Request 12 Submitted 990420 to Second 10-yr ISI Interval.Revised Relief Request Discusses in More Detail Actions APS Will Take When There Is Identified Leakage from Bolted Connection ML17313A8971999-04-20020 April 1999 Requests Use of Alternatives to 10CFR50.55a(g) Inservice Insp Requirements.Proposed Alternatives Are Related to Visual Exam of Bolted Connections 05000529/LER-1999-002, Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing1999-04-19019 April 1999 Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing ML17313A8931999-04-14014 April 1999 Forwards LER 99-003,reporting Condition Prohibited by TSs That Existed When Surveillance Requirement to Verify Essential Chilled Water Sys Valve Positions Was Not Met ML20205Q0821999-04-13013 April 1999 Forwards Second ISI Interval Relief Request 10 from ASME Section XI & Applicable Addenda Re Visual Exams Performed Subsequent to Repair or Replacement of Component or Alteration of Item ML17313A8901999-04-13013 April 1999 Forwards LER 98-003-01 Re MSSV as-found Lift Pressures out- Side of TS Limits.Ler Suppl Provides Evaluation Findings from Unit 3 out-of-tolerance MSSVs Conditions Which Were Discovered During pre-outage Testing ML17313A8831999-04-0808 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Pvngs,Units 1,2 & 3 & Rev 13 to ODCM, for Pvngs,Units 1,2 & 3 IAW TS 5.6.3 ML20205F3491999-03-30030 March 1999 Forwards Proprietary & non-proprietary Info Re Status of Decommissioning Funding for Pvngs,Units 1,2 & 3,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per Requirements of 10CFR2.790(b)(1) ML17313A8671999-03-24024 March 1999 Submits Info Re Present Levels & Sources of Property Insurance Maintained for Pvngs,Per 10CFR50.54(w)(3) ML17313A8601999-03-16016 March 1999 Forwards Revised Relief Requests PRR-05,PRR-06 & PRR-11 to Clarify That Proposed Design Flow Testing for Lpsi,Hpsi & Containment Spray Pumps Will Be Performed Using Instruments That Comply with Code Requirements,Per 990226 Telcon ML17313A8551999-03-0505 March 1999 Requests Proposed Code Alternative IAW 10CFR50.55a(e)(3),as Acceptable Alternative to Requirements of 10CFR50.55a(e)(1), for Installation of in-line safety-related Flow Measurement Instrument in ASME Class 3 Pipe 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17313B0991999-10-14014 October 1999 Forwards LER 99-005-00 Reporting Findings & Corrective Actions Taken as Result of Out of Tolerance MSSV Condition in Unit 1 Which Was Discovered During pre-outage Testing ML17313B0881999-10-12012 October 1999 Forwards Response to NRC 990831 RAI Re Several Relief Requests That Accompanied Second ten-yr Interval ISI Program Submitted on 980317.Revised Relief Request 6 Is Provided in Encl 2 ML17300B3501999-09-29029 September 1999 Forwards Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7,in Response to NRC RAI Re Proposed Amend to TS 3.8.1 & 3.3.7 ML17300B3551999-09-28028 September 1999 Responds to Aministrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. Proposed Palo Verde Operator Licensing Exam Schedule & Estimated Number of Applicants Planning to Take Exams Encl ML17313B0851999-09-24024 September 1999 Requests Approval of Alternative to Repair Requirements of 10CFR50.55a,authorizing Alternative Use of Mechanical Nozzle Seal Assemblies,As Described in Encl,For RCS Hot Leg Instrumentation & Sampling Nozzles for Two Operating Cycles ML17313B0781999-09-20020 September 1999 Forwards Rev 22 to PVNGS Emergency Plan. Summary Description of Changes,Included ML17300B3331999-09-14014 September 1999 Forwards MOR for August 1999 & Revised MOR for Jul 1999 for Pvngs,Units 1,2 & 3 ML17300B3351999-09-0808 September 1999 Informs That Repairs to Plant EDG 2A Jacket Water Cooling sub-sys Were Completed & EDG Was Declared Operable on 990903 at Approx 21:45 Mst.Noed Was Not Necessary,Since 72 Hour Completion Time Was Met ML17313B0761999-09-0303 September 1999 Requests Enforcement Discretion to TS Section 3.8.1, AC Sources - Operating. Enforcement Discretion Would Allow,On One Time Basis,Extension of Completion Time in Required Action B.4 of TS 3.8.2 from 72 H to 108 H ML17313B0731999-08-31031 August 1999 Informs That RR Bean (License OP-50452-1) Has Been Permanently Reassigned to Position That Does Not Require License & Requests That Individuals License Be Expired Per 10CFR55.55 