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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210H6381999-07-30030 July 1999 Forwards SE Accepting Relief Request for Approval for Use of Alternate Exam Requirement for Plant Inservice Insp Program A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 ML20210B4021999-07-19019 July 1999 Ack Receipt of Facility Emergency Plan Implementing Procedure EIP-ZZ-00101, Classification of Emergencies, Rev 23,issued on 990513,under Provisions of 10CFR50,App E, Section V ML20210B4401999-07-19019 July 1999 Ack Receipt of Revs to Facility Radiological Emergency Response Plan,Chapters 8.0 & 4.0,issued Respectively on 990512-14,under Provisions of 10CFR50,App E,Section V ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209E5591999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.TAC MA0531 Closed ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20196J9501999-07-0202 July 1999 Ack Receipt of Plant Ep,Rev 22,received on 981207 & Submitted Under Provision of 10CFR50,App E,Section V.Changes Does Not Decrease Effectiveness of EP & Continues to Meet Stds of 10CFR50.47(b).NRC Approval Not Required ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 ML20196H2521999-06-25025 June 1999 Forwards Insp Rept 50-483/99-05 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20196F8181999-06-24024 June 1999 Forwards RAI Re 990111 Request for Relief from Certain ASME Code ISI Requirements for Containment Liners.Response Requested within 30 Days from Date of Agreement ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve IR 05000483/19990041999-06-18018 June 1999 Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1 ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H0971999-06-14014 June 1999 Discusses Une 990407 Request That Proprietary Document Entitled, Thermal Stability Assessment - Electrosleeved Tubes, Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20207H3751999-06-14014 June 1999 Discusses 990407 Une Request That Proprietary Version of Document Entitled, Evaluation of Severe Accident Simulation, Dtd April 1999,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20207G3201999-06-0707 June 1999 Ack Receipt of Change Notice 98-008 Dtd 980918,which Transmitted Changes to Callaway Plant Ep,Rev 21,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required.No Violations Identified ML20207G3151999-06-0707 June 1999 Ack Receipt of Callaway Plant EP Implementing Procedure EIP-ZZ-001001M,Classification of Emergencies,Rev 22,issued on 981222 Under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS 1999-09-22
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS ML20196L2911999-05-19019 May 1999 Forwards Responses to NRC 990315 RAI Concerning GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves A36791, Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl1999-05-17017 May 1999 Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl ULNRC-04034, Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions1999-05-17017 May 1999 Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions 05000483/LER-1998-003, Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept1999-05-12012 May 1999 Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept ML20206Q9551999-05-12012 May 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-04.Corrective Actions:Une Commits to Make Available for NRC Review,Action Plan Outlining Scope & Completion Dates of Project ULNRC-04027, Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 9905281999-05-0404 May 1999 Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 990528 ML20206E3211999-04-28028 April 1999 Forwards Special Rept 98-03 Re Inservice Insp of CP Sgs,Per Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage.Rept Is Being Resubmitted Due to Typos in Original Rept ML20206E5781999-04-23023 April 1999 Informs That R Schukai Is No Longer Employed with Amerenue & Info Sent Is No Longer Required.Name Should Be Removed from Mailing Lists.Mailing Label Used by Company Which May Assist in Matter,Submitted ULNRC-04018, Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date1999-04-21021 April 1999 Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date ML20205Q7751999-04-16016 April 1999 Forwards Special Rept 98-03 Concerning ISI of Callaway SGs Performed in Apr 1998 During Callaway Plants Ninth Ro. Rept Documents Final SG Insp Results ULNRC-04015, Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.211999-04-15015 April 1999 Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.21 ULNRC-04005, Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.7901999-04-0707 April 1999 Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.790 ULNRC-04004, Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld1999-04-0707 April 1999 Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld ULNRC-04007, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date1999-04-0707 April 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date ULNRC-04000, Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w)1999-04-0101 April 1999 Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w) ULNRC-03998, Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.751999-03-30030 March 1999 Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.75 ML20205G2211999-03-25025 March 1999 Submits Rev 28A to Callaway Plant Physical Security Plan, Incorporating Addendum Re Security Sys Replacement Transition Plan,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20205R5251999-03-25025 March 1999 Forwards Special Rept 98-03 Re Results of Tenth SG Tube Inservice Insp,Per Requirements of Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage ULNRC-03988, Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 101999-03-19019 March 1999 Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 10 ULNRC-03991, Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette1999-03-19019 March 1999 Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette ML20204F7211999-03-17017 March 1999 Forwards Amended Fitness for Duty Program Performance Data for Six Month Period Beginning Jul-Dec 1998 ML20204E1331999-03-17017 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-02 on 990208-12.Corrective Actions:Will Revise Security Plan to Increase Min Staffing by Three Armed Security Force Response Personnel Per Shift ML20207C3631999-03-12012 March 1999 Forwards Exam Matl & Associated QA Checklist for Written Exam to Support Plant RO Retake Exam Scheduled for 990423. Exam Matls Requested to Be Withheld from Public Disclosure Until After Exam Completion 05000483/LER-1998-001, Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability1999-03-10010 March 1999 Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability ULNRC-03979, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date1999-03-0909 March 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date ULNRC-03975, Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl1999-03-0505 March 1999 Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl ULNRC-03971, Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded1999-02-26026 February 1999 Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded ML20207A4311999-02-17017 February 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for Period of 980701-981231 1999-09-15
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Union Elzctric one Ameren Plaza 1901 Chouteau Avenue I PO liox 66149 l March 19,1999 st. louk, Mo 63166-6149 314GH3272 U. S. Nuclear Regulatory Commission ATTN: Document ControlDesk Mail Station PI-137 Washington, D.C. 20555-0001 Gentlemen: ULNRC-03988 DOCKET NUMBER 50-483 CALLAWAY PLANT UNION ELECTRIC COMPANY REQUEST FOR ALTERNATIVE EXAMINATION REQUIREMENTS FOR g
N'
_TIIE CALLAWAY PLANT INSERVICE INSPECTION PROGRAM PLAN
References:
- 1) ULNRC-3703 dated December 19,1997 N f#$[$# 2) NRC letter dated March 24,1998 UE This letter transmits a request for approval of Alternative Examination ISI-12A per 10CFR50.55a(a)(3)(i) and (ii) for the 1989 Edition of ASME Section XI, IWA-5242(a) for Class 1 bolted connections inside the bioshield for Callaway l Refueling Outage 10. ISI-12A requests a one-time extension ofISI-12, which was approved for Callaway Refueling Outage 9 (See Reference 1 and 2).
This submittal explains the hardship due to unnecessary man-rem exposure and the unusual difficulty associated with removing insulation from Class I components inside the bioshield on systems borated for the purpose of controlling reactivity. The scope of this request is limited to components inside the bioshield for a single refueling outage. The proposed altematives to the code requirements provide an acceptable level ofquality and safety.
AmerenUE has been aggressively working with the ASME Section XI Subcommittee since December 1996 for the approval of a Code Case that would provide a similar alternative (ASME Section XI ISI #97-43). It was expected at the time of submittal ofISI-12 (ULNRC-3703) that the Code Case would be finalized in 1998, however the committee process has taken longer than expected. We expect the
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Code Case to pass in 1999, but not in time for use dming our 10* Refueling outage in October 1999.
Refuel 10 is scheduled to begin October 1,1999. Approval of this Alternative Exam is requested by September 15,1999. Ifyou have any questions concerning this information, please contact us.
Sincerely,
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9903300011 990319 PDR ADOCK 05000403 #d M&M G PDR -
Alan C. Passwater Manager, Corporate Nuclear Services i DES /pir
Attachment:
Alternative Examination ISI-12A a subsidiary of Amaren Corporation
l STATE OF MISSOURI ) ;
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CITY OF ST. LOUIS ) ;
i Alan C. Passwater, of lawful age, being first duly sworn upon oath says that he is Manager, Corporate Nuclear Services for Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By -
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Alan C. Passwater Manager, Corporate Nuclear Services 4
SUBSCRIBED and sworn to before me this ~ day of d '27 # M , 1999.
