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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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Union Electric po Box 620 Calleway FIant Fulton, MO 65251 April 28,1999 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop PI-137 Washington, DC 20555-0001 77ggg ULNRC-4019
- E Gentiemen:
DOCKET NUMBER 50-483
, CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 98-03 RESULTS OF TIIE TENTH STEAM GENERATOR TUBE IN-SERVICE INSPECTION The enclosed Special Report is submitted pursuant to the requirements of Callaway Technical Specification 4.4.5.5.b concerning the Inservice Inspection of Callaway's Steam Generators performed in April,1998 during Callaway Plant's ninth refueling outage. This report documents the final Steam Generator inspection results.
This is being resubmitted because the previous letter (ULNRC-3993) was inadvertently sent with two typographical errors: one in Table 3 and one in Table 4. Specifically in Table 3, the tube imperfection located at row 43, column 30, should be deleted. Also, in Table 4, the tube imperfection located at row 32, column 111, with a location of AV2 and +10.27, should be changed to AV3 and 0.00. We are sorry for any inconvenience this may have caused.
1 gL R. . Affolter Manager, Callaway Plant RDA/HDB/TWP/ GAG Enclosure
4, .e
- 4 W 9905050080 990428 PDR ADOCK 05000483 G PDR e subsidinty of Amoren Corporation
ULNRC-4019 Page 2 l-cc:
' U. S. Nuclear Regulatory Commission (Original and I copy)
! Attn: Document Control Desk .
Mail Stop Pl-137 Washington, DC 20555-0001 Mr. Ellis W. Merschoff Regional Administrator U.S. Nuclear Regulatory Commission Region IV l 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office l U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman,MO 65077 Mr. Melvin K. Gray (2 copies) ;
Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation ;
U. S. Nuclear Regulatory Commission i Mail Stop 13E16 Washington, DC 20555-2738 Manager, Electric Department
.- Missouri Public Service Commission PO Box 360 l Jefferson City, MO 65102 Deputy Director Department of Natural Resources PO Box 176 Jefferson City, MO 65102 i
Superintendent, Licensing Wolf Creek Nuclear Operating Corporation PO Box 411 Burlington,KS 66839
. s ULNRC-4019 Page 1 of 15 SPECIAL REPORT 98-03 RESULTS OF TENTH STEAM GENERATOR TUBE IN-SERVICE INSPECTION i
INSPECTION REOUIREMENTS:
This report is submitted in accordance with Technical Specification (T/S) 4.4.5.5.b, which states:
The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shallinclude:
- 1) Number and extent of tubes and sleeves inspected,
- 2) Location and percent of wall-thickness penetration for each indication of an imperfection, and
- 3) Identification of tubes plugged or repaired.
INSPECTION REPORT:
In April 1998, with the plant in Mode 6 for the ninth refueling outage, the tenth Steam Generator (S/G) Eddy Current Inservice Inspection was performed by Westinghouse Electric Corporation. The final results of this inspection are summarized below and are numbered to correspond with the information requested by T/S 4.4.5.5.b. ,
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j ULNRC-4019 Page 2 of 15 (1) Number / Extent ofInspected Tubes and Sleeves Table I below shows the scope of the eddy current inspections performed during Refuel 9 at the Callaway Plant. As shown in this table, eddy current inspections were performed on 100% of the tubes in Steam Generators B and C using the standard bobbin coil probe, and eddy current inspections were performed on 100% of the top of tubesheet (hot leg) on all four steam generators using a PlusPoint RPC probe. Additionally, eddy current inspections were performed on the Row I U-bends in Steam Generator A using a PlusPoint RPC probe.