ML17313B0581999-08-0606 August 1999 Forwards Rev 1 of Changes to TS Bases Implemented Between Aug 1998 & Jul 1999.Insertion Instructions & List of Affected Pages Included ML17313B0311999-08-0303 August 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001 ML17313B0441999-07-30030 July 1999 Forwards Comments on Draft NRC Repts Evaluation of AOVs at Us Light-Water Reactors (1999) & Idaho Natl Engineering & Environ Lab Rept (INEEL)EXT-98-00383,Study of AOVs in Npps. ML17313B0431999-07-30030 July 1999 Advises of Listed Senior Mgt Changes That Have Taken Place at Plant ML17313B0151999-07-20020 July 1999 Submits Request to Obtain All Data Previously Sent by PVNGS & Currently in REIRS for OLs NPF-41,NPF-51 & NPF-74.Data Is Requested in Electronic Form (Ascii Format) as It Currently Exists in REIRS Sys ML17313B0091999-07-20020 July 1999 Forwards Requested Calculations Performed to Verify That Increase in Max Radially Averaged Enrichment for Fuel Assemblies from 4.3 Weight Percent to 4.8 Weight Percent Did Not Affect Requirements for TSs 3.7.15,3.7.17 & 4.3.1 ML17313B0171999-07-16016 July 1999 Forwards LER 99-005-00,re Automatic Rt Which Occurred on 990618,following Sensor Failure in Core Protection Calculators.Corrective Actions Described in LER Are Not Necessary to Maintain Compliance with Regulations ML17300B3111999-07-15015 July 1999 Forwards PVNGS Unit 2 ISI Rept for Eighth Refueling Outage. No Commitments Made to NRC by Ltr ML17300B3141999-07-15015 July 1999 Forwards Corrected Electronic Files for Individual Monitoring Repts for 1998.Original Electronic Files Were Found to Have Two Administrative Errors,Which Has Been Corrected.Encl Withheld,Per 10CFR2.790 ML20209G6771999-07-0808 July 1999 Forwards Supplemental Info to Confirm That Decommissioning Funding Plans of Public Service Co of Nm for Interests in PVNGS Have Been Reviewed by Nm Public Regulation Commission. Final Order & Recommended Decisions in Case 2742,also Encl ML17300B2931999-07-0202 July 1999 Submits Withdrawal of Relief 5 for Second ISI Interval for Units 1,2 & 3.Proposed Alternative Is Related to Exam Requirements for Component Supports for Second ISI Interval ML17313A9951999-06-26026 June 1999 Provides Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML17300B2831999-06-26026 June 1999 Requests NRC Approval of Proposed Alternative IAW Provisions of 10CFR50.55a(a)(3)(i) to 10CFR50.55a(g) & Requirements of ASME Boiler & Pressure Vessel Code Section XI for Repairs & Installation.Description of Proposed Alternative,Encl ML17313A9901999-06-15015 June 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. No Commitments Being Made to NRC by Ltr ML17313A9521999-05-24024 May 1999 Notifies NRC That Ja Proctor,License SOP-50314,has Been Permanently Reassigned to Position That Does Not Require License.License Should Be Expired,Per 10CFR55.55 ML17313A9311999-05-13013 May 1999 Notifies NRC That Rev 2 to COLR for Unit 2 Remains Applicable Following Recently Completed Unit 2 Reload ML17313A9481999-05-12012 May 1999 Informs of Change Needed in Order to Update Current Mailing List.Future Mailings for J Horne Should Be Forwarded to Listed Address ML17313A9261999-05-0707 May 1999 Forwards LER 99-004-00,per 10CFR50.73.LER Repts Findings & Corrective Actions Taken as Result of Unit 2 Out of Tolerance Pressurizer Safety Valve (Psv) Condition Which Was Discovered During Outage Testing ML20206H1931999-05-0303 May 1999 Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl ML17313A9191999-04-30030 April 1999 Forwards Special Rept 2-SR-99-001 Re SG Tube Plugging in PVNGS Unit 2,per TS Reporting Requirement 5.6.8.Complete Results of SG Tube Inservice Insp Will Be Submitted by 000422 ML17313A9181999-04-30030 April 1999 Forwards Electronic File of Individual Monitoring Repts for 1998.Encl Withheld Per 10CFR2.790 ML17313A9091999-04-30030 April 1999 Forwards Proprietary Proposed Test Outlines for Initial License Exams to Be Administered at PVNGS in Aug/Sept 1999. No Commitments Are Contained in Ltr.Proprietary Info Withheld ML17313A9081999-04-23023 April 1999 Documents 990421 Telcon with E Emeigh,Which Requested Extension for Submitting Next Matl Balance Rept for Pvngs,As Required by 10CFR70.53 & 74.13.Required Info Will Be Submitted by 990531 ML17300B3751999-04-23023 April 1999 Forwards LER 99-003-00,reporting