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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) 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 ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 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 ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210H6381999-07-30030 July 1999 Forwards SE Accepting Relief Request for Approval for Use of Alternate Exam Requirement for Plant Inservice Insp Program A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 ML20210B4021999-07-19019 July 1999 Ack Receipt of Facility Emergency Plan Implementing Procedure EIP-ZZ-00101, Classification of Emergencies, Rev 23,issued on 990513,under Provisions of 10CFR50,App E, Section V ML20210B4401999-07-19019 July 1999 Ack Receipt of Revs to Facility Radiological Emergency Response Plan,Chapters 8.0 & 4.0,issued Respectively on 990512-14,under Provisions of 10CFR50,App E,Section V ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209E5591999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.TAC MA0531 Closed ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20196J9501999-07-0202 July 1999 Ack Receipt of Plant Ep,Rev 22,received on 981207 & Submitted Under Provision of 10CFR50,App E,Section V.Changes Does Not Decrease Effectiveness of EP & Continues to Meet Stds of 10CFR50.47(b).NRC Approval Not Required ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 ML20196H2521999-06-25025 June 1999 Forwards Insp Rept 50-483/99-05 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20196F8181999-06-24024 June 1999 Forwards RAI Re 990111 Request for Relief from Certain ASME Code ISI Requirements for Containment Liners.Response Requested within 30 Days from Date of Agreement ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve IR 05000483/19990041999-06-18018 June 1999 Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1 ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H0971999-06-14014 June 1999 Discusses Une 990407 Request That Proprietary Document Entitled, Thermal Stability Assessment - Electrosleeved Tubes, Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20207H3751999-06-14014 June 1999 Discusses 990407 Une Request That Proprietary Version of Document Entitled, Evaluation of Severe Accident Simulation, Dtd April 1999,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20207G3201999-06-0707 June 1999 Ack Receipt of Change Notice 98-008 Dtd 980918,which Transmitted Changes to Callaway Plant Ep,Rev 21,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required.No Violations Identified ML20207G3151999-06-0707 June 1999 Ack Receipt of Callaway Plant EP Implementing Procedure EIP-ZZ-001001M,Classification of Emergencies,Rev 22,issued on 981222 Under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS 1999-09-22
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS ML20196L2911999-05-19019 May 1999 Forwards Responses to NRC 990315 RAI Concerning GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves A36791, Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl1999-05-17017 May 1999 Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl ULNRC-04034, Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions1999-05-17017 May 1999 Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions 05000483/LER-1998-003, Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept1999-05-12012 May 1999 Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept ML20206Q9551999-05-12012 May 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-04.Corrective Actions:Une Commits to Make Available for NRC Review,Action Plan Outlining Scope & Completion Dates of Project ULNRC-04027, Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 9905281999-05-0404 May 1999 Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 990528 ML20206E3211999-04-28028 April 1999 Forwards Special Rept 98-03 Re Inservice Insp of CP Sgs,Per Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage.Rept Is Being Resubmitted Due to Typos in Original Rept ML20206E5781999-04-23023 April 1999 Informs That R Schukai Is No Longer Employed with Amerenue & Info Sent Is No Longer Required.Name Should Be Removed from Mailing Lists.Mailing Label Used by Company Which May Assist in Matter,Submitted ULNRC-04018, Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date1999-04-21021 April 1999 Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date ML20205Q7751999-04-16016 April 1999 Forwards Special Rept 98-03 Concerning ISI of Callaway SGs Performed in Apr 1998 During Callaway Plants Ninth Ro. Rept Documents Final SG Insp Results ULNRC-04015, Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.211999-04-15015 April 1999 Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.21 ULNRC-04005, Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.7901999-04-0707 April 1999 Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.790 ULNRC-04004, Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld1999-04-0707 April 1999 Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld ULNRC-04007, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date1999-04-0707 April 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date ULNRC-04000, Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w)1999-04-0101 April 1999 Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w) ULNRC-03998, Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.751999-03-30030 