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PATRICIA L REYNOLDS ll0TARY PUBUC--6 TATE OF A8880UN ST. Louts COUNTY hlY004StSSION EXPlRES DEC.22,2000
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J cc: 'M. H. Fletcher
'Piofessional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855-2432 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 Steedman, MO 65077 Mr. Mel Gray (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 l
Manager, Electric Department ,
Missouri Public Service Commission .
P.O. Box 360 l Jefferson City, MO 65102 i
l i
i
ALTERNATIVE EXAMINATION ISI-12A (Page1of3) 1 COMPONENT FUNCTION Code Class: 1
Reference:
_ IWA-5242(a) ,
Exammation Category: B-P Item Numbers: All item Numbers Listed Under Exammation Categories B-P
Description:
. Alternate Rules for inadema Removal During IWA-5000 Pressure Tests at ;
Bolted Connecuens in Systems Borated for the Purpose of Controlling i Reactivity Ca==panant Numbers. Bolted Connections Listedin Table 1 CODE REOUIREMENTS ASME Secuon XI,1989 Edition, Paragraph IWA-5242(a) states, "For systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for sisual l examination VT-2."
i BASIS FOR PROPOSED ALTERNATIVE Authorization is requested for a proposed alternative from the reqmrement to remove insulation for visual VT-2 examination of bolted connections during a system pressure test on systems borated for the purpose ;
of controlling reactivity. This request is for an extension of the previously approved request ISI-12 for !
Callaway Refuel 10 only. 'this request is for a one-time exemption from the code requirements ofIWA-
$242(a) for Callaway Refuel 10 on Class 1 bolted connections inside the bioshield. l AmerenUE believes that removal ofinsulation at bolted connections during Refuel 10 on components msule the bioshield for the sole purpose of visual examination is impractical and will result in hardship and unumm1 ddficulty for the reasons listed below per 10CFR50.55a(aX3Xi):
- 1) The visual VT-2 examination of the Reactor Coolant System (RCS) is performed following the majority of outage maintenance activities andjust prior to reactor criticality. The RCS is at a normal operating temperature and pressure (557*F and 2235 psig) during the pressure test as required by IWA-5000.
Performance of a visual VT-2 examination, re-installation ofinsulation, and disassembly of scaffolding under these conditions is a personnel safety hazard. Performance oithe examinations at cold shutdown
' is the only relief realized by the use of Code Case N533.
- 2) All Class 1 bolted connections listed in Table I were inspected without insuiation in accordance with Code Case N533 during Refuel 8. None of the bolted connections exhibited any esidence of degradstion due to boric acid corrosion. Where boric acid residue was discovered ami bolting removed, no corrosion or gross degradation due to intergranular stress corrosion cracking (IGSCC) was evident on the botting material. Exposure for all examinations perforir_ed in accordance with Code Case N533 from Callaway Refuel 8 totaled 9.2 Person-Rem, wit h no evidence of degradation discovered. 'the projected dose for the nine components listed in Table I for Refuel 10 is expected to exceed 5.8 hrson-Rem. This is considered an excessive amount of dose relative to the anticipated inspection results.
- 3) Differential thermal expansion occurs when insulation is removed from a bolted connection tiet creates a greater chance for leakage. When insulation is remowd, the flanges expand at a rate greater than the
o ALTERNATIVE EXAMINATION ISI-12A (Page 2 of 3) bolts causing stress on the connection. Once the bolts expand, the stress has caused the equivalent of untorquing the connection. The less tightened connection then has a higher probability ofleaking.
- 4) Code Class I systems borated for the purpose of controlling reactivity are extensive and consist of large systems covering many areas inside the containment bioshield on multiple elevations.
