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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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Text
canunam Pau Cnia Bu (20
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U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 ULNRC-2757 Gentlemen:
DOCKET NUMlu.R 50-483 CALLAWAY PLANT UNIT I FACILITY OPERATING Ln~FESE NPF SPECIAL REPORT 92-03' (SOS 92-1293)
RESULTS OF TIIE SIXTII STEAM GENERATOR TlillE INSERVICE INSPECTION Ref: ULNRC-2637, dated 5/13/92 The enclosed Special Report is submitted pursuant to the requirements of Callaway Technical Specification 4.4.5.5.b concerning the sixth Inservice Eddy Current Inspection of Steam Generators 'B' and 'C' performed in April 1992, during Callaway Plant's fifth refueling outage. This report documents'the final Conam inspection results.
/
L W. R. Campbell-'
l Manager, Callaway Plant WRC/SES/MAIUlrj Attachments: 1) Tables 1 & 2-
- 2) Eddy Current Examination Conam Nuclear, Inc. :
cc: Distribution attached
!- 9302120086 930129 3
. DR -ADOCK 0500 aA Qk.
+ ,
+
cc distribution for ULNRC-2757 hir. A. Bert Davis' hir. L. Raynard Wharton
-Regional Administrator ' U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission OWFN -hiail Stop 13E21 Washington, D. C. 20$55
~
Region III 799 Roosevelt Road Glen Ellyn,IL 60137 hianager, Electric Department hir. Art hiah hiissouri Public Service Commission Wolf Creek Nuclear Operating Corp.
P. O. Box 360 P. O. Box 411
-Jefferson City, hiO 65102 Burlington, Kansas,66839 Records Center . hir. I. N. Jackiw Institute of Nuclear Power Operations Chief, Project Section 3C. .
Suite 1500 U. S. Nuclear Regulatory Commission 1100 Circle 75 Parkway Region IIIJ _ .
Atlanta, GA 30339 799 Roosevelt Road' .
Glen Ellyn, IL -60137 '
NRC Senior Resident Inspector
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EDDY CURRENT EXAMINATION UNION ELECTRIC COMPANY CALLAWAY, UNIT 1 STEAM GENERATORS B & C APRIL 1992 o
CONAM NUCLEAR, INC
a
- s SPECIAL REPORT 92-03 RESULTS OF SIXTII STEAM GENERATOR tulle INSERVICE INSPECTION 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 I
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 inspected, (2) Location and percent <3 all-thickness penetration for each indication of an imperfection, a...
(3) Identification of tubes plugged."
In April 1992, with the plant in Mode 6 - Refueling for the fillh refueling outage, the sixth plant Steam Generator (S/G) Eddy Current Inservice Inspection was performed. S/G's _'B' and 'C' were inspected. The inspection was performed by Conam Nuclear, Inc. and their formal results are detailed in the Eddy Current Examination (ECE) which is submitted with this Special Report.
Although the Conam ECE provides details on the inspection, the results are summarized below and are numbered to correspond with the information requested by T/S'4.4.5.5.b:
(1) Number / Extent ofInspected Tubes (a) Inspection Summary:
S/G 'II' S/G 'C' S/G 'D' Tubes Plugged (Refuel 5) 15 14 2 Tubes Previously Plugged 9 19 28 Total Tubes Plugged 24 33 -30
Page 2 SPECIAL REPORT 92-03 S/G 'll' S/G 'C' Tubes evaluated with 5617 5607 standard bobbin coil
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Tubes plugged previously 9 19 '
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Total Tubes 5626 5626 Tubes further evaluated with MRPC probes' .
l 0711 - 07C 0 244 03C - 02C 2 1 04C - 03C 0 2 OlC - TSC 0 1 ,
FBC - TSC 0 1 FEH - FBH 0 1 -
TSH - FBli 1 0-TSH - TSH 603 4 05C - 05C 1 0 OIC - OlC 1 0 TSC - TSC 4 4 07C - 07C 0 1 4
OlH - OlH 0 1 Tubes evaluated with probetype 8xt:
07H - 07C 0 11
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SPECIAL REPORT 92-03 (b) Steam Generator 'B' One hundred percent of the unplugged tubes or five thousand six-hundred seventeen (5617) tubes were tested fu!! length using the standard bobbin coil probe. In addition to the bobbin probe examination,603 hot leg tube sheet interfaces were examined using a three-coil MRPC (motorized rotating pancake coil) probe.
This probe utilizes one pancake coil, one coil sensitive to axial indications and one coil sensitive to circumferential indications.
