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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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a Union Electric one Ameren Plaza 1901 Chouteau Avenue Po flox 66149 St. Louis, Mo 63166-6149 samt.sm s 8 July 10,1998 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop PI-137 Washington, DC 20555-0001 ULNRC-03863 MI6 g
fggg DOCKET NUMBER 50-483 UNION ELECTRIC CALLAWAY REFUEL 9 REOUEST FOR RELIEF FROM ASME CODE in accordance with 10CFR50.55a(g)(5)(iii), Callaway is requesting relief from the requirements of the 1989 Edition of ASME Section XI as detailed in attached Relief Requests ISI-13, ISI-14, ISI-15, ISI-16, ISI-17, and ISI-18.
These Relief Requests detail the examination limitations encountered during Callaway Refueling Outage 9.
Please contact us if you have any questions concerning this information.
/
Very truly yours, t' f
G~4 A. C. Passwater Manager - Corporate Nuclear Sersices JAM /DSH/RDM Attachment (12 pages)
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.. ouoa 9807210007 980710 PDR ADOCK 05000483-
% PDR 1 e subsidiary of Amoren Corporation
cc: M. H. Fletcher Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20055-2432 Regional Administrator U.S. Nuclear Regulatory Commission
- Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Stc, edman, MO 65077 Kristine M. Thomas (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E16 11555 Rockville Pike Rockville, MD 20852-2738 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 i
i 1
l 4
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l CALLAWAY ISI RELIEF REQUEST ISI-13 System: Reactor Coolant System (RCS) Pressurizer Surge Line Examination Category: B-J ltem Number: B9.11 Component
Description:
Pipe to Pressurizer Surge Line Nozzle Safe-End Weld. This weld is identified as 2-BB-01-F004.
Code Requirement: ASME Section XI,1989 Edition, Table IWB-2500-1, Examination Category B-J, Item No. B9.11 requires volumetric and surface examination of the weld. This is a high stress location, therefore inspection of this weld once per 10-year interval is required.
Areas for Relief: Weld 2-BB-01-F0')4 achieved a composite coverage of 82.47% of the weld volume when including the axial exam from the safe end side and the circumferential exam.
Basis for Relief: The limitation to the axial scan is due to four lugs welded to the pipe within the examination volume. The lugs were formerly used as anchors for a snubber that has since been removed from this line under modification package CMP 94-1019. Actual coverage achieved in each direction is listed below.
2-BB-01-F004 1 Axial Scan Coverage in two directions 64.95 % ,
Circumferential Coverage in two directions 100 % I The code required surface exams were also performed on these !
welds at this time and yielded no indications with 100% coverage.
In addition to the code required 45 scan, a 60 shear wave scan was l performed on both sides of the weld to compensate for the beam l redirection. The estimated coverage achieved is conservatively based on this nominal 60' angle. With beam redirection, the actual examination angle is estimated to be closer to 45 and thus yields a l greater weld volume examined than was recorded. Examination l l results can be found in Callaway file E170.0100 reports 6226-98-23 l and 6106-98-23.
1 I It is impractical to achieve any additional weld coverage at this time, therefore reliefis requested pursuant to 10CFR50.55a(gX5Xiii).
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Alternate Testing: None. The best possible examination was performed using a
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combination of 60' and 45' shear wave transducers. The extent of l, ,
this ultrasonic examination, the liquid penetrant surface examination, the Section XI VT-2 (visual) examination for leakage performed once every refueling outage, and the reactor coolant leakage detection system verify weld integrity.
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CALLAWAY ISI RELIEF REQUEST ISI-14 I
l System: Reactor Coolant System Cast Piping (BB)
Examination Category: B-F Item Number: B5.130 l Component
Description:
2-BB-01-F304 and 2-BB-01-F305 are Reactor Coolant System 'C' Loop piping to Steam Generator Nozzle Welds. 2-BB-01-F304 is the
, Steam Generator inlet nozzle to 50 elbow weld. 2-BB-01-F305 is the Steam Generator outlet nozzle to 40 elbow weld.