Condition Prohibited by TS 3.7.17 Where Spent Fuel Assembly Was Stored in Inappropriate Region in Spent Fuel Pool ML17313B0271999-04-21021 April 1999 Forwards Proprietary Epec Pro Forma Cashflow Statement for 1999.Proprietary Info Withheld,Per 10CFR2.790.Affidavit Encl ML17313A9031999-04-21021 April 1999 Forwards Rev to Relief Request 12 Submitted 990420 to Second 10-yr ISI Interval.Revised Relief Request Discusses in More Detail Actions APS Will Take When There Is Identified Leakage from Bolted Connection ML17313A8971999-04-20020 April 1999 Requests Use of Alternatives to 10CFR50.55a(g) Inservice Insp Requirements.Proposed Alternatives Are Related to Visual Exam of Bolted Connections 05000529/LER-1999-002, Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing1999-04-19019 April 1999 Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing ML17313A8931999-04-14014 April 1999 Forwards LER 99-003,reporting Condition Prohibited by TSs That Existed When Surveillance Requirement to Verify Essential Chilled Water Sys Valve Positions Was Not Met ML20205Q0821999-04-13013 April 1999 Forwards Second ISI Interval Relief Request 10 from ASME Section XI & Applicable Addenda Re Visual Exams Performed Subsequent to Repair or Replacement of Component or Alteration of Item ML17313A8901999-04-13013 April 1999 Forwards LER 98-003-01 Re MSSV as-found Lift Pressures out- Side of TS Limits.Ler Suppl Provides Evaluation Findings from Unit 3 out-of-tolerance MSSVs Conditions Which Were Discovered During pre-outage Testing ML17313A8831999-04-0808 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Pvngs,Units 1,2 & 3 & Rev 13 to ODCM, for Pvngs,Units 1,2 & 3 IAW TS 5.6.3 ML20205F3491999-03-30030 March 1999 Forwards Proprietary & non-proprietary Info Re Status of Decommissioning Funding for Pvngs,Units 1,2 & 3,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per Requirements of 10CFR2.790(b)(1) ML17313A8671999-03-24024 March 1999 Submits Info Re Present Levels & Sources of Property Insurance Maintained for Pvngs,Per 10CFR50.54(w)(3) ML17313A8601999-03-16016 March 1999 Forwards Revised Relief Requests PRR-05,PRR-06 & PRR-11 to Clarify That Proposed Design Flow Testing for Lpsi,Hpsi & Containment Spray Pumps Will Be Performed Using Instruments That Comply with Code Requirements,Per 990226 Telcon ML17313A8551999-03-0505 March 1999 Requests Proposed Code Alternative IAW 10CFR50.55a(e)(3),as Acceptable Alternative to Requirements of 10CFR50.55a(e)(1), for Installation of in-line safety-related Flow Measurement Instrument in ASME Class 3 Pipe ML17313A8241999-02-23023 February 1999 Advises That Kp Jarvis,License OP-50287-1,no Longer Needs to Maintain License as Permanently Assigned to Position Requiring No License ML17313A8111999-02-18018 February 1999 Forwards PVNGS Unit 3 7th Refueling Outage, Which Provides Complete Results of SG Tube Inservice Insp Performed,Per TS 5.6.8 ML17313A8721999-02-16016 February 1999 Discusses Resolution of Generic Safety Issue 171, ESF Failures from Loss-of-Offsite Power Subsequent to Loca. Util Has Low Vulnerability to Loca/Grid Collapse/Loop Scenario ML17313A7611999-01-22022 January 1999 Forwards PVNGS Unit 3 Inservice Insp Rept Seventh Refueling Outage, Per 10CFR50.55a.Ltr Contains No New Commitments 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML17305B0681990-09-17017 September 1990 Forwards Response to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. Exam Dates,Anticipated Number of Candidates & Requalification Exam Schedules for FY91-FY94 Also Encl ML17305B0491990-09-12012 September 1990 Forwards Palo Verde Nuclear Generating Station Unit 2 Steam Generator Eddy Current Exam,Second Refueling Outage Apr 1990. ML17305B0281990-08-27027 August 1990 Forwards fitness-for-duty Semiannual Performance Rept for Period of Jan-June 1990,per 10CFR26.71(d) ML17305B0111990-08-15015 August 1990 Responds to Request for Addl Info Re Emergency Lighting,Per Insp Repts 50-528/90-25,50-529/90-25 & 50-530/90-25. Availability Info Provided in Ref 2,most Appropriate Analysis of Lighting Sys Availability ML17305B0021990-08-0909 August 1990 Provides Update on Status of Record 546 post-restart Item, Per 900412 Ltr.Record Will Revise Procedures for Analyzing & Disseminating Incident Investigation,Operations & Maint Experience to Appropriate Dept