Table 1 Eddy Current Inspection Program Summary Work Scope S/G A S/G H S/G C S/G D Bobbin coil, fulllength 0 5589 5562 0
+ Point RPC, top of tubesheet, 5531 5589 5529 5549 hot leg - +2"/-3"
+ Point, RPC, U-bend 121 0 0 0 l
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ULNRC-4019 Page 3 of15 (2) Location / Percent of Wall-Thickness Penetration for Each Indication of
., . Imperfection See Tables 2,3,4, and 5 on the following pages for steam generator tube imperfections found during the eddy current inspection during Refuel 9. The imperfections listed in these tables are those showing 20% or greater tube wall thinning. The key below provides a description of the abbreviations used
. in these tables:
TABLES 2. 3. 4. AND 5 KEY AV1,2,3,4,5,6 - Anti-Vibration Bars 02H, 07H, 07C, etc. - Tube Support Plate Numbers / Cold Leg (C), Hot Leg (H)
TSH - Tubesheet Hot Leg SAI- Single AxialIndication MAI- Multiple AxialIndication SCI - Single Circumferential Indication MCI - Multiple Circumferential Indication l SVI- Single Volumetric Indication f
MV1 - Multiple Volumetric Indication i
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TUBE IMPERFECTIONS - STEAM GENERATOR 'A' INDICATION % INCH (+) FROM l ROW COLUMN WALL THINNING LOCATION LOCATION
! 21 25 SCI TSH -0.04 18 26 SA! TSH +0.05 21 37 SCI TSH -4.92 i 27 38 SCI TSH -1.11 21 42 SCI TSH -0.42 18 46 SCI TSH -0.14 17 - 49 sal TSH +0.04 12 53 SCI TSH -0.05 19 55 SCI TSH +0.11 21 56 SAI TSH +0.16 13 57 sal TSH +0.09 21 58 SCI TSH +0.16 14 59 SCI TSH 0.00 39 59 MAI TSH -0.01 30 60 SCI TSH -0.11 46 60 sal TSH +0.01 30 62 SCI TSH -0.04 29 65 SAI TSH +0.02 36 65 SCI TSH -0.05 32 68 SAI TSH +0.08 13 70 sal TSH +0.12 15 70 SCI TSH -0.08 22- 70 MCI TSH +0.04 11 79 sal TSH +0.07 32 79 SAI TSH 0.00 40 80 sal TSH +0.01 19 82 sal TSH +0.08 30 83 SCI TSH 0.00 41 88 SAI TSH -0.05 38 90 SCI TSH 0.00 35 - 99 SAI TSH +0.05 15- 114- SCI TSH +0.03 i
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TABLE 3 TUBE IMPERFECTIONS - STEAM GENERATOR *B' l
INDICATION % INCH (+) FROM i ROW COLUMN WALL THINNING LOCATION LOCATION
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l 37 20 40 AV4 0.00 I 50 47 42 AVS 0.00 12 58 SAI TSH +0.09 54 67 43 AV2 0.00 28 8 26 AV6 0.00 29 9 37 AV5 0.00 30 10 23 AV2 -0.12 1 32 11 33 AV6 -0.25 l 32 12 27 AV4 0.00 l 33 12 23 AV3 0.00 !