There were no indications reported at the tube sheet interface, During this outage, there were eleven (11) tubes plugged in Steam Generator 'B' for anti-vibration bar (AVB) indications above 40 percent .
through wall depth. Union Electric elected to plug four (4) additional q tubes with indications above 35%. -
(c) Steam Generator 'C';
One hundred percent of the unplugged tubes or five thousand six hundred seven (5607) tubes were tested full length using the bobbin coil probe. In addition to the bobbin probe examination,- all Row I and 2 U-bends were examined with a three-coil MRPC probe.
Fourteen (14) tubes were plugged in Steam Generator 'C'. Seven (7) tubes were pluggeo when anti-vibration bar indications exceeded 40 [
percent. Union Electric elected to plug seven (7) additional tubes with indications of 29,33,36,37,38,39 percent, and an undefined '
indication (UDI).
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Page 4 SPECIAL REPORT 92-03 Tube, Row 2 Column 98, was reported as having an UDI 1-1/2 above the seventh cold leg support plate. As a result of this anomaly, this tube was included in the fourteen (14) removed from service. Another tube, Row 40 Column 106, was reported as having an indication at the fourth AVB that measured 79 percent through wall with a voltage response of 34 volts This large volume indication prompted an 8xl probe (8 surface-riding coils) examination of selected tubes with AVB wear =
indications to determine if the wear was on one or two sides of the tube. The results of this 8xl examination showed that all AVB indications were on one side of the tube only, (2) Location / Percent of Wall-Thickness Penetration for Each Indication of Imperfection See Tables 1 and 2 (Percent of wall-thickness penetrations are shown for indications >f > 15%j (3) Identification ofTubes Plugged from the Sixth In crvice Inspection Union F..ctric replaced all Westinghouse Inconel 600 mechanical tube plugs in the hot legs of all four (4) steam generators with Inconel 690 plugs.
Thirty-seven (37) plugs were replaced: 6 in S/G 'A', 6 in S/G 'B',
15 in S/G 'C', and 10 in S/G 'D'. All tubes plugged in the sixth inservice inspection used Inconel 690 plugs.
IL Page$
3PECIAL REPOllT 92-03 STEAM GENERATOR 'll STEAM GENERATOR 'C'
% INI)l- % INI)),-
ROW COI,11M N CATION ItOW C O I,II M N CATION 30 9 35 32 10 38 41 19 44 41 19 39 41 20 49 44 22 51 41 22 38 43 23 44 49 28 41 44 23 33 51 32 44 45 24 29 51 69 T9 45 34 53 23 70 39 12 56 41 47 73 48 41 64 51 51 73 48 2 98 UDI 32 81 47 44 101 57 47 84 46 41 104 37 51 93 42 40 105 36 44 101 56 40 106 79 32 113 44
Page 6 3PECIAL REPORT 92-03 In addition, two tubes were plugged in S/G 'D' as a precautionary measure, using data from the fifth inservice inspection. These tubes were plugged since they were of a similar profile to a tube plugged in the 'C' S/G. The tubes are:
S/G 'If Ro_w Cohen ,
33 11 15 37 KEY - TAllI.ES 1 AND 2 avl,2,3,4,5,6 - Anti-Vibration Bars 0211,07H,07C, etc. - Tube Support Plate Numbers / Cold Leg (C), Hot Leg (H)