ML17305A9871990-08-0303 August 1990 Forwards Rev 1 to Abb Impell Rept 01-1658-1815, Emergency Lighting Independent Review, Per Insp Repts 50-528/90-25, 50-529/90-25 & 50-530/90-25 ML17305A9791990-07-31031 July 1990 Forwards, Conceptual Design for Palo Verde Nuclear Generating Station for Diverse Auxiliary Feedwater Actuation Sys (Dafas) for Review.Schedule of Implementation as Indicated ML20056A4161990-07-31031 July 1990 Forwards Revised Security Plan Implementing Procedures.Encl Withheld (Ref 10CFR2.790) ML17305A9831990-07-27027 July 1990 Requests Temporary Waiver of Compliance from Limiting Condition for Operation 3.6.3 to Allow Corrective Maint to Be Performed on Main Feedwater Isolation Valves by Extending Allowed Outage Time to 12 H Instead of 4 H ML20055J2671990-07-25025 July 1990 Forwards Info Constituting Decommissioning Financial Assurance Certification Rept,Per 10CFR50.33(k)(2) & 50.75(b) ML17305A9771990-07-25025 July 1990 Forwards Status of Corrective Actions to Min Multiple Control Element Assembly Drop Events at Plant.Insp of Insulation Coils & Replacement of Defective Coils for Units 1 & 2 Completed ML20055J1031990-07-25025 July 1990 Forwards Certification of Decommissioning Financial Assurances ML20055J1711990-07-25025 July 1990 Forwards Certification of Decommissioning Financial Assurances for Plant,Per 10CFR50.75(b) & 50.33(k)(2) ML17305A9411990-07-20020 July 1990 Forwards Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. ML17305A9431990-07-17017 July 1990 Forwards Rev 1 to Palo Verde Nuclear Generating Station Annual Radiological Environ Operating Rept for 1987. Rev Results from Internal Review Bu Nuclear Safety Group & Audit Performed by Radiation Protection Stds ML17305A9601990-07-13013 July 1990 Forwards Preliminary Response Re Justification for Continued Operation of Fire Protection Sys Equipment,Per Insp Repts 50-528/90-25,50-529/90-25 & 50-530/90-25 ML17305A9331990-07-12012 July 1990 Discusses Util Compliance w/fitness-for-duty Program Implementation.Lab Specialists,Inc Audited & Monitored W/ Satisfactory Results.Ltr of Agreement Has Been in Place Since 900202 ML17305A9391990-07-0909 July 1990 Forwards Endorsement 44 to Maelu Policy MF-116 & Endorsement 62 to Nelia Policy NF-266 ML17305A9341990-07-0909 July 1990 Submits Results of 900514-18 NUREG-1220 Audit,Per NRC 900608 Request,Per Insp of Plant.Remaining Licensed Operators Found to Be in Conformance W/Medical Exam Requirements of 10CFR50.55 ML17305A9151990-06-29029 June 1990 Forwards Emergency Lighting Failure Data Update,Per 900621 Request ML17305A9061990-06-26026 June 1990 Suppls 891114 Response to Violations Noted in Insp Rept 50-528/89-16.Application for Amend to License NPF-41 Will Be Submitted in Oct 1990 to Permit Lower Flow Rate for RCS & Shutdown Cooling Sys ML17305A9111990-06-25025 June 1990 Responds to Generic Ltr 90-04, Status of Implementation of Generic Safety Issues. ML17305A9081990-06-25025 June 1990 Forwards Schedule Reiterating Util Plans for Implementation of USIs A-9 & A-44 & Provides Current Forecast Refuel Dates ML17305A9051990-06-25025 June 1990 Forwards Endorsement 45 to Maelu Policy MF-116 & Endorsement 63 to Nelia Policy NF-266 ML17305A9121990-06-24024 June 1990 Forwards Discharge Test Voltage Curve,Per 900623 Request for Completion of Emergency Lighting Exide Power Supply Prior to Entry Into Mode 2 ML17305A9171990-06-24024 June 1990 Confirms Compliance W/Agreed Upon Course of Action for Restart of Facility as Outlined in 891224 Ltr & Completion of Items Contained in Restart List Provided as Attachment to 900111 Ltr ML17305A8961990-06-20020 June 1990 Responds to NRC 900521 Ltr Re Violations Noted in Insp Repts 50-528/90-12,50-529/90-12 & 50-530/90-12.Corrective Action: Wiring in PPS Cabinets & Cabinet Drawers Reworked in Accordance W/Approved Work Authorization Documents IR 05000528/19900021990-06-19019 June 1990 Describes Current Status & Provides Description of Actions Taken to Ensure Continued High Reliability of Emergency Lighting Sys,Per Insp Repts 50-528/90-02,50-529/90-02 & 50-530/90-02.Emergency Lights Mfg by Emergi-Lite ML17305A9041990-06-19019 June 1990 Describes Current Status & Provides Description of Actions Taken to Ensure Continued High Reliability of Emergency Lighting Sys,Per Insp Repts 50-528/90-02,50-529/90-02 & 50-530/90-02.Emergency