32 13 21 AV5 -0.17 33 14 26 AV5 -0.20 37 18 36 AV2 -0.14 37 18 37 AV3 -0.11 39 18 21 AV2 -0.09 39 18 34 AV4 -0.03 36 19 22 AV3 0.00 ,
37 19 28 AV4 0.00 37 20 21 AV2 0.00 37 20 40 AV4 0.00 42 23 21 AV3 -0.03 42 23 21 AV4 0.00 42 24 21 AV3 +0.03 42 24 34 AV4 -0.11 42 24 29 AV5 -0.31 4 45 24 27 AV5 -0.06 l 42 25 22 AV4 -0.17 i 50 28 27 AV5 0.00 41 30 24 AV2 -0.09 I 42 30 25 AV3 -0.03 42 30 21 AV4 -0.17 I
49 31 24 AV2 -0.06 49 31 28 AVS -0.20 39 32 24 AV2 +0.40 39 33 23 AV2 -0.19 40 35 25 AV5 +0.25 26 43 21 AV2 0.00 l 26 43 24 AV6 0.00 l 35 43 34 AV3 0.00 l
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ULNRC-4019 Page 6 of 15 TABLE 3 TUBE IMPERFECTIONS - STEAM GENERATOR 'B' INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 35 43 24 AV5 -0.28 26 45 26 AV1 +0.23 26 45 24 AV6 +0.03 35 45 31 AV3 +0.03 47 45 34 AV3 +0.03 47 45 27 AV4 +0.03 50 47 37 AV3 -0.28 50 47 33 AV4 -0.08 50 47 42 AV5 0.00 50 47 25 AV6 -0.36 50 53 30 AV4 0.00 43 57 22 AV3 0.00 50 58 26 AV2 0.00 47 59 25 AV2 0.00 47 59 22 AV3 0.00 47 59 37 AV4 0.00 54 61 31 AV2 0.00 47 63 26 AV2 0.00 40 64 35 AV3 -0.40 40 64 25 AV4 +0.30 26 65 23 AV2 +0.03 26 65 33 AV5 0.00 46 66 26 AV4 0.00 47 66 24 AV2 0.00 47 66 29 AV4 0.00
( 54 67 43 AV2 0.00 54 67 24 AV3 0.00 54 67 30 AV4 0.00 54 67 25 AV5 +0.11 42 68 30 AV2 +0.03 42 68 30 AV3 +0.20 42 68 22 AV4 -0.08 42 68 30 AVS +0.03 42 68 27 AV6 -0.17 47 69 21 AV2 0.00 55 71 27 AV4 -0,08 55 71 26 AV5 -0.30 50 72 21 AV3 -0.06 41 74 38 AV4 +0.08 41 74 38 AV5 + 1.32 I-
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TABLE 3 4
TUBE IMPERFECTIONS - STEAM GENERATOR 'B' l lNDICATION %
! ROW INCH (+) FROM f COLUMN WALL THINNING LOCATION LOCATION I t
49 75 21 AV2 -0.54 37 76 28 AV3 -0.31 37 76 31 AV4 +0.08 i 39- 79 25 AV3 -0.06 39 79 24 AV4 +0.14 35 82 30 AV3 0.00 40 83 29 AV4 -0.19 40 83 21 AV5 -0.11 42 85 21 AV4 -0.11 43 85 24 AV3 +0.03 46 86 33 AV3 0.00 46 86 24 AV4 +0.08 50 86 33 AV4 +0.19 50 86 36 AV5 +0.03 46 88 23 AV2 -0.14 l 40 89 24 AV2 0.00 I 40 89 33 AV3 0.00 40 89 30 AV5 0.00 42 90 35 AV4 0.00 46 91 31 AV2 -0.03 ,
46 91 33 AV4 -0.14 49 93 24 AV3 0.00
'42 98 33 AV3 0.00 l 42 98 32 AV5 0.00 44 98 22 AV4 0.00 44 98 26 AV5 0.00 44 98 21 AV6 0.00 46 98 21 AV3 0.00 46 98 27 AV4 0.00 48 98 33 AV4 +0.06 42 99 23 AV5 0.00 41 100 30 AV5 0.00 42 103 31 AV5 0.00 I 34 110 24 AV3 0.00 32 112 22 AV5 0.00 30 113 21 AV5 0.00 30 114 21 AV1 0.00 i
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TABLE 4 TUBE IMPERFECTIONS - STEAM GENERATOR 'C' INDICATION % INCH (+) FROM l
ROW COLUMN WALL THINNING LOCATION LOCATION l
28 11 SCI TSH +0.09 27 13 SCI TSH +0.09 l 20 17 SAI TSH + 0.10 l