March 1999 Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.75 ML20205G2211999-03-25025 March 1999 Submits Rev 28A to Callaway Plant Physical Security Plan, Incorporating Addendum Re Security Sys Replacement Transition Plan,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20205R5251999-03-25025 March 1999 Forwards Special Rept 98-03 Re Results of Tenth SG Tube Inservice Insp,Per Requirements of Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage ULNRC-03988, Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 101999-03-19019 March 1999 Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 10 ULNRC-03991, Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette1999-03-19019 March 1999 Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette ML20204F7211999-03-17017 March 1999 Forwards Amended Fitness for Duty Program Performance Data for Six Month Period Beginning Jul-Dec 1998 ML20204E1331999-03-17017 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-02 on 990208-12.Corrective Actions:Will Revise Security Plan to Increase Min Staffing by Three Armed Security Force Response Personnel Per Shift ML20207C3631999-03-12012 March 1999 Forwards Exam Matl & Associated QA Checklist for Written Exam to Support Plant RO Retake Exam Scheduled for 990423. Exam Matls Requested to Be Withheld from Public Disclosure Until After Exam Completion 05000483/LER-1998-001, Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability1999-03-10010 March 1999 Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability ULNRC-03979, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date1999-03-0909 March 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date ULNRC-03975, Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl1999-03-0505 March 1999 Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl ULNRC-03971, Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded1999-02-26026 February 1999 Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded ML20207A4311999-02-17017 February 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for Period of 980701-981231 1999-09-15
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e-~ m 1901 Chouteau Avenue 1
. Post 0thce Box 149 1 St. Louis Masoun 63166 l
. 314-554-2650 l
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i j l l Umon September 24, 1996 0 i Etscnuc ~ ? " "c"'
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s U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 1 Mail Station P1-137 Washington, D. C. 20555-0001 :
I Gentlemen: ULNRC-3451 ;
TAC No, M95204 CALLAWAY PLANT DOCKET NUMBER 50-483 REVISION TO TECHNICAL SPECIFICATION j 3/4.4 - REACTOR COOLANT SYSTEM l 1
References:
- 1) ULNRC-3358 dated April 12, 1996 l
- 2) K. M. Thomas ltr to D. F. Schnell i dated July 25, 1996 l
This letter provides additional information in support of the Callaway Plant amendment application that proposes the installation of electrosleeves in the Callaway Plant steam generators. This information )
is. submitted in response to the request for additional l information transmitted by reference 2. The ;
significant hazards consideration determination, as previously transmitted in Attachment 4 of Reference 1, is still valid.
Framatome Technologies Inc. has determined that information associated with the installation process for electrosleeves is proprietary, and is j thereby supported by an affidavit signed by Framatome, 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 10CFR2.790. Accordingly, it is respectfully requested that the information which is (/
< proprietary to Framatome be withheld from public disclosure i1 accordance with 10CFR2.790. j
})f 9610020045 960924 PDR ADOCK 050004 3 g. gg aga : wc Nhl I wp
I i
l If you have any questions concerning this ;
information, please contact us.
Very truly yours, Donald F. Schnell WEK/
Attachments: 1) Proprietary Information Affidavit
- 2) Response to Request for Additional Information (Proprietary)
- 3) Response to Request for Additional Information (Non-Proprietary)
STATE OF MISSOURI ) l SS
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CITY OF ST. LOUIS )
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i Schnell,'of lawful age, being first duly sworn upoh, oath Donald F, that he is Senior Vice President-Nuclear and says an officer-of Union Electric Company; that he has read the ,
foregoing document and knows the content thereof; that he has l executed the same for and on behalf of said company with full !
power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
'By 'l DIc/fiald F. 'Schnell Senior Vice President Nuclear I
~ SUBSC]itIBE.D and sworn to before me this NW day
-of A44W --
, 1996.
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'l e r ry BARBARA J. PFAFE NOTARY PUBUC-STATE OF MISSOURf MY COMMISSION EXPlRES APRIL 22,1993 ST LOUIS COUNTY t
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- t cc: M. H. Fletcher Professional Nuclear. Consulting, Inc.
19041 Raines Drive Derwood, MD 20855-2432 I-L L. Joe Callan Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive j Suite 400 '
Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Kristine M. Thomas (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E16 11555 Rockville Pike ,
Rockville, MD 20852-2738 I Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102
.Ron Kucera Department of Natural Resources P.O. D6x 176 Jefferson City, MO 65102 Don Woodlan !
