|
---|
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
[Table view] |
Text
.
. Cattaway Piet
, Post Othce Box 620
, futton. Missoon 65251 Union Euicnue
$E April 1,1996 Document Control Desk Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission l
Mail Stop PI-137 Washington,DC 20555 ULNRC-3350 j Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 95-02 (SOS 95-1138)
RESULTS OF TIIE EIGIITII STEAM GENERATOR TUBE IN-SERVICE INSPECTION REF: ULNRC-3211, dated 5/11/95 The enclosed Special Report is submitted pursuant to the requirements of Callaway Technical Specification 4.4.5.5.b concerning the In-service Eddy Current Inspection of Callaway's Steam Generators (S/G) performed in May 1995, during Callaway Plant's seventh refueling outage. This report documents the final inspection results.
- T R. D. Affolter Manager, Callaway Plant WAY 4 % .f % 7 % d RDA/WAW/TEH/HDB/MAH/tdf Enclosure l l
9604080153 960401 0R0073 gj l PDR ADOCK 05000483 O . (8 I PDR , ,
I l
i I
ULNRC-3350 April'1,1996 Page 2 cc: Mr. L. J. Callan Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Resident Inspector Ms. Kristine M. Thomas Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 13-E-21 Washington,DC 20555 Manager. 'dlectric Department Missoun Public Service Commission PO Box 36C Jefferson City, MO 65102 Mr. Thomas A. Baxter Shaw, Pittman, Potts, & Trowbridge 2300 N. Street N.W.
Washington, DC 20037 l
l l
, ULNRC-3350
. April 1,1996 Page 3 SPECIAL REPORT 95-02 RESULTS OF EIGHTH STEAM GENERATOR TUBE IN-SERVICE INSPECTION 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 in-service 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 inspected,
- 2) Location and percent of wall-thickness penetration for each indication of an imperfection, and
- 3) Identification of tubes plugged."
INSPECTION
SUMMARY
In May 1995, with the plant in Mode 6 for the seventh refueling outage, the eighth plant Steam Generator (S/G) Eddy Current In-service Inspection was performed. Forty (40) tubes were plugged as a result of the inspection. The inspection was performed by Westinghouse Electric Corporation, and the final results are detailed in this Special Report. The results are summarized below and are numbered to correspond with the information requested by T/S 4.4.5.5.b:
y
. ULNRC-3350
. April 1,1996 Page 4 (1) Number / Extent ofInspected Tubes i
100% of the non-plugged tubes in S/Gs 'B' and 'C' were inspected using the !
bobbin coil probe No bobbin coil testing was performed in S/Gs 'A' and
'D'.
S/G 'B' S/G 'C' ,
Tubes evaluated with 5609 5596 standard bobbin coil Tubes plugged previously 17 ._1Q Total Tubes 5626 5626 !
i The RPC inspection scope for S/G's included: 100% (17,507 tubes) of the l Tubesheet Ilot Leg (TSII) for the mill annealed tubing (> Row 10), 8.3% '
(405 tubes) TSH for thermally treated tubing and a small sample (108 inspections) ofIlot Leg support plates. The tubesheet inspections consisted of +2/-2 inches from the top of tubesheet. All tube support plate inspections were +2/-2 inches except the seventh tube support plate inspections were
+1/-2 inches.
l i
. ' ULNRC-3350 1
- April'1,1996 )
Page 5 l
(2) Location / Percent of Wall-Thickness Penetration for Each Indication of l Imperfection
]
1 See Tables 1,2, and 3 l l
TABLEI S/G 'B' ;
TABLE 2 S/G 'C' '
TABLE 3 S/G's 'A' & 'D'
)
(Percent of wall-thickness penetrations are shown for indications of ,
> 20%.) ]
KE./ - TABLES 1. 2. and 3 i
i AV 1,2,3,4,5,6 - Anti-Vibration Bars 0~ 1I,07H,07C, etc. - Tube Support Plate Numbers / Cold Leg (C), llot Leg (II)
TSH - Tubesheet Hot Leg TSC - Tubesheet Cold Leg ,
DNT - Dent 1 OBS - Obstructed SAI - Single Axial Indication MAI-Multiple AxialIndication SCI - Single Circumferential Indication MCI - Multiple Circumferential Indication SVI- Single Volumetric Indication I i
l
. ULNRC-3350 April 1,1996 Page 6 l
l (3) Identification of Tubes Plugged from the Eighth In-service Inspection.
