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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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059G2971990-09-0404 September 1990 Notifies of Implementation of Procedure on 900831 to Correct wide-range Gas Monitor Display for Noble Gas Spectrum ML20059G4991990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-Jun 1990 & Rev 0 to APA-ZZ-01003, Odcm ML20059C3371990-08-23023 August 1990 Advises That Util Plans to Remove Some Thimble Plugging Devices from Plant During Upcoming Refueling Outage.No License Amend Required.Revs to Tech Spec Bases 3/4.2.2 & 3/4.2.3 That Reflect All Removal of Thimble Plugs Encl ML20058N2051990-08-0707 August 1990 Advises of Implementation of Amend 55,rev to Tech Spec 3/4.7.1.2 Re Auxiliary Feedwater Sys,Effective 900807 ML20081E1971990-07-27027 July 1990 Forwards Rev 6 to Indexing Instruction T210.0002/Q101, Qualification/Certification Documentation & Rev 6 to T210.002/R353, Required Reading/Personnel Form 2 ML20044B1821990-07-0909 July 1990 Forwards Westinghouse Revised Proprietary RCS Flow Measurement Uncertainty Calculation Supplementing Setpoint Studies Submitted in Attachment to Util 900412 Ltr.Encl Withheld ML20055E5261990-07-0505 July 1990 Forwards Revised marked-up Tech Spec Pages for 900306 Application for Amend to License to Place cycle-specific Core Operating Parameters in Core Operating Limits Rept ML20055E7861990-07-0505 July 1990 Forwards Callaway Plant 1990 Annual Exercise Scenario on 900530 ML20044A6601990-06-25025 June 1990 Forwards Requested Info Re Seismic Design of safety-related above-ground Vertical Liquid Storage Tanks,Per 900404 Ltr. All Stresses on Tank Roof Angle,Connecting Cylinder to Roof,Remain within Code Allowables Under Postulated Loads ML20043H8371990-06-21021 June 1990 Forwards Response to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issues at Facility ML20043H2721990-06-12012 June 1990 Forwards 10CFR50.59 Annual Rept Summaries of Written Safety Evaluations of Changes Approved & Implemented for Plant from 890330 to Present ML20043E2161990-06-0505 June 1990 Forwards Endorsements 42-48 for Nelia Policy NF-264 & Endorsements 28-34 for Maelu Policy MF-111 ML20043G9331990-06-0404 June 1990 Forwards Rev 13 to Operating QA Manual. ML20043D7101990-05-31031 May 1990 Forwards NPDES Renewal Application Submitted to State of Mo Dept of Natural Resources on 900518 ML20043B5841990-05-22022 May 1990 Responds to NRC 900423 Ltr Re Violations Noted in Insp Rept 50-483/90-04.Corrective Actions:Security Post Instructions Modified to Require Check of Security Container in QA Area ML20042F2831990-04-30030 April 1990 Forwards Rev 11 to Inservice Testing Program. ML20042F1161990-04-30030 April 1990 Provides Clarification to SALP 9 Rept 50-483/90-01 for Sept 1988 - Jan 1990.Licensee Voluntarily Retested Few Remaining Const Workers Originally Approved for Unescorted Access Using mini-IPAT ML20042F2901990-04-27027 April 1990 Forwards Util 900402 Ltr Documenting Agreement Between State of Mo Historic Preservation Officer & Util Re Cultural Resources ML20042D8491990-04-0202 April 1990 Forwards Listing of Present Level of Nuclear Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w) ML20012F1601990-03-29029 March 1990 Submits Supplemental Info Re Util Response to Station Blackout.Callaway Will Comply W/Numarc Station Blackout Initiative 5A Re Emergency Diesel Generator ML20012D1901990-03-19019 March 1990 Forwards Rev 15 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20012D7441990-03-16016 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. No Changes or Implementation Schedule Need Be Provided in Response to Generic Ltr 89-19 ML20012C6791990-03-0808 March 1990 Advises That Installation Date for Regulatory Effectiveness Review Concern 2.6.1 Revised to 900531.Deficiency Will Be Under Continuous Surveillance Until Correction Made ML20012C3111990-03-0606 March 1990 Forwards Addl Info Re Storage of Enriched Fuel in Spent Fuel Pool Area,Per NRC 900216 Request ML20012B3691990-02-28028 February 1990 Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums ML20012A4141990-02-23023 February 1990 Requests NRC Concurrence That Leak Chase Sys Is Integral Part of Containment Boundary & Does Not Need to Be Vented During Containment Integrated Leak Rate Test ML20006E1401990-02-12012 February 1990 Requests Clarification