TU Electric 1601 Bryan Street Dallas, TX 75201-3411 Pat Nugent Pacific Gas & Electric .,
-Regulatory Services P.O. Box 56 Avila Beach, CA 93424
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AFFIDAVIT OF IAMES H. TAYLOR !
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l-l A. My name is James H. Taylor. I am Manager of Licensing Services for Framatome l
Technologies, Inc. (FTI), and as such, I am authorized to execute this Affidavit. j l
B. I am familiar with the criteria applied by FTI to determine whether certain information of FTI !
is proprietary and I am familiar with the procedures established within FTI to ensure the proper ,
application of these criteria.
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l C. In determining whether an FTI document is to be classified as proprietary information, an initial
- determination is made by the Unit Manager, who is responsible for originating the document, as to whether it falls within the criteria set forth in Paragraph D hereof. If the information falls j- within any one of these criteria, it is classified as proprietary by the originating Unit Manager. ;
- This initial determination is reviewed by the cognizant Section Manager. If the document is l
l designated as proprietary, it is reviewed again by Licensing personnel and other management within FTI as designated by the Manager of Licensing Services to assure that the regulatory requirements of 10 CFR Section 2.790 cre met.
l D. The following information is provided to demonstrate that the provisions of 10 CFR Section 2.790 of the Commission's regulations have been considered:
_(i) The information has been held in confidence by FTI. Copies of the document are clearly identified as proprietary. In addition, whenever FTI transmits the information to a customer, customer's agent, potential customer or regulatory agency, the
,_ ' transmittal requests the recipiem to hold the information as proprietary. Also, in l; order to, strictly limit any potential or actual customer's use of proprietary information, the substance of the following provision is included in all agreements l entered into by FTI, and an equivalent version of the proprietary provision is
! included in all of FTI's proposals:
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- AFFIDAVIT OF JAMES H. TAYLOR (Cont'd.)
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{ "Any proprietary information concerning Company's or its Supplier's ,
products or manufacturing processes which is so designated by Company or ,
its Suppliers and disclosed to Purchaser incident to the performance of such t
contract shall remain the property of Company or its Suppliers and is ,
disclosed in confidence, and Purchaser shall not publish or otherwise disclose ,
it to others without the written approval of Company, and no rights, implied or otherwise, are granted to produce or have produced any products or to practice or cause to be practiced any manufacturing processes covered thereby.
Notwithstanding the above, Purchaser may provide the NRC or any other j l
regulatory agency with any such proprietary information as the NRC or such other agency may require; provided, however, that Purchaser shall first give Company written notice of such proposed disclosure and Company shall have the right to amend such proprietary information so as to make it non-proprietary. In the event that Company cannot amend such proprietary information, Purchaser shall prior to disclosing such information, use its best efforts to obtain a commitment from NRC or such other agency to have such information withheld from public inspection.
- Company shall be given the right to participate in pursuit of such confidential treatment."
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AFFIDAVIT OF JAMES H. TAYLOR (Cont'd.)
(ii) The following criteria are customarily applied by FTI in a rational decision process to determine whether the information should be classified as proprietary. Information may be classified as proprietary if one or more of the following criteria are met:
- a. Information reveals cost or price information, commercial strategies, production capabilities, or budget levels of FTI, its customers or suppliers.
- b. The information reveals data or material concerning FTI research or development plans or programs of present or potential competitive advantage to FTI.
- c. The use of the information by a competitor would decrease his expenditures, in time or resources, in designing, producing -or marketing a similar product.
- d. The information consists of test data or other similar data concerning a l process, method or component, the application of which results in a competitive advantage to FTI.
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- e. The information reveals special aspects of a process, method, component or the like, the exclusive use of which results in a competitive advantage to FTI.
- f. The information contains ideas for which patent protection may be sought. ,
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- AFFIDAVIT OF JAMES H. TAYLOR (Cont'd.)
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l The document (s) listed on Exhibit "A", which is attached hereto and made a part hereof, has been evaluated in accordance with normal FTI procedures with respect j to classification and has been found to contain information which falls within one or !
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- more of the criteria enumerated above. Exhibit "B", which is attached hereto and made a part hereof, specifically identifies the criteria applicable to the document (s) -
i listed in Exhibit "A". !
l i (iii) The document (s) listed in Exhibit "A", which has been made available to the United
- States Nuclear Regulatory Commission was made available in confidence with a
- request that the document (s) and the information contained therein be withheld from l public disclosure.