Code Requirement: ASME Section XI,1989 Edition. Table IWB-2500-1, Examination Category B-F, Item No. B5.130 requires volumetric and surface examination of all dissimilar metal welds once per 10 year interval.
The Reactor Coolant System Loop piping is cast stainless steel (SA-351 CF8A) while the steam generator nozzle is carbon steel. ASME Section XI requires 100% volumetric examination of the inner 1/3 thickness of weld metal plus the inner 1/3 of adjacent base metal for a distance of 1/4" beyond the edge of the weld crown, in addition, Article 111, Paragraph 111-4420 requires that the ultrasonic examination for reflectors parallel to the weld scam be performed using a sufficiently long examination beam path to provide coverage of the required examination volume in two beam path directions.
Areas for Relief: A composite coverage of 69.7% of the weld volume was achieved for weld 2-BB-01-F304 and 77% of the weld volume was achieved for weld 2-BB-01-F305 for both the axial and circumferential exams.
Basis for Relief: Scanning of the subject welds is limited on the elbow side by a steep outside diameter taper on the steam generator outlet and inlet nozzles. The elbow material is cast stainless steel (SA-351 CF8A).
Due to the high attenuative nature of this material, a refracted longitudinal sound wave is necessary to get a meaningful ultrasonic examination. A longitudinal sound wave cannot be extended to provide coverage in two beam path directions.
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Basis for Relief (cont): Achieved Coverage:
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2-BB-01-F304 Parallel Scan in Two Directions 71 %
Axial Scan in Two Directions 37.02 %
Axial Scan in One Direction 62.98 %
2-BB-01-F305 Parallel Scan in Two Directions 71.87 %
l Axial Scan in Two Directions 65.03 %
Axial Scan in One Direction 34.97 %
l These welds were approved for reliefin the first ten year interval l under Callaway ISI Relief Requests P-2 and P-3 submitted May 20, i 1994.
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l Based on the fact that no indications were detected, the weld integrity has been assured. Furthermore, a liquid penetrant surface examination was performed over the entire surface of the weld, l which yielded no relevant indications. It is impractical to achieve any additional weld coverage at this time, therefore reliefis request pursuant to 10CFR50.55a(gX5Xiii).
Alternate Testing: None. The maximum possible volume was examined as practical.
The extent of this uhrasonic examination, the liquid penetrant surface examination, the Section XI VT-2 (visual) examination for leakage
- l. performed once every refueling outage, and the reactor coolant l leakage detection system verify weld integrity.
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CALLAWAY ISI RELIEF REQUEST ISI-15 System: Reactor Coolant System Cast Piping (BB)
Examination Category: B-J Item Number: B9.11 Component
Description:
2-BB-01-F301 and 2-BB-01-F307 are Reactor Coolant System 'C' Loop piping to 'C' Reactor Coolant Pump Welds. 2-BB-01-F301 is the Reactor Coolant Pump inlet weld. 2-BB-01-F307 is the Reactor Coolant Pump outlet weld.
Code Requirement: ASME Section XI,1989 Edition, Table IWB-2500-1 Examination Category B-J, item No. B9.11 requires 100% volumetric examination of the inner 1/3 thickaess of weld metal plus the inner 1/3 of adjacent base metal for a distance of 1/4" beyond the edge of the weld crown.
In addition, Article Ill, Paragraph 111-4420 requires that the ultrasonic examination for reflectors parallel to the weld seam be performed using a sufficiently long examination beam path to provide coverage of the required examination volume in two beam path directions.
Areas for Relief: A composite coverage of 83% of the weld volume was achieved for weld 2-BB-01-F301 and 65% of the weld volume was achieved for weld 2-BB-01-F307 for both the axial and circumferential exams.