TSH - Tubesheet Hot
j SPECIAL REPORT
' TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'B' _ _ _
INDICATION % _ _
INCH (+) FROM - _
ROW COLUMN WALL THINNING LOCATION LOCATION-29 9 27' AV5- 0.00 30 9 35 AV2 0.00 30 9 24 AV5 0.00 32 11 28- /.V6 0.00-32 12 32 AV4 0.00 33 12 20 AV3 0.00 37 18 25 AV2 0.00 37 18 28 AV3 0.00 39 18 24 AV4 -0.00 t 36 19 24 AV3 0.00-37 19 25 AV4 0.00 41 19 44 AV4 0.00-37 20- 28 AV4 0.00-41 20 31 'AV3 0.00-41 20 49 AV4 0.00 41 20 34 AV5 0.00' 41 22 38 AV4 0.00 42 23 20 AV4 0.00-42 24 21 AV2. 0.00 42 24 28 AV4 0.00' 42 24- 23 AV5 '0.00
.45 24 28- AVS 0.00 5 27 20 06H 2.71 49 28 26 AV2 0.00 49 28 33 'AV3 0.00 ,
49 28 37 AV4 . 0.00 ^
49 28 41- AV5 0.00 49 28 24- AV6 0.00 50- 28 26- AV5- 0.00.-
I' 49 31 25 AV5 0.00 Page 1 of 5-
4 SPECIAL REPORT--
TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'B' - -
INDICATION % , INCH ( +) FROM ROW COLUMN - WALL THINNING LOCATION - - LOCATION 39 32 20 AV2- 0.00-1 51 ?? 44 AV2 -0.00 51 32 35 -AV3 0.00-
-51 32 39 AV4 0.00 51' 32 -30 AV5- 0.00 49 33 29 AV2 0.00 ;
49 33 31 AV3 0.00' 41 35- 21 AVS 0.00 32 40 27 OH1 27.79 26 4J 21 AV2 0.00 26 43 24 AV6 -0.00 35 43 31 AV3 0.00-35 45 26 AV3 0.00 35' 45 21 AV5 0.00 47- 45 29 AV3 0.00 47 45 20- AV4 0.00 50 47 23 -AV3 0.00 50 47 27 AV4 0.00
'50 47 30 AV5 0.00 50 47 -21 AV6 0.00-
'39 49 21 AV3- 0.00 .-
50 .53 28. AV4 0.00-26 54 30 -01H 28.25
--47 59 ~ 24- AV4_ : 0.00 -_
27 63 23- 06H- 0.00 40 64 3S AV3 0.00 -
40 64' 23 AV4 -0.00 26 -65 25 AV5 0.00-47 ~65 20 AV1- 'O 00 Page 2 of 5
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[ SPECIAL REPORT.
. TABLE 1-TUBE IMPERFECTIONS STEAM GENERATOR 'B' INDICATION % INCH ( & ) FROM ROW COLUMN Wall THINNING - LOCATION LOCATION-47 65 20- AV3. 0.001 47 65 37 AV4 0.00 -
40 66 27 AV4- 0.00 47 G6 '25 AV2 0.00.
54 67 25 ~AV4 0.00 41 68 33 AV2 0.00 42 68 24 AV3 0.00 42 68 25 AV4 'O.00 42 68 23 AV6 0.00 47 69 26 AV2 0.00-51 69 31 AV2- 0.00 51 69 34 AV3 . 0.00 51 69 39 AV4 0.00-51 69 38 AV5 -0.00 12 70 24 02C -27.00 23 70 39- AV6' O.00 55 71 24 AV4 ;0.00 55 71 24 -AV5 0,001 55 71 23 AV6- - 0.00:
50 72 22 -AV3 - 0.00 ~
~
47 73 39' .-AV3 0.00 47 73 48 AV4 0.00 51 73 30- AV3= -
= 0.00 -
- 51. '73 48: AV4 - 0.00:
51 73 32 AV5 0,00-51 73- 24 AV6 10.00-41' 74 '35 AV4 0.00 L 41 74- 37- AV5- 50.00 -
37 76 -32. AV4 -0.00 37 76- 23_ AV5 0.00 _
32 81- 30 -AV1 'O 00.
Page 3 of 5
l SPECIAL REPORT '
- TABLE 1 TUBE IMPERFECTIONS STEAM GENERATOR 'B':
INDICATION % INCHl + ) FROM. '
ROW COLUMN WALL THINNING- LOCATION LOCATION :
l 32 81 27 AV2: -0.00 32 81 27 AV3 0.00 32 81 32 AV4- 0.00-32 81 47 -AV5' O.00 26 83 24 AV5 0.00 ~
29 -84 25 04H' 29.00-47 84 43 AV2 0.00 47 84 46 AV3- 0.00 47' 84 37 AV4 0.00 -'
47 84 22 AV5 0.00' 43 85 21 AV3- 0,00 46 86 24 AV3 0.00 50 86 34 AV4 0.00 50 86 36 AV5 0.00 46 88 20 -AV2 0.00- .
'40 0.00-89 35 AV3 40 89 28 AV4 0.00 42 90 25 AV4. 0.00 --
46 '91 22 AV2- -O 00 46 91 24 AV4- 0.00 50 91 27 AV1 0.00 50 91 21 AV3 . 0.00.
50 91' 32 AV4 0.00' 51' 93 22' AV3 0.00-51 93 39 AV4 0.00 51 93 42 AVS 0.00 51 93 29 .AV6 0.00-
'42 ' 98' 27 AV3 O.00.