Re Positive Test Results for Controlled Substances,Specifically How Second Confirmed Positive Test Results Are Handled ML20011E7941990-02-0202 February 1990 Requests Emergency Relief from Tech Spec 3.1.3.1.b Due to Electrical Problem W/Rod Control Sys.Action Required to Prevent Plant Shutdown from 100% Power When Adverse Weather Conditions Exist in Svc Area ML20006D1061990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Dredge & Visual Shoreline Insps of Missouri River Near Plant Intake Indicated Presence of Small Numbers of Asiatic Clams ML20006C2311990-01-24024 January 1990 Forwards Callaway Plant Annual Exercise,891011, Emergency Exercise Scenario for 1989 Exercise ML20006B1371990-01-19019 January 1990 Forwards ECCS Evaluation Model Revs 10CFR50.46 Annual Rept. Util Will Provide Followup Rept Based on Results of Westinghouse Investigation to Be Completed in Second Quarter 1990 ML20005E8161990-01-0303 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of high-hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design ML20005E5141990-01-0202 January 1990 Certifies That fitness-for-duty Program That Meets Requirements of 10CFR26 Will Be Implemented on 900103 ML20005G3511989-12-28028 December 1989 Forwards Addl Info Supporting NRC Review of Proposed Revs to Tech Spec 3/4.1.3, Movable Control Assemblies. ML20005E5221989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. ML19353B0041989-12-0404 December 1989 Forwards Response to NRC 891016 Ltr Re Results of Regulatory Effectiveness Review on 890918-21.Encl Withheld (Ref 10CFR73.21) ML19332F1861989-11-30030 November 1989 Responds to Generic Ltr 89-15 Re Emergency Response Data Sys.Sys Will Be Implemented by Jul 1991,to Allow Addl Features to Be Developed for Plant Computer Sys & to Be Installed in Conjunction W/New Plant Computer Sys ML19332E9881989-11-30030 November 1989 Discusses Visual Insp of Hafnium Rod Cluster Control Assemblies During Refuel-2 in Fall 1987.Results Indicate Guide Card Fretting Wear Per NRC Info Notice 87-019.All Hafnium Rods Replaced W/Silver/Indium/Cadnium Assemblies ML19332D4441989-11-22022 November 1989 Responds to Generic Ltr 89-21,forwarding Table Providing Implementation Status of Each USI at Facility ML19327C0741989-11-0707 November 1989 Forwards Executed Amend 3 to Indemnity Agreement B-93, Reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements. ML19324C4291989-11-0707 November 1989 Responds to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded-Case Circuit Breakers. Bulletin Provisions as Clarified by Suppl Met & Documentation Associated W/Review Being Maintained at Facility ML19332B6121989-10-31031 October 1989 Provides Individual Plant Exam Method & Schedule.Completion of Level 1 PRA Scheduled for Jul 1991.Containment Performance Analysis Will Be Completed in Feb 1992.Results Will Be Provided in Sept 1992 ML20005D6181989-10-23023 October 1989 Submits Response to Suppl 1 to Generic Ltr 89-07 Re Safeguards Contingency Planning for Surface Vehicle Bombs. Short-term Actions Included to Protect Against Attempted Radiological Sabotage Involving Land Vehicle Bomb ML19325C9251989-10-0404 October 1989 Submits Corrected Wording to Encl to 890929 Ltr Supporting 10CFR50,App J Exemption to Allow Leak Chase Plugging During Integrated Leak Rate Test ML20248E4831989-09-29029 September 1989 Forwards Addl Info to Support 10CFR50,App J Exemption to Allow Leaving Leak Chases Plugged During Type a Integrated Leak Rate Test ML20248G0871989-09-28028 September 1989 Responds to NRC Bulletin 88-011 Re Pressurizer Surge Line Thermal Stratification.Action Items 1.a & B Completed & 1.d Actions Re Stress & Fatigue Ongoing Through Westinghouse Owners Group ML20248C1951989-09-21021 September 1989 Forwards Summary of Refueling Water Storage Tank Seismic Design Analysis Which Includes Effects of Tank Wall Flexibility.Issue Not Applicable to Condensate Storage Tank at Facility ML20246J7011989-08-30030 August 1989 Forwards Semiannual Radioactive Effluent Release Rept for First Half 1989.W/o Encl ML20246K9451989-08-29029 August 1989 Forwards Relief Request 0 to Plant Inservice Insp Program Plan,Per Observations During Refuel III ML20246E0521989-08-18018 August 1989 Forwards Info on Operator Licensing Exam Schedule,Per Generic Ltr 89-12 1990-09-04
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1901 Grctiot Street
. Post Office Box 149.