Basis for Relief: Scanning of the subject welds is limited due to the weld profile and the large search unit footprint. The 1" 1 Milz longitudinal transducer required to project the sound through the cast stainless steel (SA-351 CF8A) is limited by the pump to pipe configuration. Furthermore, due to the high attenuative nature of this material, a refracted longitudinal sound wave is necessary to get a meaningful ultrasonic examination. A longitudinal sound wave cannot be extended to provide coverage in two bearn path directions.
Achieved Coverage:
2-BB-01-F301 Parallel Scan in Two Directions 84.28 %
Axial Scan in Two Directions 63.72 %
Axial Scan in One Direction 36.28 %
2-BB-01 F307 Parallel Scan in Two Directions 82.76 %
Axial Scan in Two Directions 4.19 %
Axial Scan in One Direction 86.57 % ,
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. Basis for Relief (cont): Based on the fact that no indications were detected, the wc'd integrity has been assured. Furthermore, a liquid penetrant surface examination was performed over the entire surface of the weld, ;
which yielded no relevant indications. It is impractical to achieve )
any additional weld coverage at this time, therefore relief is requested pursuant to 10CFR50.55a(g)(5)(iii).
Alternate Testing: None. The maximum possible volume was examined as practical. l The extent of this ultrasonic examination, the liquid penetrant surface 1 examination, the Section XI VT-2 (visual) examination for leakage performed once every refueling outage, and the reactor coolant leakage detection system verify weld integrity.
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. CALLAWAY ISI RELIEF REQUEST ISI-16 System: Reactor Coolant System Cast Piping (BB)
Examination Category: B-J Item Number: B9.11 Component
Description:
2-BB-01-S302-3 is the Residual Heat Re noval suction-to-RCS loop I cold leg branch connection weld.
Code Requirement: ASME Section XI,1989 Edition, Table IWB-2500-1, Examination Category B-J, item No. B9.11 requires 100% volumetric examination of the inner 1/3 thickness of weld metal plus the inner 1/3 of adjacent base metal for a distance of 1/4" beyond the edge of the weld crown.
In addition, Article 111, Paragraph 111-4420 requires that the ultrasonic examination for reflectors parallel to the weld seam be performed using a sufficiently long examination beam path to provide coverage of the required examination volume in two beam path directions.
Areas for Relief: A composite coverage of 23.35% of the weld volume was achieved for weld 2-BB-01-S302-3 for both the axial and circumferential exams.
Basis for Relief: Weld 2-BB-01-S302-3 can be examined from the RCS pipe side only due to the nozzle-to-pipe branch configuration. The RCS piping material is SA-351 CF8A (cast stainless steel). Due to the highly attenuative nature of this material, a refracted longitudinal wave is necessary to get a meaningful ultrasonic exarnination. A longitudinal sound wave can not be extended to provide coverage in two beam path directions.
Achieved Coverage:
2-BB-01-S302-3 Axial Scan in One Direction 93.4 %
Additionally, a 35 refracted longitudinal scan was attempted to detect reflectors transverse to the weld. Even though the weld itself could not be examined from this direction, no indications were l detected.
l This weld was approved for reliefin the first ten year interval under Callaway ISI Relief Request S-1 submitted May 20,1994.
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i Basis for Relief (cont.): Based on the fact that no indications were detected, the weld integrity has been assured. Funhermore, a liquid penetrant surface j examination was performed over the entire surface of the weld, l which yielded no relevant indications. It is impractical to achieve !
tany additional weld coverage at this time, therefore reliefis requested )
pursuant to 10CFR50.55a(g)(5)(iii). 1 i
l Alternate Testing: None. The maximum possible volume was examined as practical. l The extent of this ultrasonic examination, the liquid penetrant surface examination, the Section XI VT-2 (visual) examination for leakage performed once every refueling outage, and the reactor coolant leakage detection system verify weld integrity.