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i j' (iv) The information is not available in the open literature and to the best of our
- knowledge is not known by Combustion Engineering, EXXON, General Electric,
! Westinghouse or other current or potential domestic or foreign competitors of FTI.
(v) Specific information with regard to whether public disclosure of the information is likely to cause harm to the competitive position of FTI, taking into account the value .
of the information to FTI; the amount of effort or' money expended by FTI developing the information; and the ease or difficulty with which the information could be properly duplicated by others is given in Exhibit "B".
E. I have personally reviewed the document (s) listed on Exhibit "A" and have found that it is d considered proprietary by FTI because it contains information which falls within one or more of the criteria enumerated in Paragraph D, and it is information which is customarily held in confidence and protected as proprietary information by FTI. This report comprises information l
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i AFFIDAVIT OF JAMES H. TAYLOR (Cont'd.)
i utilized by FTI in its business which afford FTI an opportunity to obtain a competitive advantage over those who may wish to know or use the information contained in the document (s). ;
I W b DAMES H. TAYLOR !
State of Virginia)
) SS. Lynchburg l City of Lynchburg) i James H. Taylor, being duly sworn, on his oath deposes and says that he is the person who i subscribed his name to the foregoing statement, and that the matters and facts set forth in the statement are true.
/ JAMES H. TAYLOR ,
Subscribed and sworn before me this[ day of dublev 1996.
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Notary Public in and for the City of Lynchburg, State of Virginia.
My Commission Expiresdly R /W) 5 I
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EXHIBITS A & B EXIIIBIT_A
" Proprietary" Responses to Request for AdditionalInformation (RAI) Regarding Union i Electric Company's Request for Amendment to the Technical Specifications for Callaway l Plant, Unit 1. This information was transmitted in J. H. Taylor's letter (JHT/96-59) to Ms. l Kristine M. Thomas (NRC), dated September 12, 1996.
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EXHIBIT B ,
The above listed document contains information which is considered Proprietary in accordance with Criteria b, c, d, and e of the attached affidavit.
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REQUEST FOR ADDITIONAL INFORMATION ,
UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483 i
- Subject Egges I 1' Questions / Answers ...... 10 Attachment 1 ...... 2 Attachment 2 ...... 3 ll 2
Attachment 3 ...... 7 .
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FTI Non-Proprietary Table of Contents 1
REQUEST FOR ADDITIONAL INFORMATION i UNION ELECTRIC COMPANY
- CALLAWAY PLANT, UNIT 1 i
DOCKET NO. 50-483 1
The following information relating to the proposed Framatome electrosleeving process for repairing steam generator tubes at the Callaway plant is needed. Answers provided to I j Questions 1 through 4 should address both ultrasonic and eddy current inspection methods.
- Ql. Framatome presented only limited information on the inspection of Electrosleeves 4
for the detection of laboratory Jnduced stress corrosion cracking (SCC) in the parent tube. Discuss the detection threshold for SCC tube flaws (axial and circumferential) l in electrosleeved tubes using the actual field data analysis procedures for degradation i i located at expansion transitions and dented tube support plate intersections. Also l include a discussion of the potential masking of the outside-diameter parent tube defects caused by asymmetric variations in the sleeve thickness at the exit and entrance regions.
A1. UT inspection of the nickel and alloy 600 depends on the transmission and reflection of a sound wave through the combined layer.
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FTI has used the Electrosleeve" UT system to perform field examination of steam generator tubes associated with subsequent tube pulls. Data has been collected on i tubes, including both TSP /freespan regions and Top of Tubesheet (ITS) roll expansion transitions. )
Table 1 presents the results of the comparison.
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Qualification of an ECT technique for inspecting an Electrosleeve i The qualification include both EDM notches and laboratory- J induced SCC.
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Q2. Since the electrosleeving process enables detection of parent tube flaws beneath the sleeve, define and provide the basis for a plugging criteria for tubes with a measurable change (from the initial inspections) in NDE signal response for
- indications located belov the Electrosleeve . If these criteria rely on the ability to i depth size indications, provide a detailed description of the qualification process to
- assess these depths. Include a description of the flaws (i.e., SCC versus EDM notches, orientation, depths, nurnber of samples, etc.) used to qualify the method.
