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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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UxI:n iI:ctric
- l9lsonc20 rattawar Dant nihon, MO G5351 February 10,1998 d.
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U. S. Nuclear Regulatory Commission Attn: Document ControlDesk Mail Stop Pl.137 Washington, DC 20555 0001 ULNRC.3725 Gentlemen:
SUPPLEMENTAL REPLY TO UNRESOLVED ITEM INSPECTION REPORT NO. 50-483/97015 UNION ELECTRIC CO CALLAWAY PLANT Ref: ULNRC-3668 This response supplements information provided in our letter dated November 14, 1997. During a meeting held with the NRC staff on January 29,1998, it was ;
determined that additionalinformetion would be useful to facilitate resolution of the I Unresolved item discussed in Inspection Reports 50-483/97015 and $0-483/97017. As ;
such, the following attachments provide specific examples to illustrate the potential i impact of the NRC stafi's proposed interpretation regarding technical soecification required shutdown surveillance testing.
Attachment 1 provides examples of components that are actuated oy the emergency diesel load sequencer and can be tested while the plant is at power with no adverse ;
consequences, Based on the NRC stafi's proposed interpretation, examples are '
provided where:
A plant shotdown would be required to establish equipment OPERABILITY ,!
or
establish equipment OPERABILIT.Y or, #
enforcement discretion would be required to permit continued operation and ilOU1 defer testing to some future plant shutdown.
9902170123 900210 illilillllllilH Il***
}
. ULNRC-3725 February 10,1998 Page 2 Attachment 2 provides specific examples of work performed at Callaway where, utilizing the NRC steff's proposed interpretation, enforcement discretion would be required to prevent an unnecessary plant shutdown.
These lists are not all encompassing, but are intended to illustrate adva se effects of the NRC staft's proposed interpretation regarding the Unresolved Item identified at Callaway Plant. If our understanding of the staf!'s proposed interpretation is incorrect, we would be glad to have further discussions with you at your convenience.
None of the material in the response is consia'ered proprietary by Union Electric.
l If you have any questions regarding this response or if additional information is required, please let me krmw, Sincerely, J. V. ux Manager, Quality Assurance JVIJMAR/tmw
Attachment:
- 1) Component Shed From Emergency Busses
- 2) Specific Examples of Maintenance Activities Performed at Callaway Plant
4 0 ULNRC-3725 February 10,1994 Page 3 #.
cc: Mr. Ellis W. Merschoff Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 8064 Mr. William H. Bateman Director, Project Directorate 1%2 Office of Nuclear Reactor Regulation
, U. S. Nuclear Regulatory Commission Mall Stop 13E16 Washington, DC 20555 2738 Mr. Thomas P. Gwynn Director Division of Reactor Projects U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 8064 Mr. Barry C. Westreich (2 copies)
Acting Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 13E16 Washington, DC 20555-2738 Senior Resident Inspector Callaway Resident Oftice
.U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman,MO 65077 Manager, Electric Department
. Missouri Public Service Commission PO Box 360 Jefferson City, MO 65102
9
^
ULNRC-3725 February 10,1998 Page 4 Mr. Thomas A. Baxter Shaw, Pittman, Potts, & Trowbridge 2300 N. Street N.W.
Washington, DC 20037 Manager, Plant Support Wolf Creek Nuclear Operating Corporation PO Box 411 Burlington, KS 6683" l
_ _ _ _ _ = -
V
e Attachment I to ULNRC-3725 February 10,1998 Page1 Conanaments Shed Frna Emermency Busses The following is a list of congonents which are shed from the emergency tus following a LOCA. The shed of these components can be individually tested on-line with no adverse impact to plant operation:
- ofIndividual Componeet Classification Components ESW Pump Room Unit Heater _ 12 l
UHS Coolira Tower Surnip Heaters 4 Lishtina Transformer 13 l Plant Computer Inverter 2 CRDM Coolina Fans 2 Boric Acid Transfer Pumps 2
_ UHS Coolina Tower Equip. Rm. Sump Pumps 2 The following is apart /allist of components which are shed from the emergency bus following a Loss of Offsite Power. The shed of these components car. also be tested a on-line with no adverse impact to plant operation:
- ofIndividual Compcsent Classification Components Auxiliary Feedwater Pumps 2 Essential Service Water Pumps 2 Component Coolina Water Pumps - ,
4 RHR Pumps 2 Safety Irdection Pumps 2 ,
Contr,itunent Spray Pumps 2 Fuel Pool Coolina Pumps 2 NB01 Ahernate Feeder Breaker 1 NB02 Alternate Feeder Breaker 1 These lists contain only so#re of the components actuated by the sequencers. Additional listings could be provided for equipment shed or started from other actuations, inhibit contacts, etc. T hese individual actuations can be easily curveilled at power with no .