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CALLAWAY ISI RELIEF REQUEST ISI-17 I
System: 'A' Steam Generator (BB)
Examination Category: B-B ltem Number: B2.40 Component
Description:
2-EBB 01 A-SEAM-1-W is the 'A' Steam Generator Bottom Head-to-Tubesheet weld.
Code Requirement: ASME Section XI,1989 Edition, Table IWB-2500-1, Examination Category B-B, item No. B2.40 requires 100% volumetric examination of the Steam Generator Tubesheet-to-Head Weld.
Areas for Relief: 100" of the 427.07" circumferential distance is obstructed by suppo-t lugs in four locations. The lugs are integral portions of the steam generator.
Basis for Relief: Scanning of the subject welds is limited due to four lugs that obstruct 100" of the 427.07" circumferential distance of the weld.
Achieved Coverage:
2-EBB 01 A-SEAM-1-W 0 Scan 76.6 %
45 AxialScan 76.6 %
60 Axial Scan 76.6 %
45 Circumferential Scan 76.6 %
60 Circumferential Scan 76.6 %
This weld was approved for reliefin the first ten year interval under Callaway ISI Relief Request H submitted April 11,1988.
Based on the fact that no indications were detected, the weld integrity has been assured. It is impractical to achieve any additional weld coverage at this time, therefore reliefis requested pursuant to 10CFR50.55a(g)(5)(iii).
Alternate Testing: None. The maximum possible volume was examined as practical.
The extent of this ultrasonic examination, the Section XI VT-2 (visual) examination for leakage performed once every refueling outage, and the reactor coolant leakage detection system verify weld integrity, h
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CALLAWAY ISI RELIEF REQUEST ISI-18 System: Reactor Coolant System Cast Piping (BB)
Examination Category: B-J Item Number: B9.11 l
Component
Description:
2-EP-02-F007 is a Loop 2 Accumulator Safety injection pipe to valve weld upstream of valve BB8948B (RCS Loop 2 Cold Leg Safety injection Accumulator Check Valve).
Code Requirement: ASME Section XI,1989 Edition, Table IWB-2500-1, Examination Category B-J, item No. 89.11 requires 100% volumetric examination of the inner 1/3 thickness of weld metal plus the inner 1/3 of adjacent base metal for a distance of 1/4" beyond the edge of the weld crown.
In addition, Article III, Paragraph 111-4420 requires that the ultrasonic examination for reflectors parallel to the weld seam be performed using a sufficiently long examination beam path to provide coverage of the required examination volume in two beam path directions.
Areas for Relief: A composite coverage of 59.8% of the weld volume was achieved for weld 2-EP-02-F007 for both the axial and circumferential exams and 70.42% coverage for the surface examination.
Basis for Relief: Scanning of the subject welds is limited due to a permanent energy absorption chamber that obstructs 10.5" of the 35.5" circumferential distance of the weld.
Achieved Coverage:
2-EP-02-F007 !
I Parallel Scan in Two Directions 70.5 %
Axial Scan in Two Directions 28% I Axial Scan in One Direction 42.5 %
This weld also required a surface examination of 100% of the circumference. 70.42% of the surface could be examined using dye penetrant method due to the obstruction of the permanent energy i absorption chamber.
This weld was approved for reliefin the first ten year interval under l
Callaway ISI Relief Request M submitted June 28,1991. l Basis for Relief (cont): Based on the fact that no indications were detected, the weld integrity l' has been assured. It is impractical to achieve any additional weld l coverage at this time, therefore reliefis requested pursuant to
- j. 10CFR50.55a(g)(5)(iii).
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, . Alternate Testing: None. The maximum possible volume was examined as practical.
The extent of this ultrasome exammation, the liquid penetrant surface
! examination, the Section XI VT-2 (visual) examination for leakage
( performed once every refueling outage, and the reactor coolant
! leakage detection system verify weld integrity.
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