Also discuss the potential influence on flaw depth measurement due to variations in sleeve wall thickness.
l A2. As discussed in response to Question 1, FTI has applied the Electrosiceve" UT j system in the field to examine tube pull candidates. l l;
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The pulled tubes discussed above did not have Electrosiceves installed at the defect locations. FTIis of documenting UT-360 crack sizing of stress ,
corrosion cracks under an installed Electrosleeve .
l discusses the UT qualification program performed on electrosleeved tubes with EDM notches and flat bottom holes.
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j- The qualification program of an ECT technique i
Q3. Eddy current inspection methods may be more sensitive than ultrasonic techniques for the detection of pits and nodules introduced in the fabrication process. Discuss the need to use diverse inspection methods for accepting Electrosleeves following the installation process.
A3. The ASME Boiler and Pressure Vessel Code Case N-569 (Reference 3) defines the general requirements for electrochemical deposition repair of steam generator tubes.
This Code Case states that NDE acceptance of the repair shall be performed on the entire volume of the deposit with the ultrasonic method. This is in agreement with Installation acceptance (bonding, verification of thickness, and evaluation of defects or inclusions) requires the use of UT examination. UT is also planned for future inspections. However, ECT will also be performed at installation to provide a baseline for future inspections.
Q4. .At what tolerance level can the sleeve thickness be measured using the proposed field data analysis procedures?
A4.- The field UT data analysis equipment and procedures can measure sleeve thickness to an accuracy of is not intended to measure sleeve thickness.
QS. During the presentations on July 2,1996, NDE data was presented that suggested that inservice operation of electrosleeves can expand unbonded areas between the sleeve and tube. Define the acceptance criteria, if any, for electrosleeved tubes with identified unbonded regions addressing the potential for these areas to expand over the next operational cycle.
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k A5. The information presented on July 2,1996 relative to " inservice operation" was based on the Electrosleeve* installation at Pickering in April-May 1994. Attachment 4,
- pages 10 through 13 of Reference 2 discussed this evaluation. The surface of the alloy 400 tubes at Pickering were cleaned using i
j The alloy 600 tubing is cleaned to remove oxides followed by step to remove any remaining oxides t
The alloy 600 cleaning process was qualifled L
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Acceptance of an installed Electrosleeve with an unbonded area depends on review i
of the complete installation. The minimum bond length required on the ends of the sleeve which span a defect area is defined in Reference 1 The ASME Section XI Code Case (Reference 3) which considers initial installation inspection requirements defined the acceptance criteria as any disbond length greater than 0.250 inch is unacceptable.
i Q6. The electrosleeving process requires a clean tube surface prior to electrochemical deposition of the sleeve. For tubes with geometry changes in the vicinity of the parent tube defect, this will largely depend on the ability to remove all tube deposits during the cleaning / activation step. Discuss the ability of the cleaning / activation step to remove tube deposits. If previous testing has been conducted to assess this issue, discuss the similarity between the deposits on inservice steam generator tubes and those used in the tests.
A6. As stated in the response to question 5, the cleaning process for alloy 600 tubing to remove oxides followed by step to remove any remaining oxides of alloy 600 material. This step is very aggressive due to the FTI Non-Proprietary Page 4 of 10
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- the alloy 600. The step is not sensitive to the j tube ID contours because an electrochemical cell containing a fluid at temperature and i
pressure is established by the probe to clean the tube.
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Q7. Has Framatome contacted a third-party reviewer (not a customer) to examine the i overall plating process? If so, provide a summary of the review scope and the findings.
A7. Framatome has not directly contacted a third-party reviewer to examine the overall plating process. independent reviews have been performed; an ASME working group there is I substantial relevant experience with acceptance of nickel plating in Europe.
ASME SECTION XI. An ASME Code Case for repair of steam generator tubes by electrochemical deposition was submitted to the ASME Section XI for review and approval. As a result of this request, an ASME working task force was assembled and performed several reviews which included a technical review of the actual equipment used to perform the process. The working group consisted of 12 members with diverse technical backgrounds. The results of this review found the process to be acceptable. The ASME Code Case was subsequently approved [3].