42 98 27 AV5 0.00 -
44 98 28 AV5 0.00 48 98 21 AV4 0.00 ,
Page 4 of 5 -
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SPECIAL REPORT ,
. TABLE 1 TUBE IMPERFECTIONS - STEAM GENERATOR 'B' INDICATION % INCH (+) FROM ROW - COLUMN WALL THINNING LOCATION LOCATION 40 100 22 AV3 0.00 41 100 22 AV5 0.00 44 101 39 AV2 0.00 44 - 101 33 AV4 0.00 44 101 56 AV5 0.00 44 101 25 AV6 0.00 34 110 25 AV3 0.00-32 112 22 s V5 - 0.00 30 113 21 AV5 0.00 32 113 25 AV2 0.00 32 113 41 AVS 0.00 Page 5 of 5
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1 SPECIAL REPORT TABLE 2 TUBE IMTERFECTIONS - STEAM GENERATOR 'C' INDICATION % INCH (+) FROM ROW COLUMN - WALL THINNING LOCATION ' LOCATION -
28 8 31 AV1- 0.00 3 29 9 20 AV5 0.00 32 10 38 AV2 0.00 32 10 32 AV5 ' O.00 34 15 20 AV2 0.00 37 18 25 AV3 0.00 37 19 20 AV3 0.00 41 19 39 AV2 0.00 41 19 31 AV3 0.00 41 19 25 AV4- 0.00 40 20 22 AV4 0.00 ~ ,
44 22 51 AV4 0.00 44 22 48 AVS 0.00 43 23 44 AV5- 0.00-44 23 22 AV4 0.00 44 23 33 -AVS 0.00 45 24 29 AV5 0.00 50 28 24 AV5 0.00 50 28 22 AV6 0.00 45 34 22' -AV3 0.00 45 34 53 AV4 0.00 46 35 22 AV4 0.00 40 37 27 AV3 0.00 r .40 37 25 AV4 0.00 46 37 27 AV4 -O.00 L 27 39 25 'AV5 0.00 l
50 45 21 AV2 0.00 l 50 45 22 AV3 0.00 t-l' L
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- SPECIAL REPORT 4- TABLE 2 TUBE IMPERFECTIONS STEAM GENERATOR 'C' INDICATION % INCHl+) FROM:
ROW- COLUMN - WALL THINNING- . LOCATION . - LOCATION 50 45- 30- AV4 0.00 --
49 48 25 AV3 0.00 16 50 28 04C: 23.30 .
12 56 41 TSH -0.86 46 56 24 AV4 0.00 51 57 22 07H- 0.57 47 58 21 AV4- 0[00
-18 63 21 AV5 0.00 54 63 36 AV3 -0.00
-0.00 54 63 34 AV4 54 63 30 AV6- 0.00
-41 64 51' AV2 0.00-41 64 20- AV3.- 0.00 41 64 20 AV5 0.00 38 71 39' '03C 29.01 l 44 71 32 AV4 0.00 ~
44 71 34 AV5 0.00-7 77 '21. .TSH 25.30 41 81 -23 AV3 0.00 53 90 31 AV5 0.00 47 91 31 AV4 0.00'
- 47. 24- AV5 10.00--
49 :93 24 'AV5 0.00
_43 94 24 AV4 0.00
_ - -49 95 26 AV4 0.00 Page 2 of 3 w %-- g y v , + -
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. SPECIAL REPORT . ,
TABLE 2.
. TUBE IMPERFECTIONS - STEAM GENERATOR .'C'-
INDICATION % INCH ( +1 FROM ROW COLUMN -- WALL THINNING- _ LOCATION LOCATION _ j 40 100' 22 -AV5 -0.00-44 101 39 AV3 0.00 = {
44 101 31 AV4 0.00 44 101 57 AV5 l 0.00 -
45 101 32 AV4 0.00 -- y 40 103 28 AV5 0.00: -j
=41 104 25 AV3 0.00 41 104 37 AV4 0.00 j 41 104 27 AV6 0.00 s
39 105 24 AV4- 0.00- 4 40 105 -36 AV4 0.00-41 105- 28 =AV4 0.00 41 105 33 AV5 0.00 41- 105 AV6 0.00
=
21 40 106 26 AV3' .0.00 ,
40 106 79 AV4' O.00 40 106 20 AVS 0,00 t 40 106 45 AV6 0.00 17 109 28 TSH 16.00-32 109 29 AV5 0.00
- 30. 114 '32. AV2- - . 0.00 --
30' 114 34 AVS 0.00'
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