- St Louis, Missouri 63166;
'314-554-2650.
m September 29, 1989 . DonaldF. schneII IEtecraic; ' Senior Mce President uva.
13 r
U.S. Nuclear: Regulatory Commission Attn: Document Control Desk Mail Station.P1-137 Washington, D.C. 20555 ULNRC-2083 Gentlemen:
DOCKET NO. 50-483
.CALLAWAY PLANT INTERPRETATION TO LEAVE LEAK: CHASES PLUGGED DURING AN' INTEGRATED LEAK RATE TEST (ILRT) l
References:
- 1) ULNRC-1542, dated July- 10,'1987
- 2) T.W. Alexion letter to D.F. Schnell dated March 30, 1988
- 3) ULNRC-1945, dated March 20, 1989
- 4) T.W. Alexion letter'to D.F. Schnell dated July 31, 1989 References 1 and 3 requested the NRR staff to review the interpretation that the combined liner. butt weld along with'the associated pre-tested channel fillet welds I and leak test connections constitute the actual-containment boundary in post accident conditions. This interpretation would form the basis for not venting the containment liner weld channels during a containment integrated leak rate test (ILRT).
Reference 4 requested additional information to support a 10CFR50, App. J exemption to allow leaving the leak chases plugged during a Type A ILRT. This information is provided as an attachment to this letter If you have any questions, please contact me.
Very truly yours, I
8910050200 890929 FDR ADOCK 05000483 FDC Donald F. Schnell WEK/ dis j 01 Attachments l
b____ __ _ _ _ -- _ . _ _ _ .J
cc:. Gerald Charnoff, Esq. .
Shaw, Pittman, Potts & Trowbridge 2300'N. Street, N.W.
Washington, D.C. 20037 Dr.:J. O. Cermak CFA, Inc.
4 Professional Drive (Suite 110)
Gaithersburg, MD 20879 R. C. Knop Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077 Tom Alexion (2)
Office of Nuclear Reactor Regulation -
U.S. Nuclear Regulatory Commission
- 1. White' Flint, North, Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20852 Manager, Electric Department i Missouri Public Service Commission P.O. Box 360 '
Jefferson City, MO 65102 Ron Kucera Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 i
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bcc: D. Shafer/A160.761
/QA. Record (CA-758) W[A Nuclear Date E210.01 DFS/ Chrono D. F. Schnell J. E. Birk J. V. Laux W/A M. A. Stiller G. L. Randolph R. J. Irwin H. Wuertenbaecher W. R. Campbell W[A A. C. Passwater R. P. Wendling D. E. Shafer D. J. Walker O. Maynard (WCNOC)
N. P. Goel (Bechtel)
T. P. Sharkey NSRB C n1. (Sandra D ,vig ,,,,+/sAuston)lA W
W. L . Wa 1. L Wlx l
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n ATTACHMENT TO ULNRC-2083 ADDITIONAL INFORMATION REGARDING 10CFR50, APPENDIX J EXEMPTION REQUEST (Leak Chases)
NRC Question 1. Provide supporting analyses and stress calculations for at least one typical leak chase channel to show that the containment liner leak chase channel system meets the following requirements:
- a. The weld material strength and quality of weld attaching the channel to the liner plate should be equal to or better than that of the original liner joints and should meet the applicable requirements of either ASME Boiler and Pressure Vessel Code,Section III, Division 2, Subsections CC-2000, 3000 and 4000 (Code of Concrete Reactor Vessels and Containments, 1983),
or whatever comparable code that was used in design and construction.
Union The leak chase channel system was installed by Electric Chicago Bridge and Iron (CBI) as a non-safety Response related portion of the containment liner (also constructed by CBI). The fabrication and installa-tion of the leak chase system was performed under the same construction specification (C-151 and C-151A) as the fabrication and erection of the containment liner. The general notes for the construction of the liner restricts all field welds to E7018 or E6010 weld rod, with no exceptions mentioned for the installation of the leak chase channel. Therefore, it is reasonable to conclude that the same welding material used for the pressure boundary joints of the liner was used for the fabrication of the leak chase channel system.
l Since these channels were installed as non-safety l related, there are no weld control records that document the actual material used. However, where portions of the liner required repair (including the repair of channel), the repair plan specified the welding material to be used. This material was L consistent with the general notes regarding permissible weld rod types. The construction specifications for the containment liner also specified that proper controls would be taken for the storage of welding rods to ensure that there was no degradation of the material. Again, there are no exceptions stated allowing lesser controls for the welding material that was to be used on the leak chases. Consequently, it can be reasonably concluded that the material used to attach the weld channel to the liner was the same material used for i Page 1 of 6
the welding of the liner pressure boundary joints (thus material quality and strength would be the same as the liner pressure boundary joints).