S/G 'A' S/G 'B' S/G 'C S/G 'D' Tubes Plugged (Refuel 7) 11 5 20 4 j Tubes Previously Plugged 16 24 33 48 !
Total Tubes Plugged 47 29 53 52 l
S/G A S/G B S/G C S/G D l ROW COLUMN RO_W COLUMN RO_W COLUMN ROW COLUMN J X 21 47 49 33 1 1 1 1 11 50 47 65 37 18 33 56 ,
12 51 50 91 14 41 X 16 61 X 18 54 1 120 36 43 17 108 X 13 55 1 121 12 55 32 58 14 56 12 61 46 56 X 12 69 13 57 !
X 14 69 14 57 X 19 80 14 58 34 100 X 15 58 13 59
)
X 15 60 13 61 X 14 61 I 54 63 43 80 24 88 14 100 45 101 NOTE: X's indicate tubes with stabilizers installed.
l l
1
'. ULNRC-3350 April' I,1996 Page 7 TABLE 1 1
TU8E IMPERFECTIONS - STEAM GENERATOR 'B' l
' INDICATION % INCH (+) FROM !
ROW COLUMN WALL THINNING LOCATION LOCATION 28 8 25 AV6 0.00 29 9 32 AV5 0.00 31 11 20 AV3 0.00 )
32 11 28 AV6 0.00 l
[ '
32 12 26 AV4 0.00 f
! 37 18 30 AV2 0.00 37 18 34 AV3 0.00 39 18 29 AV4 0.00 33 19 25 AV3 0.00 36 19 26 AV3 0.00 37 19 27 AV4 0.00 37 20 38 AV4 0.00 42 23 27 AV3 0.00
! 42 23 23 AV4 0.00
! l 42 24 37 AV4 0.00 l 42 24 27 AV5 0.00 I 45 24 29 AV5 0.00 42 25 23 AV4 0.00 ;
50 28 27 AV5 0.00 50 28 24 AV6 0.00 45 29 25 AV4 0.00 48 29 21 AV6 0.00 41 30 29 AV2 0.00 l 42 30 23 AV2 0.00
- 42 30 27 AV3 0.00 l - . .-. ,
. s
'. ULNRC-3350 -
April ~ 1,1996 l' 4
Page 8 INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 49 31 28 AV2 0.00 49 31 25 AV4 0.00 49 31 30 AV5 0.00 49 31 22 AV6 0.00 39 32 22 AV2 0.00 39 32 21 AV5 0.00 49 33 39 AV3 0.00 49' 33 41 AV2 0.00 j 40 35 23 AV5 0.00 41 35 22 AV4 0.00 41 35 24 AV5 0.00 j l
26 43 21 AV2 0.00 26 43 25 AV6 0.00 35 43 30 AV3 0.00 1 26 45 22 AV6 0.00 35 45 31 AV3 0.00 35 45 25 AV5 0.00 1 47 45 32 AV3 0.00 f 47 45 24 AV4 0.00 )
i 50 47 30 AV3 0.00 I 50 47 28 AV4 0.00 l
50 47 30 AV5 0.00 50 53 28 AV4 0.00 26 54 29 01H 27.84 47 59 25 AV2 0.00 47 59 26 AV4 0.00 26 61 22 AV2 0.00 26 61 21 AV5 0.00 34 61 25 03C -0.03 27 63 27 06H 0.11 i 40 64 36 AV3 0.00
~
. i
, l ULNRC-3350 ;
l Aprif 1,1996 l i Page 9 INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION ,
40 64 22 AV4 0.00 i
26 65 30 AV5 0.00 47 65 24 AV1 0.00 .
47 65 23 AV3 0.00 47 65 40 AV4 0.00 46 66 27 AV4 0.00 47 66 27 AV2 0.00 54 67 34 AV2 0.00 54 67 29 AV4 0.00 (
s 42 68 32 AV2 I 0.00 ,
42 68 24 AV3 0.00 l 42 68 25 AV4 0.00 42 68 22 AV5 0.00 42 68 25 AV6 0.00 47 69 25 AV2 0.00 !