Lights Mfg by Emergi-Lite ML17305A8891990-06-15015 June 1990 Informs NRC That post-restart Items Due Prior to Scheduled Restart Have Been Completed on Schedule W/Listed Exceptions ML17305A8871990-06-14014 June 1990 Advises That Fuel Pool Cooling & Cleanup Procedures Being Restructured,Per Response to Violations in Insp Repts 50-528/89-36 & 50-530/89-36 ML17305A8731990-06-0808 June 1990 Responds to Bulletin 88-005 Re Product Forms Other than Fittings & Flanges for Plant.Significant Number of Lugs Delivered to Plant.Util Should Be Notified,If NRC Previous Review of Records Has Identified Other Product Forms ML17305A9421990-06-0101 June 1990 Forwards Pinnacle West Response to State of Az Corp Commission Complaint Filed W/Us Securities & Exchange Commission on 900521,to Revoke Exemption from Public Utils Holding Co Act ML17305A8391990-05-31031 May 1990 Forwards 1990 Reactor Containment Bldg Integrated Leak Rate Test,Final Rept. ML17305A8571990-05-31031 May 1990 Forwards Amended Pages of Feb,Mar & Apr 1990 Monthly Operating Repts for Palo Verde Nuclear Generating Station Unit 2 ML17305A8661990-05-31031 May 1990 Forwards Projected 1990 Cash Flow Statements ML17305A8201990-05-23023 May 1990 Provides Status of Improvements to Eliminate Possibility of Multiple Control Element Assembly Drop Events.Licensee Developed Mod to Ground Fault Detection Sys to Assure Continuous Monitoring & Annunciation of Any Future Faults ML20043B6421990-05-19019 May 1990 Forwards Amend 26 to Security Plan.Amend Withheld (Ref 10CFR2.790(d) & 10CFR73.21) ML17305A7841990-05-15015 May 1990 Forwards Special Rept 2-SR-90-002 Re Steam Generator Tube Plugging Due to Inservice Insp Activities.Twenty Tubes Plugged in Steam Generator 1 & ninety-one Tubes Plugged in Steam Generator 2 ML17305A8721990-05-14014 May 1990 Forwards Arizona Corp Commission Complaint Filed W/Us Securities & Exchange Commission Seeking Revocation or Mod of Exemption of Pinnacle West Capital Corp.Complaint Wholly W/O Merit ML17305A7621990-05-11011 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Repts 50-528/90-03,50-529/90-03 & 50-530/90-03.Corrective Actions: Night Order Written for Guidance on Use of Instrumentation W/Maint Tag Present ML17305A7921990-05-0808 May 1990 Forwards Public Version of Rev 2 to EPIP-14, Dose Assessment. W/900523 Release Memo ML20043A0511990-05-0303 May 1990 Forwards Public Version of Revised Epips,Including Procedure Change Notice 11 to Rev 12 to EPIP-04 & Procedure Change Notice 1 to Rev 6 to EPIP-15 ML17305A7421990-05-0303 May 1990 Responds to 900330 Enforcement Conference Re Violations Noted in Insp Repts 50-528/90-04,50-529/90-13 & 50-530/90-13.Corrective Action:Special Locking Mechanisms Installed on Currently Posted Radiation Area Doors & Gates ML17305A8861990-04-30030 April 1990 Forwards EPIP Update,Including Rev 7 to EPIP 02,Rev 12 to EPIP 03 & Rev 9 to EPIP 20.W/o Encl ML17305A7381990-04-30030 April 1990 Forwards Annual Environ Operating Rept for 1989 & Annual Rept for Salt Deposition Monitoring Program 1989. ML17305A7131990-04-20020 April 1990 Responds to NRC 900321 Ltr Re Violations Noted in Insp Rept 50-530/90-08.Corrective Action:Plant Guideline Providing Addl Guidance Re Prioritization of Work Promulgated ML17305A6891990-04-16016 April 1990 Forwards Rev to Cycle 3 Reload Analysis Rept,Submitted 891024.Rev Reflects Early end-of-cycle Unit Shutdown & Replacement of Eight New Fuel Assemblies ML17305A7011990-04-12012 April 1990 Forwards Rev 3 to Palo Verde Nuclear Generating Station Post-Restart Actions, Per JB Martin 891224 Ltr ML17305A7081990-04-0909 April 1990 Forwards post-exam Security Agreements for Dk Hendrick, D Ensign,M Alavi & Author.Agreement Certifies That Signatories Will Not Divulge Info Re 900320 Exams 1990-09-17
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REGULATOR NFORMATION DISTRIBUTION
'EM (RIDS)AOCESSION NBR: 820 FACIL:STN-50"528 STN-50-529 STN"50'530 AUTH+NAME VAN BRUNT,E~E~RBC IP, NAME NOVAKP'TAHE 8160092 DOC~DATE: 82/08/11 NOTARIZED:
YES Palo Verde Nuclear StationP Uni,t ii Arizona Publi Palo Verde Nuclear Stations Uni,t 2i Arizona Publi'Palo Verde Nuclear StationP Uni,t 3i Arizona Publi AUTHOR AFFILIATION Arizona Public Service Co.RECIPIENT AFFILIATION Assistant Dir actor for Licensing DOCKET 05000528 05000529 05000530
SUBJECT:
Forwards proposed.amended Section 6'.6 of FSAR responding to NRC 820510 question re local leak note testing of certain valves using water in lieu of air or niitrogen~Changes will be incorporated in future FSAR amend, OI'STRISUTION CODE: 800 IS COPIES RECEIVED:LTR I ENCL TITLE: PSAR/FSAR AMDTS and Related Correspondence NOTES:Standardized plant, Standardized Iplant, Standardized plant~S I ZE o JQ 05000528 05000529 05000530 RECIPIENT ID CODE/NAME A/D LICENSNG LIC BR 03 LA INTERNAL: ELD/HDS3 IE/DEP EPOS 35 NRR/DE/CEB NRR/DE/GB 28 NRR/DE/MEB 18 NRR/DE/QAB 21 NRR/DE/SEB 25 NRR/DHFS/LQB 32 NRR/DHFS/PTRB20 NRR/DSI/ASS 27 NRR/DSI/CSB 09 NRR/DSI/ICSB 16 NRR/DS I/RAB 2?NRR/DST/LGB 33 RGN5 EXTERNAL: ACRS 41 DMB/DSS (AMDTS)LPDR 03 NSIC 05.COPIES LTTR ENCL 1 0 0 1 0 1 1 1 1 2'2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 10 10 1 1 1 1 1 1 REC IP IENT ID CODE/NAME LIC BR 43 BC LICITRAg E~01 IE FILE IE/DEP/EPLB 36 NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DF/SAB
?0 NRR/DHFS/HFEBQO NRR/DHFS/OLB 34 NRR/DS I/AEB 26 NRR/DS I/CPB 10 NRR/DS I/ETSB 12 NRR/DSI/PSB 19 N/RSB 23 EG F IL 04 MIB BNL(AMDTS ONLY)FEMA REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1 0 1 1 1 1 3 3 3 3 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 1'1 1 1 1 1 1 (TOTAL NUMBER OF COPIES REQUIRED: L'TTR 58 ENCL 53 Ih II II IL hr'll, I 4 STA.O WlllIIII III aaalII'/IIIIIII IKIHIPIDHW P.o.BOX 21666-PHOENIX, ARIZONA 85036 August ll, 1982 ANPP-21600
-WFQ/KEJ/8208lih0092 8208i 1 PDR ADQCK 05000528 A PDR Hr.T.H.Novak Assistant Director of Licensing Division of Licensing Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2 and 3 Docket Nos.STN-50-528/529/530 File: 82-056-026 G.1.10
Reference:
(1)Letter from F.J.Niraglia, NRC, to E.E.Van Brunt, Jr., APS dated 5/10/82.(2), Letter from E.E..Van Brunt, Jr., APS, to R.L.Tedesco, NRC, dated 2/2/82.(3)Letter from E.'.Van Brunt, Jr.,'PS, to R.L.Tedesco, NRC, dated 2/26/82.(4)Letter from E.E.Van Brunt, Jr., APS, to R.L.Tedesco, NRC, dated 5/24/82.
Dear Hr.Novak:
Please find attached proposed amended section 6.2.6 of the FSAR respogding to the question in reference (1)concerning local leak rate testing of certain valves using water in lieu of air or nitrogen.The valves asso-ciated with penetrations 26, 27, 40 and 41 will be Type C tested using air.Penetrations 44, 67 and 77 will be Type C tested using water.These changes will be incorporated in a future FSAR amendment.
If you have any questions concerning these matters, please contact me.Very truly yours, C.ALII S+>~E.E.Van Brunt, Jr.APS Vice President, Nuclear Projects ANPP Project Director EEVB/KEJ/dh Attachment r C~~a Page 2.cc: A.L.P.E.J~W.G.C.Gehr Bernabei, Esp.Hourihan Licitra Huang H.Wilson Kopchinski (w(a)
?l STATE OF ARIZONA)'ss.COUNTY OF MARICOPA)I, A.Carter Rogers, represent that I am Nuclear Engineering Manager of Arizona Public Service Company, that the foregoing document has been signed by me for Edwin E.Van Brunt, Jr., Vice President Nuclear Projects, on behalf of Arizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and behalf, the statements made therein are true.A.Carter Rog Sworn to before me thin~0 dey of 1982 Notary Pu lic My Commission expires:.My Commisstan Expires May 19, 1986 f 1 v,'I y'o<5 gtniily),,c'e~-'"~A$J I~,s~l,+"IL~'.~*s 1 I NRC uestion The applicant has responded in their letters dated February 2, 1982 and February 26, 1982, to our concern identified in Section 6.2.6 of the Palo Verde SER (NUREG-0857) regarding the local leak rate test.In the submittals, the applicant continued to propose testing of certain valves using water in lieu of air or nitrogen.Although, water testing of certain valves for leakage is permissible under Appendix J requirements, the applicant is required to perform an analysis to justify that the affected valves will remain water covered following onset of the LOCA.In the applicant's analysis, the following information must be provided: 1)Source of sealing water for each of the affected valves: 2)Minimum water inventory available assuming a single active failure in the associated system;and 1 J 3)Proposed technical specification limits for the water test to ensure that the affected valves will remain water covered up to 30 days following onset of a LOCA under a pressure of 1.1 Pa.RESPONSE: The response is given in amended section 6.2.6.