Scaffolding will be required to access many of the bolted connections. In addition, many of the bolted connections are lacatM in medium to high radiation areas. Insulation removal combined with scaffolding requirements will increase outage costs. Refuel 8 craA support of these incpections incurred $43,000 in additional costs. These costs were incurred despite the limited relief prmided by Code Case N533. If the exam were to be performed dunng the normal VT-2 between Modes 3 and 2 ascending, critical path time will be extended by several burs to accommodate the insulation installation and scaffold removal inside the bioshield wall and throughout containment aAer the examination is complete. Critical path cost is currently estimated at $207,000 per day.
- 5) VT-2 exams on the listed components were performed with the inanimaion installed in accordance with Alternative Examination ISI 12 during Callaway Refuel 9. The inspections identified no leakmg connectsons at any of the listed components.
AmerenUE believes that the established Callaway piograms described below in addition to the alternative examination proposed below, pro ide an acceptable level of safety and quality for bolted connections in ,
systems borated for the purpose of controlling reactivity per 10CFR50.55a(a)(3)(ii). l 1
- 1) In response to NRC Generic Letu:r 88-05, AmerenUE established a program to inspect all boric acid i leaks discovered in the contamment building and to evaluate the impact of those leaks on carbon steel or low alloy steel components. All evidence of leaks, including boric acid crystals or residue, is kW and evaluated regard! css of whether the leak was discovered at power or during an outage.
Issues such as the following are considered in the inspection and enluation: 1) evidence of corrosion or metal degradation,2) effect the leak may have on the pressure boundary,3) possibility of boric acid traveling along the inside ofinsulation on piping, and 4) possibility of dripping or spraying on other c-:-4-:+ents. Based on this evaluation, appropriate corrective actions are initiated to prevent reoccurrence of the leak and to repair, if necessary, any degraded materials or components.
- 2) In addition to the nondestructive examinations required by ASME Section XI, AmerenUE has committed to the bolting examination requirements of NRC Bulletin 82 02. In accordance with this Bulletin, at least two nondestructive examination techniques (e.g., ultrasonic, liquid penetant, magnetic particle, or visual VT-1) are performed on bolted connections of the following components:
Steam Generator primary manways, Pressurizer pnmary manway, Pressunzer safety valves, and a total of 22 Reactor Coolant System isolation valves that are greater than 6" NPS. As a minunum, two ;
nondestructive examination techniques are used whenewr the bolted connection of one of the subject components is disasserabled for maintenance or other inspection. 'Ihese additional examinations ensure that degradation mechanisms such as stress corrosion crackmg or corrosion do not go undetected in bolted connections critical to reactor safety. j
- 3) All bolted connections on Callaway's Class 1 borated systems inside the bioshield consist of SA-453 Grade 660 for studs and SA-194 Grade 6 or SA-453 Grade 660 for nuts. The stainless steels were i designed to be corrosion resistant in corrosive applications. 'Ihis is substantiated for the 410 stainless 1 steels (SA-194) by documents such as EPRI Report NP-5769 which attests to the resistance of stainless steels to boric acid corrosion. EPRI Report "1R-104748 further confirms in section 7.2.1 that the 410 stainicas steels are superior to the low alloy and carbon steel bolting materials. 410 stainless steel is an acceptable nut material as the nuts only experience a compressive stress. Tensile stresses are required for initiation of stress corrosion cracking. Therefore, only studs comprised of 410 stainless steel are potentially susceptible to stress corrosion crackmg. EPRI Report TR-104748 also identifies the A 286 (SA-453) as a superior fastening material. The superalloy was designed for resisthity to acid mrrosion environments due to its high nickel and chrome content and the inclusion of molybdenum specif.cally to inhibit inorganic acids such as boric acid. 'Ihese materials have been further evaluated by rsterial selection expert C.P. Dillon who was subcontracted by Nickel Laboratories. His evaluation concludes "the development of intermediate concentrations of boric acid solution in the flange area (due to minor leaks and evaporation of the water) would not attack the bolting significantly
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ALTERNATIVE EXAMINATION ISI-12A (Page 3 Of 3) and would be a marked improvement over low-alloy steel assemblies." To ensure that degradation mechanisms in these metals are mitigated, AmerenUE mainmins a program at the Callaway Plant that controls matenals (insulation, thread lubricant, boron, etc.) that may come in contact with safety related components, including bolting. 'Ihis program ensures that impurities are not present in concentrations that would promote development of Stress corrosion cruciang in stainless steel bolted connections. 'Ihe only carbon steel bolted connections at the Callaway Plant on systems borated for the purpose of controlling reactivity inside the bioshield are Steam Generator manways, Reactor Coolant Pump bolting and Pressurizer manways. 'lhese areas will be iaW for with the insulation r6 moved in accordance with Code Case N533.