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! RELEVANT EXPERIENCE. As discussed nickel plating of
. defective steam generator tubes has been performed successfully by Framatome for l over 10 years in Europe.
4 i papers documenting testing and
- experience are referenced .
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! Q8. - During any plating process, bonding is dependent on two basic things: (1) cleanliness of the parent surface material, and (2) minimal resistance to current path. How does Framatome propose to ensure that these two items are within a high certainty of optimum cleanliness and current flow? What is the range of acceptable parameter variations?
A8.
Bonding is verified with UT after each Electrosleeve" installation.
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Q9. Since the sleeve is a deposit of Ni rather than a forged material, what does l Framatome propose to do about qualifying this material as a reactor coolant boundary from the QA/QC gsgctive? It has been staff experience that commercial sources of i expendables for use in safety-related applications are often problematic - i.e.,
j purchases of greases, oils, powders, resins, boron, lithium, and zine (for zinc l l
injection). Describe the actions taken to assure an effective commercial dedication 4
program for materials to be obtained from commercial suppliers. How has Framatome addressed this issue with respect to the consumables important to the
- plating process? What protocol is in place to ensure acceptability?
A9. FTI has an Electrosleeving Chemical Procurement procedure that specifies the steps to
- be taken for the procurement and the inventory control of chemicals to be used in this
] process. This procedure references the Electrosleeving Chemical Procurement Specifications document that lists the content requirements for each chemical.
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. The documentation for the chemicals used are provided to the customer in the form of a data package to support transportation, receipt, and control at a plant site.
Q10. In conjunction with the preceding question, what chemical or elemental species has Framatoms identified that are particularly deleterious to a successful cleaning / plating l job? What acceptable concentration levels for such containments been established?
Describe programs such as receipt inspection for conformance that have been established.
i A10. The response to question 9 provides information on receipt and inspection programs.
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Q11. Describe any engineering evaluations and independent confirmatory tests regarding electrosleeving that were performed by Union Electric prior to submittal of the license amendment. Describe any ongoing engineering evaluations. l l
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$ All. Union Electric was represented when FT1
, presented an overview of the topical and the methodology used in the structural testing. Additional evaluation was performed in conjunction with the evaluation and
. preparation of tlee ASME Section XI code case. The Safety Evaluation and i Signifiant Hazards Evaluation were prepared by Union Electric and reviewed for technical input relative to the Electrosleeve repair option. Relative to " independent !
confirmatory tests by Union Electric", none were conducted.
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Attachments:
- 1. Table 1. SCC Depth Sizing
- 2. Table 2. EDM Notch Depth 3.
References:
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- 1. Topical Report BAW-10219P, Rev 1, "Electrosleeving Qualification for PWR Recirculating Steam Generator Tube Repair", March 1996.
- 2. " Proprietary" Presentation Material from July 2,1996 Meeting in Lynchburg Va on Electrosleeving, as defined in Union Electric Company, Technical !
Specification Amendment, Docket 50-483, NRC Meeting Notice dated June 17,1996.
- 3. ASME Section XI, Division 1, Code Case N-569, Alternative Rules for Repair by Electrochemical Deposition of Class 1 and 2 Steam Generator Tubing.
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i Attachment 1 l Table 1. SCC Depth Sizing l (2 Pages)
LABEL Defect PERCENT THROUGH WALL (% TW) l l Type ACTUAL UT-360 DELTA t
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! Table 1. SCC Depth Sizing (2 Pages) l 3
LABEL Defect PERCENT THROUGH WALL (% TW)
Type -ACTUAL UT-360 DELTA a
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j Table 2. EDM Notch Depth Sizing l (3 Pages) i m
Flaw Flaw Actual Percent Through Wall (%TW) i Label Type %TW Analyst 1 Analyst 2 Delta 1 Delta 2
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' Table 2. EDM Notch Depth Sizing j' (3 Pages) i j Flaw Flaw Actual Percent Through Wall (%TW) l Label Type %TW Analyst 1 Analyst 2 Delta 1 Delta 2 i
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Table 2. EDM Notch Depth Sizing
! (3 Pages)
Note: 1.
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