~I1 Table 6.2.6-3 CONTAINMENT ISOLATION VALVE TESTING (Sheet 4 of 12),C',2g'.Kjenetration
~m~~y~~-'Number Aa'Valve Arrangement (see figure 6.2'-1)Function Vented and drained~for Type A test 16 Recirc.sump Yes 25A 33 Radiation monitor Yes 25B 33 Radiation monitor Yes Shutdown cooling No 26 10 Containment isola-tion valves tag nos.SIB-UV675 SIB-UV676 SIB-PSV140 HCB-UV044 HCA-UV045 HCB-UV047 HCA-UV046 SID-SIB-SIB-SIB-UV654 UV656 HV690 PSV189 Valve sizes 24 3/4 16 16 10 10 Valve type Location Type C tested Test pressure on CB side CB AB Yes Yes Yes No Yes Yes B'fly B'fly RF Gate CB Yes Yes Gate AB Yes Yes Gate CB Yes Yes Gate Yes Yes'ate CB (c)Yes Gate Yes')Yes (c)Yes')Y (c)No<<)Globe RV Status during-Type A test 0 0 0 0 0(0(i)C n I)
Table 6.2.6-3 CONTAINMENT ISOLATION VA'LVE TESTING (Sheet 5 of l2))Pen'etration Number , Valve Arrangement (see figure 6.2.4-1)Function Shutdown cooling 27 10 SI tank drain 2S 12 29 19 LP nitrogen 30 19 HP nitrogen 31 29 Instrument air ri If 8 J 8 Vented and drained for Type A test rf'ontainment isola-tion valve tag nos.No SIC-UV653 SIA-VV655 SIA-HV691 SIA-PSV179 No SIA-SIE-UV6S2 V463 SIE-PSV474 Yes GAE-V015 GAA-UV002 Yes Yes GAE-GAA-IAE-V011 VV001 V021 IAA-UV002 l8~hJ I I I Valv'e sizes Valve type Location Type C tested Test pressure on CB side CB AB Ye ()Ye B (c)Yes Yes Yes B (c)No'g'6 16 10 10 Gate Gate Globe RV 2 2 3/4 Globe Globe RV B 9 AB B (c)Y (c)(c)Yes Yes No CB Yes Yes Yes Yes 1 1 Check Gate 1 1 2 2 CB AB CB Yes Yes Yes Yes Yes Yes Yes Yes Check Gate Check Gate h Is Status during Type A test NA C NA C C C)s:~H a 3co
Table 6.2.6-3 r"-4 CONTAINMENT ISOLATION VALVE TESTING (Sheet 8 of 12)Penetration Number Valve Arrangement (see figure 6.2.4-1)Function Vented and drained for Type A test 40'17 Letdown line (b)Charging line Yes'b'1 21 Pressurizer sample Yes'"'2B 21 Pressurizer sample (b)Containment isola-tion valve tag nos.Valve sizes Valve type Location Type C tested Test pressure on CB side CHA-CHB-UV516 UV523 2 2 Globe Globe CB AE Ye ()Ye (c)Yes Yes CHE-CHE-V431 vnvo 3 2 CHE-V043 CHE-V393 3/4 CHE-HV524 CHE-V854 Check Yes CB (c)Yes CB Yes(')Yes CB Yes No(h)Yes Yes AB Yes Yes heck Globe Globe Globe Globe SSA-UV204 SSB-UV201 SSA-UV205 SSB-UV202 3/8 3/8 3/8 3/8 CB Yes Yes Yes Yes CB Yes Yes Yes Yes Globe Globe Globe Globe , Status during Type A test C NA NA M co hJ
<'~'~n-,'".~'" Table 6.2.6-3 CONTAINMENT ISOLATION VALVE TESTING (Sheet 9 of 12)Penetration Number'Valve Arrangement (see figure 6.2.4-1)42C 21 43 21 44 45-g 13 46,47,48,49 39 50)6~~Ch D;p~(:,'Q Ql D Q C'V Function Vented and drained for Type A test Containment isola-tion valve tag nos.Valve sizes Valve type Location Type C tested Test pressure.on CB side Hot leg sample Y (b)SSA-UV203 SSB-UV200 3/8 3/8 CB AB Yes Yes Yes Yes Globe Globe RCP bleedoff Y (b)Y (b)CHA-UV506 CHB-UV505 CHA-CHB-UV560 UV561 CHE-V494 CHA-UV580 3~3 1-1/2 1-1/2 Globe Globe Gate.Gate Check Gate CB Yes Yes AB Yes Yes CB AB Yes<<)Yes<<)Yes Yes CB Yes Yes AB Yes Yes Reactor dqain Reactor drain tank tank cl~)n.~Yes (b)No"'one (a)Yes PCE-PCE-V071 V070 4 4 Gate Gate I 8 CB AB Yes Yes Yes Yes SG blowdown Pool cooling D Status during Type A test NA C C C