12 70 26 02C 28.02 55 71 28 AV4 0.00 55 71 26 AV5 0.00 55 71 22 AV6 -0.03 47 72 22 AV2 0.00 50 72 24 AV1 0.00 50 72 25 AV3 0.15 1 i
41 73 20 AV1 0.00 41 74 22 AV1 0.31 41 74 37 AV4 0.26 41 74 35 AV5 0.13 35 75 22 AV3 0.00 l 37 76 20 AV3 0.00 37 76 31 AV4 0.00 37 76 20 AV5 0.00
ULNRC-3350 Aprif 1,1996 Page 10 i INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 26 83 24 AV5 0.00 29 84 24 04H 29.74 46 84 20 AV1 0.00 46 84 22 AV2 0.00 46 84 21 AV3 0.00 !
i 43 85 23 AV1 0.00 43 85 29 AV3 0.00 46 86 26 AV3 0.00 46- 86 20 AV4 0.00 50 86 22 AV2 0.00 50 86 23 AV3 0.00 50 86 38 AV4 0.00 l 50 86 37 AV5 0.00 46 88 24 AV2 -0.03 l
46 88 22 AV3 0.00 '
40 89 38 AV3 0 00 40 89 35 AV5 0.00 42 90 33 AV4 0.00 46 91 26 AV1 -0.08 46 91 30 AV2 0.03 46 91 32 AV4 -0.01 50 91 30 AV1 -0.08 50 91 21 AV2 0.00 50 91 39 AV3 0.00 50 91 50 AV4 0.00 I
42 98 27 AV2 0.00 42 98 34 AV3 0.00 42 98 21 AV4 0.00 42 98 32 AV5 0.00 44 98 25 AV4 0.00 44 98 28 AV5 0.00 44 98 24 AV6 0.00 46 98 25 AV3 0.00 46 98 29 AV4 0.03 46 98 21 AV5 0.00
.. . . . - - -- . .-. . . - . . -. ~ . . .. . - . - . . . - . . - .- . . . . . ..
ULNRC-3350 I April 1,1996 i Page11 :
INDICATION % INCH (+) FROM -
ROW COLUMN WALL THINNING LOCATION LOCATION l
48 98 32 AV4 0.00 48 98 32 AV4 0.00 >
42 99 26 AV5 0.00 41 100 27 AV5 0.00 42 103 29 AV5 0.00 32 107 22 AV2 0.00 i 34 110 30 AV3 0.00 32 112 26 AV5 0.00 f 30 113 27 AV5 0.00 i 30 114 23 AV1 0.00 1 120 38 TSC 4.02
]
1 121 45 TSC 3.66 l
l 1
l t
1 t
f i
1
-r -w w
.- . i ULNRC-3350 -
- April 1,1996 Page 12 l
i TABLE 2 TUBE IMPERFECTIONS - STEAM GENERATOR 'C INDICATION % INCH (+) FROM ROW
[
COLUMN WALL THINNING LOCATION LOCATION 1 1 OBS 01C 0.00 24 6 25 AV1 0.00 27 8 24 AV1 0.00 .
28 8 33 AV1 0.00 !
29 9 22 AV2 0.00 29 9 23 AV5 0.00 30 12 25 AV5 0.00 32 13 26 AV3 0.00 34 13 22 AV5 0.00 1
35 14 20 AV1 0.00 34 15 35 AV2 0.00 35 15 20 AV3 0.00 37 15 23 AV5 0.00 35 16 28 AV1 0.00 35 16 22 AV2 0.00 35 16 20 AV3 0.00 35 16 22 AV4 0.00 36 16 23 AV4 0.00 36 18 28 AV4 0.00 37 18 41 AV3 0.00 40 18 25 AV2 0.00 40 18 23 AV4 0.00 37 19 27 AV3 0.00 40 20 21 AV3 0.00 40 20 28 AV4 0.00 50 28 27 AV5 0.00 50 28 27 AV6 0.00
'. ULNRC-3350 April 1,1996 Page 13 l INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 39 29 25 AV2 0.00 39 29 24 AV4 0.00 46 29 20 AV2- 0.00 !
46 29 27 AV4 0.00 42 33 29 AV2 0.00 42 33 22 AV5 0.00 46 35 20 AV2 0.00 46 35 25 AV4 0.00 ,
t 40 37 27 AV3 0.00 !