23 18 sal TSH +0.02 ;
31 19 SCI TSH +0.08 l 42 21 SVi TSH +0.05 l 22 24 SCI TSH +0.01 31 24 SCI TSH +0.01 46 37 41 AV4 0.00 50 45 46 AV4 0.00 19 46 SCI TSH +0.10 51 46 SCI TSH +0.10 12 47 SAI TSH +0.12 49 48 40 AV3 0.00 12 50 SCI TSH 0.00 14 51 sal TSH +0.13 52 51 SCI TSH -0.02 11 53 SAI TSH +0.52 31 53 SCI TSH +0.10 11 57 SAI TSH +0.60 12 57 SAI TSH +0.48 12 59 mal TSH +0.33 30 60 SCI TSH -0.01 40 70 SCI TSH 0.00 48 71 SCI TSH +0.11
'16 76 SCI TSH -2.51 47 79 SCI TSH +0.06 47 91 41 AV4 0.00 43 92 47 AV4 0.00 50 92 SCI TSH -0.04 22 99 sal TSH +0.08 44 100 43 AVS 0.00 41 105 51 AV5 0.00 13 107 SCI TSH +0.05 32 109 43 AV5 0.00 30 114 50 AV5 0.00 24 6 26 AV1 0.00 l 27 8 27 AV1 0.00 l 28 8 34 AV1 +0.17 l 28 8 33 AV1 -0.11
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.. .. TABLE 4 TUBE IMPERFECTIONS - STEAM GENERATOR 'C' INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 28 9 21 AV5 0.00 29 9 21 AV5 0.00 30 12 26 AV5 0.00 i 34 15 39 AV2 0.00 37 15 22 AV5 0.00 35 16 29 AV1 +0.08 36 16 22 AV3 +0.14 36 16 23 AV4 0.00 36 18 34 AV4 0.00 40 18 28 AV2 +0.03 I 37 19 31 AV3 0.00 40 20 31 AV4 0.00 50 28 32 AVS 0.00 50 28 29 AV6 0.00
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39 29 26 AV2 0.00 46 29 31 AV4 0.00 '
42 33 28 AV2 +0.08 ,
36 35 23 AV3 0.00 {
46 35 23 AV2 0.00 1 46 35 21 AV3 0.00 46 35 24 AV4 0.00 40 37 29 AV3 -0.03 40 37 25 AV4 +0.06 46 37 32 AV2 0.00 1 46 37 24 AV3 +0.14 46 37 41 AV4 +0.44 27 39 22 AV1 0.00 27 39 34 AV5 +0.08 46 39 21 AV2 0.00 ,
45 41 22 AV2 0.00 !
45 41 31 AV4 0.00 l 46 41 23 AV2 0.00 46 42 24 AV3 0.00 40 43 23 AV2 0.00 35 44 23 AV3 0.00 50 45 40 AV2 0.00 45 45 AV3 0.00 50 45 46 AV4 0.00 24 46 22 AV6 0.00
- 40. 46 24 AV3 0.00
l ULNRC-4019 Page 10 of 15 TABLE 4 l l TUBE IMPERFECTIONS - STEAM GENERATOR 'C' INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 49 48 40 AV3 0.00 49 48 23 AV4 +0.22 36 52 29 AV2 0.00 36 52 23 AV4 0.00 36 54 28 AV3 0.00 37 56 22 AV3 0.09 37 59 28 AV3 0.00 49 61 22 AV5 0.00 32 62 21 AV2 0.00 18 63 26 AV5 0.00 49 63 23 AV2 0.00 49 63 27 AV4 0.00 49 63 23 AV5 0.00 45 64 26 AV5 +0.17 48 64 23 AV5 -0.03 44 71 25 AV3 -0.14 44 71 36 AV4 0.00 44 71 38 AV5 0.00 44 71 25 AV6 +0.03 41 79 22 AV6 0.00 36 80 23 AV4 0.00 41 81 28 AV3 0.00 41 81 28 AV4 0.00 41 81 22 AV5 0.00 42 82 22 AV4 0.00 29 84 27 AV2 0.00 48 85 24 AV3 0.00 41 87 23 AV2 0.00 41 87 25 AV3 0.00 41 87 25 AV4 0.00 41 87 24 AV6 +0.22 47 87 26 AV2 0.00 47 87 28 AV5 0.00 41 88 21 AV4 0.00 48 89 21 AV4 +0.16
'48 89 28 AV5 +0.19 46 90 21 AV3 0.00 l 46 90 32 AV4 0.00 l 53 90 34 AV5 0.00 i
47 91 25 AV2 0.00 l