In regard to meeting the requirements of CC-2000, and 4000;'the leak chase system was constructed to the 1974 code (Division 1, subsection NE).
Section NE-2000 is the sane for welding material requirements with the exception that further restrictions on the use of electroslag welding is introduced in the CC subsection. This type of welding was not used on Callaway's liner and is therefore not an issue. The requirements imposed by subsection CC-2000 for material certification and material testing of the weld rods cannot be verified since there is no safety related documentation for the non-safety related welds.
The weld design does meet the requirements of subsection CC-3000. The configuration is an H joint as defined by section CC-3840, and identical (in form and size) to the weld of figure CC-4542.2-6(a).
NRC Question 1.b. Since the leak chase channels now become part of the containment wall and are therefore considered a structural element, the strength of the channel box and its welds should be able to resist all load combinations involving the tested loads and the loads of a postulated accident, including seismic loads. The design of the leak chase channel should meet the applicable requirements of steel containments; i.e., either ASME Boiler and Pressure Vessel Code,Section III, Division 1, Subsections NE-2000, 3000 and 4000 for Class MC Components (1983) and American Institute of Steel ,
Construction Specification for the Design, Fabrication and Erection of Structural Steel for Buildings (1978), or whatever comparable code that was used in design and construction. 1
)
Union The response to this question (included as an Electric attachment to this letter) is in the form of an Response engineering analysis. This analysis concludes that the callaway containment liner leak chase system meets the design requirements of ASME Subsection III for all pressure boundary loading applications.
NRC Question 2. Complete documentation of installation records, including leak test procedures and results of the liner seam welds and the welds attaching the channel to the liner, should be available onsite. Please summarize and Page 2 of 6 w _ _ . _ _ _ _ _ - - - _ _ _ _ - - _ .
provide examples of available records. If-no records or only partial records are available,-
as suggested in your March 20, 1989 letter,-
provide whatever additional information/ assurance is available regarding procedures, materials, welds, inspection records, etc.
Union, The installation was not.for a safety related-Electric system, therefore complete documentation as Response required by ASME subsections CC-2000, 4000, and NE-2000, 4000 is not available. Design documents and other documentation exist which provide.added assurance of the quality and type of material used.
Each leak chase system was required to be 100%-
halogen leak tested. The leak chases were divided
'into test zones with each zone numbered and identified on design drawings (See C151-739, attached as an example). Each of these zones was pressurized to 9 psig with air and checked for leaks. After the air test, each zone was then pressurized to 5 psig with a halogen mixture (using Refrigerant 12) and checked for leakage with a halogen sniffer. The acceptance criteria was 0.0001 scc /sec. These leak tests provide assurance that the existing welds were performed with sufficient quality to ensure the capability of each zone and each weld to act as a pressure boundary.
The leak test procedure that was used and the documentation of 100% acceptability for all the leak chase zones are included as attachments to this letter.
Assurance as to the type of material used can be provided by the existing design specifications, drawings and some construction documentation.
Bechtel construction specifications C-151 and C-151A were the specifications used to build the containment liner. These documents specify the acceptable material for shapes, welding material, control of welding material and requirements for welder qualification (per ASME section IX). The only exception taken from these specifications was for the requirements of test channels to meet the vendor's QA program.
For example, a typical channel shape (part number 69-1) is required to be made of A36 (SA36) material per the construction specification C-151. The design drawings identify the type of channel to be used by specifying a design detail. C-151-740 lists part number 69-1 as a test channel for the Page 3 of 6
perimeter-of-the liner floor. Drawing C-151-744 _
then identifies part number 69-1 as an L-2X2X1/4 channel made of A36 material. This'is further shown on the Final Bill of Material to be made of
!V A36 material. And finally, a shipping order for.
g some of this. material is available specifying'that 9 A36 material be: ordered. The' pieces were individually fabricated 1and shipped-to the Callaway.
~
site. The. receiving report that accompanied some of the.69-1 pieces attests that.the material is A36 c
material.(from the' Material Heat _ Number' Sheet) and is certified by the shop ~ to be manufactured to; the required specifications on the Shop Release for Shipment check List.