40 37 23 AV4 0.00 46 37 22 AV2 0.00
{
46 37 31 AV4 0.00 1 27 39 30 AV5 0.00 14 41 MAI TSH 0.09 36 43 sal TSH -0.16 40 43 23 AV2 0.00 35 44 22 AV3 0.00 50 45 25 AV2 0.00 50 45 28 AV3 0.00 50 45 33 AV4 0.00 24 46 22 AV6 0.00 i
33 48 29 06C 38.03 49 48 33 AV3 0.00 49 48 21 AV4 0.00 16 50 26 04C 23.46 36 52 25 AV2 0.00 36 54 22 AV3 0.00 12 55 MIA TSH 0.42
l l
'. ULNRC-3350 )
April 1,1996 l Page 14 ,
j i
INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 14 56 SVI TSH 0.24 37 56 22 AV3 0.00 '
46 56 25 AV3 0.00 !
46 56 43 AV4 0.00 13 57 SV1 TSH 0.20 14 57 SV1 TSH -0.08 50 57 24 05H 25.44 14 58 SVI TSH 0.01 15 58 SCI TSH -0.09 13 59 SV1 TSH 0.49 15 60 SCI TSH -0.26 13 61 SAI TSH 0.28 14 61 sal TSH 0.05 14 61 SCI TSH -0.08 58 61 24 02H 16.89 18 63 25 AV5 0.00 49 63 21 AV2 0.00 49 63 21 AV3 0.00 49 63 27 AV4 0.00 54 63 43 AV4 0.00 54 63 20 AV5 0.00 54 63 36 AV6 0.00 45 64 26 AVS 0.00 48 64 25 AV5 0.00 38 71 29 03C 29.49 44 71 23 AV2 0.00 44 71 30 AV4 0.00 44 71 31 AV5 0.00 44 71 23 AV6 0.00 36 77 27 03C 22.98 43 80 MAI TSH -0.19 41 81 22 AV3 0.00 l
4 ULNRC-3350 April 1,1996 Page 15
- INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 41 87 24 AV3 0.00 41 87 27 AV4 0.00 47 87 23 AV5 0.00 24 88 SAI TSH -0.16 41 r< 22 AV4 0.00 46 90 23 AV4 0.00 53 30 27 AV5 0.00 i
47 91 31 AV4 0.12 47 91 22 AV5 0.15 43 92 20 AV4 0.00 13 93 23 AV1 0.00 46 93 23 AV3 0.00 I 47 93 24 AV3 0.00 47 93 21 AV4 0.00 )
47 95 25 AV5 0.15 l 49 93 22 AV4 0.00 '
49 93 20 AV5 0.03 51 93 20 AV4 0.00 40 94 28 AV4 0.00 49 95 26 AV4 0.00 49 95 23 AV5 0.00 49 95 20 AV6 0.00 '
42 96 24 AV5 0.00 14 100 SAI TSH -0.01 40 100 29 AV5 0.00 44 100 29 AV5 0.00 45 101 44 AV4 0.00 45 101 26 AV5 0.00 27 102 31 AV6 0.00 40 103 23 AV2 0.00 40 103 27 AV5 0.00 l
ULNRC-3350
- Aprit 1,1996 Page 16 i INDICATION % INCH (+) FROM ROW COLUMN . WALL THINNING LOCATION LOCATION 39 105 25 AV4 0.00 ;
41 105 36 AV4 0.00 i 41 105 38 AV5 0.00
+
14 106 26 AV1 0.00 ,
32 109 28 AV5 0.00 32 110 21 AV6 -0.27
?
33 111 22 AV6 0.00 j i
31 113 21 AV5 -0.12 30 114 26 AV2 0.00 30 114 31 AV5 -0.27 9 118 22 06C 27A3 )
I l
h
- ..- .. _- - _ _ . _ - . . .=- - . -. . .- - .
- , ULNRC-3350 Aprij 1,1996
- Page 17 k
l TABLE 3 4
TUBE IMPERFECTIONS - STEAM GENERATOR 'A' INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 21 47 SCI TSH -1.05 11 50 sal TSH -0.16 i 12 51 sal TSH 0.10 18 54 sal TSH -0.05 18 54 MCI TSH -0.21 13 55 SCI TSH -0.18 32 58 MAI TSH -0.01 12 61 MAI TSH -0.08 12 69 SCl TSH -0.13 14 69 SCI TSH -0.22 19 80 SCI TSH -2.62 34 100 sal TSH 0.02 TUBE IMPERFECTIONS - STEAM GENERATOR 'D' INDICATION % INCH (+) FROM ROW COLUMN WALL THINNING LOCATION LOCATION 1 1 DNT TSC 17.25 33 56 SAI TSH -0.05 16 61 SCI TSH -0.06 17 108 SVI TSH -0.06
.)