$5 sh i'I t o 0 I co Penetration Number 58 Table 6.2.6-3 CONTAINMENT ISOLATION VALVE TESTING (Sheet ll of 12)59 60 61 62A 63A,63B 67 62B,62C Valve Arrangement;(see f igure 6.2.4-1)Function Vented and drained for Type A test 27 CB ILRT NA 28 Service air Yes Chilled water No 25 Chilled water 37 CB pressure monitor Yes 39 SGBD sample No<'>36 Long Term recirc YesCB ILRT NA Containment isola-tion valve tag nos.Valve sizes Flange IAE-V073 IAE-V072 WCE-V039 10 WCB-UV063 10 WCB-UV061 10 NCA-UV062 10 HCD-HV077 3/4 None<>SIB-SID-V533 HV331 3 3 Flanges 3/4 0 I Valve type Location Type C tested Test pressure on CB side Stitus during Type A test Flanges CB AB Type B NA NA Yes Yes Yes Yes NA C Check Globe CB AB CB AB Yes Yes Yes Yes NA C Check Gate Yes Yes Yes Yes C C Gate Gate CB , Globe AB No<" NA 0 NA 4i CB AB Type B NA C NA Check Globe Flanges 0~)1 1'(
4~4t>>a+,->>.~+4.Table 6.2.6-3 CONTAINMENT ISOLATION VALVE TESTING (Sheet 12 of 12)-v Penetration Number'72 75,76 77 78 79 Ll;L3 L2 Valve Ariangement (see figure 6.2.4-1)Function Vented and drained for Type A test Containment isola-tion valve tag nos.38 CHE-V835 CHE-HV255 RCP seal injection Y ()15 Aux FW No'None (a)~36 Long term recxrcy (c)(b)SIA-SIC-V523 HV321 22 CB purge Yes CPB-UV005A CPA-UV004A 30 CB purge Yes CPA-UV004B CPB-UV005B 26 Air Locks NA NA 20 Eqpt Hatch NA NA Ch tV I co Valve sxzes Valve type Location Type C tested Test pressure on CB side Status during Type A.test 1-1/2 Check CB Yes I Yes NA 1-1/2 Globe AB Yes No 3 3 Check Globe CB (AB yp<>>>NA'Ye5 NA C B'fly CB Yes No(')C B'fly AB Yes Yes NA NA NA CB.AB NA NA Yes No")Yes Yes Type B Type B NA NA B'fly B'fly NA R Ql 0 H R z R%)op
~~l, PVNGS FSAR CONTAINMENT SYSTEMS purpose of performing Type C tests would impair the operability of these engineered safety features.Inservice testing and inspection of these isolation valves, and also the associated piping system outside the containment, will be performed periodically under the ISI requirements of ASME XI.During normal operation, the systems are water filled and degradation of valves or piping would be readily detected.4 In the,CVCS system, the isolation valves in the reactor drain+fly(gk 4N)tank+line will be Type C tempted using water.This is justified on the basis that<'ki5 Mesc linep would be filled wj.th water in the event of a~IP&l~5 l<W LOCA, the reactor dragon tank being below the post-LOCA water level,/s gHt24 Valves which are Type'tested are tested with the applied test pressure in the same direction as the pressure existing folio ing an accident, except the butterfly and relief valves listed in table 6.2.6-3.Due to the design of these valves, the test leakage will inherently be equal to or greater than the leakage~following an accident.6 Isolation valves connected to the secondary side of the steam 4 generator, such as main steam isolation valves, main steam g 6~>MAL.Yc~relief valves, feed water valves~blowdown lines, and blowdown sample lines are not considered containment isolation valves and are not subjected to Type C tests.If there is leakage from primary to secondary side, the steam generator may be flooded in the event of a LOCA to effectively seal any tube leaks.If required, the filling of the steam generators will be performed by the auxiliary feedwater system, which meets the single failure criteria.March 1982 6.2.6-23 Amendment 8
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