- 4) Dunns Refuel 8 Callaway verified the integrity of all Class I bolted connections durmg cold shutdown with the insulation removed and during the normal VT-2 with insulation installed in accordance with Code Case N533 and no evidence of degradation was discovered aAer 12 years of service. Based on ine meternal properties of these bolted connections, degradation is not anticipated.
Use of the proposed akernative exammation is requested for one time use at Callaway Refuel 10. 'Ihis Alternative is not a request for use of Code Case N533 as its use has already been approved for Callaway by the NRC.
PROPOSED ALTERNATIVE EXAMINATION-Bolted connections fabricated of materials resistant to boric acid corrosion in systems borated for the purpose of controlling reactivity shall receive a sisual VT-2 exammation during the system pressure tests of IWB-5000 and IWC-5000 with the insulation installed. If evidence ofleakage is detected, either by discovery of active leakage or evidence of boric acid crystals, the insulation shall be removed and the bolt d connection shall be re-examined and, if necessary, evaluated in accordance with the corrective measures of Subarticle IWA 5250.
Carbon steel bolted connections within the Inservice Inspection bourderies will receive an inspection for j boric acid residue with the insulation removed. In addition, a VT-2 inspection will be performed in !
accordance with ASME Section XI reqmrements with the insulation installed at normal operating pressure
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Ifinsulation is removed for planned maintenance, repair, or other inspection at a bolted connection in a system borated for the purpose of controlling reactisity, a visual exanunation shall be performed on the bolted connection prior to disassembly and, if evidence of leakage is discovered, evaluated in accordance with the corrective measures of Subarticle IWA-5250.
Table 1 Claes 1 Boted Connections that 4.te insulated on systems borated for the purpose of controlkng readivity Component Stre Component Type Doomtption Stud Matertel Nut Meterial 888005 3" Gote Velvr RCS LOOP 3 XOVER LEG TO CVCS LTDN SA-453 Gr Soo SA 194 Gr 6 1 888048A 10" Check Velve RCS LOOF 1 COLD LEG SI ACC CHECK SA453 Gr 600 SA-453 Gr 600 i 8809408 10' Check Velve RCS LOOP 2 COLD LEG St ACC CHECK SA-453 Gr 600 SA-453 Gr 600 888048C 10" Check Velve RCS LOOP 3 COLD LEG St ACC CHECK SA-453 Gr 600 SA-453 Gr 600 88804'o 10" Check Velve RCS LOOP 4 COLD LEG St ACC CHECK SA-453 Gr 600 SA-453 Gr 600 BB6340A 10" Check Velve RCS LOOP 1 HOT LEG S1 PMPS CHECK SA-453 Gr 600 SA-194 Gr 6 l B889408 10" Check Velve RCS LOOP 2 HOT LEG Si PMP.S CHECK SA-453 Gr 600 SA-453 Gr 600 BnN 10" Check Velve RCS LOOP 3 HOT LEG St PMPS CHECK SA-453 Gr 600 SA-453 Gr 600 i 888040D 10" Check Velve RCS LOOP 4 HOT LEG St PMPS CHECK SA-453 Gr 600 SA-453 Gr 600