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ULNRC-4019 Page 11 of 15 l , . TABLE 4 TUBE IMPERFECTIONS - STEAM GENERATOR 'C' l
i INDICATION % - INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION i
47 91 23 AV3 0.00 l 47 91 41 AV4 0.00 47 91 28 AV5 0.00 43 92 33 AV3 +0.17 43 92 47 AV4 0.00 43 92 25 AV5 +0.06 46 93 27 AV3 0.00 47 93 25 AV2 0.00 47 93 28 AV3 0.00 47 93 27 AV4 +0.08 47 93 38 AV5 0.00 47 93 23 AV6 0.00 49 93 27 AV4 0.00 49 93 32 AV5 0.00 51 93 21 AV4 0.00 43 94 23 AV1 0.00 43 94 23 AV2 0.00 43 94 31 AV3 0.00 I 43 94 36 AV4 0.00 43 94 23 AV6 0.00 49 95 34 AV4 0.00 l 49 95 25 AV5 0.00 42 96 23 AV2 +0.09 42- 96 31 AV5 0.00 45 97 25 AV6 +0.06 40 100 36 AV5 0.00 44 100 43 AV5 0.00 40 103 26 AV2 0.00 40 103 33 AVS 0.00 43 103 21 AV4 0.00 43 103 27 AVS 0.00 43' 103 29 AV6 0.00 39 105 27 AV3 0.00 39 105 33 AV4 0.00 39 105 26 AV5 0.00 41 105 42 AV4 0.00 41 105 51 AV5 0.00 41 105 28 AV6 0.00 14 106 21 AV1 0.00 35 107 21 AV4 0.00
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TABLE 4 TUBE IMPERFECTIONS - STEAM GENERATOR 'C' INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 32 109 43- AV5 0.00 32 110 29 AV5 0.00 32 110 21 AV6 0.00 33 110 34 AV4 0.00 36 110 32 AV4 0.00 l 32 111 21 AV3 0.0G 32 111 21 AV3 -0.03 33 111 23 AV4 0.00 33 111 26 AV6 0.00 30 113 24 AV5 0.00 30 114 39 AV2 0.00 30 114 50 AV5 0.00 4
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INDICATION % INCH (+) FROM ROW ' COLUMN WALL THINNING LOCATION LOCATION 28 45 SCI TSH -4.76 24 59 SCI -TSH -3.64 17 61 SCI TSH 0.00 13 102 SCI TSH -4.20 .;
21 116 SCI TSH 0.04 l
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-(3) Identification of Tubes Plugged or Repaired Table 6 STEAM GENERATOR TUBES PLUGGED DURING REFUEL 9 I S/G A S/G B S/G C S/G D i ROW COL ROW COL ROW COL ROW COL 21 25 37 20 28 11 28 45 18
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26 50 47 27 13 24 59 21 37 12 58 20 17 17 61 27 38 54 67 23 18 13 102 21 42 31 19 21 116 18 46 42 21 17 49 22 24 12 53 31 24 19 55 46 37 21 56 50 45 13 57 19 46 21 58 51 46 14 59 12 47 39 59 49 48 30 60 12 50 46 60 14 51 1 30 62 52 51 29 65 11 53 i 36 65 31 53 32 68 11 57 13 70 12 57 1 15 70 12 59 l
22 70 30 60 i 11 79 40 70 l I
32 79 48 71 40 80 16 76 19 82 47 79 30 83 47 91 41 88 43 92 1 38 90 50 92 35 99 22 99 15 114 44 100 41 105 13 107 32 109 30 114 l
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Table 7 l STEAM GENERATOR CUMULATIVE TUBE PLUGS l-PERIOD S/G A S/G B S/G C S/G D TOTAL Previous 51 37 64 77 229 l Refuel 9 32 4 36 5 77 TOTAL 83 41 100 82 306 l
No tubes were sleeved during Refuel 9.
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