Other channel p'i eces have traceability tio a CMTR, for example a CMTR'from Connors Steel Company
~
identifies piece number 69-12 as A36 material and provides the code required physical'and-chemical test information. However,-not all material received for.the channel system can be traced'to a heat number, and of that which'is, not all the CMTRs provide a complete analysis of the material (the CMTR for-piece 70-19, heat 16634, does not provide the' physical property information, only the chemical analysis). In addition, a=particular piece installed in.the field cannot necessarily be identified to a CMTR. For example, the Final Bill-of Material requires 1800 feet of piece 69-12, but only 1320 feet can be traced to heat number 21934 (per the Daily Fabrication Report).
Therefore, for any given piece number 69-12 installed in the field there is a 73% probability (1320/1800) that the piece is made from heat number 21934.
Although all the material used for the leak chase system cannot be traced to a CMTR, those pieces y that are traceable provide added assurance that the i material used was in fact the material specified by the design documents. Also,'the material required is readily available and can be assumed to be the material that was actually installed.
The only welding materials permitted for field fabrication of the liner are E7018 and E6010 electrodes (per the general notes for construction, drawing C151-703). No exceptions are stated for the leak chase system. This information is supported by documentation available for repairs or non-conformances involving the leak chases. A copy of a repair checklist specifying that E7018 weld l
Page 4 of 6 l
L material be used in welding the affected leak l
chases is attached. The size of the weld is specified on the design drawings showing the channel detail. No other documentation identifying weld type or size is available for the non-safety related welds.
A review of the receiving documentation associated with the construction of the containment indicates that all welding material received by CBI was traceable to a CMTR via a heat number. The CMTR provides the code required tensile and chemical property information. The requirement for impact testing per NE-2420 is not applicable due to a thickness of less than 5/8" for the channel and liner. An example of this documentation is attached. It can then be assumed that even though a weld cannot be traced to a particular heat or lot number, the material that was used to make the weld was probably initially received as code material.
Based upon the above examples, there is sufficient assurance that the material specified on the design drawings was procured as indicated on the Bill of Material, shipping orders, etc., and installed as shown on the design drawings. Due to the fact that.
only two types of welding materials were allowed, it is reasonable to assume that no other types were issued for use on the containment. When on site for construction, CBI controlled their own welding material which was not issued with material used by the principle construction contractor (Daniel International). Assuming that the only welding material received was identified in the CBI receiving documentation, it may be concluded that the only welding material available on site for the CBI welders was received as code material.
The sections of ASME CC and NE regarding materials and fabrication (2000 and 4000) cannot be supported with documentation for the non-safety related installation. However, the documentation that does exist provides assurance that the leak chase system was procured and fabricated in accordance with design. All the materials used are equivalents to the SA counter parts permitted by ASME subsection NE, and the welding materials were required to be ASME SFA materials per the design specification.
Page 5 of 6
NRC Question 3. The staff needs a commitment that you will perform a visual inspection of the accessible interior and exterior surfaces of the containment structure and components prior to any Type A test, including a visual inspection of accessible channel plugs, as required by 10 CFR Part 50, Appendix J.
Union The' procedure for_ conducting a Type A test will be Electric revised to require an inspection of all accessible l Response leak chase channel test connections prior to I
starting pressurization of the containment.
As stated in Reference 3, the majority of the leak chase channel is on the liner floor (the actual channel being under 18 inches of concrete). Only a small percentage of test channel is exposed to the containment atmosphere. The concrete that covers the liner floor will act to protect the leak chase channels underneath by preventing significant degradation of the channel to take place. The initial halogen leak tests performed would then be indicative of the pressure retaining capabilities of the leak chase channels. Of the welds on the liner shell, less than 2% are covered with leak chases. Of those chases on the shell that are inaccessible, most of the actual channel can be visually inspected to verify no degradation of the channel has taken place (again verifying the validity of the initial halogen leak test).
Most of the test connections that are inaccessible are on the liner floor behind the bioshield. Therefore, any activity to vent these test connections would result in a significant amount of personnel exposure. These test connections have also been covered with the finishing of the concrete or have had support plates installed over them. Some of these plates support primary piping (resulting in significant cost to remove the support and uncover the test connection). The test connections for the liner in the instrument tunnel would require an entry into a very high radiation zone. Other test connections are located under the pad for the reactor coolant pump, steam i generator, and cross over leg supports. To vent all these connections would involve significant cost in terms of manhours and materials as well as radiation exposure in high and very high l radiation areas.
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