perturbation on plant operation. Based on the proposed NRC staffinterpretation, an enforcement relief or a plant shutdown would be required to take credit for any test used -
to satirfy the sequencer surveillance requirement. This linplies that any of these
. i I
i Attachment I to ULNRC-3725 February 10,1998 '
Page2.
l components (or others in these categories) that are repaired on line could not be returned to service due to not being able to take credit for performarW of the surveillance.
~
The examples below describe situations where, utilizing the NRC staff's proposed !"
interpretation, an enforcement relief or a plant shutdown would be required to take credit for a reted and declare the equipment OPERABLE. The alternative would be to hold the equipment out of service until the next plant shutdown. r EXAMPLES: [
Lighting Transformer ;
This circuit consists of a breaker connecting the lighting transformer to the 480 V bus. The shunt trip for this breaker is actuated firom a sequencer cabinet relay on a ;
LOCA sequence. If the relay or the breaker failed, or other maintene.nce was !
performed which could effect the shed function, post maintenance testing would ;
require verification of the shed capability from the sequencer relay. i CRDM Cooling Fans ,
The two CRDM cooling fans fed firom safety related power have a trip coil i connected to their breaker in the same manner as the lighting transfonner example discussed above. Failure or maintenance on these would also require shed-verification as discussed above. i Auxiliary Foodwater Pumps . ;
~
l- The Auxiliary Foodwater pumps (and the other listed pumps) have a relay contact L-in the trip circuit that closes on a Loss of Offsite Power to shed the pump ifit is j running. This case is similar to those discussed above, where failure or .
maintenance which could affect the shed function would regul e verification of shed capability prior to returning the pump to OPERABLE status.
These pumps also sequence onto the safety bus following a Loss of Offsite Power .
(shutdown sequence) or Safety Injection (LOCA 'equence). Fanure, or maintenance which would afroct the ability of the pump to start from the sequencer -
relay, would require verifying this actuation. This is easily accomplished without ,
running the complete sequence by energizing the individual ielay. Other testing within the sequencer cabinet provides the verification of relay actuation on the appropriate step. ;
- y re- -ir-FT-=+ m- -- -+ 9 "t++ y1--w-evi-r-=r'm~-g +- w sy=- T w--- w wr,**+ vive-=vte-we-= -- es---e c =w- m u y-v*--me-'r --'W-t-=-8' ' - + - ' ' ' 9 N F-+------=M'****t**W" - * ' '
Attachment 2 to ULNRC 3725 Februuy 10,1998 Pate 1 Snecine Enamnies of Malatemance Acirities Performed at Callaway Plant Component ClasslGcation Bre.ker ID WR'e rtquiring Enforcement Discretion l
ESW Pump Room Unit Hester _
EGD01A NG05EEFl C575048 970923 INSTALL NEW CKT BREAKER (EGD01 A)
W161605 931123 VERIFY ATI &
LOAD SHED OF BRKR.
EGD01B NG06EEF1 C575058 971013 INSTALL NEW CIRCUIT BREAKER (EGD01B)
EGD01C NG05EFF2 C575052 970824 INSTALL ,
NEW CIRCUIT BREAKER (EGD01C)
EGDOID NG06EFFI C575061 971014 INSTALL NEW CIRCUIT BREAKER GGD01D) .
EGD01E NG05EFF1 C575051 %1113- INSTALL NEW CIRCUIT BREAKER (EGD01E) .
EGD01F NG06EEF3 C575060 961220 INSTALL NEW i; CIRCUIT BREAKER (EGD01F)
EGD01G NG05EEF4 C575050 960924 INSTALL NEW ,
CIRCUIT BREAKER (EGD0lG)
WI83879 % 1110 T/S REWORY BKR FAILING TO OPEN EGD0lH NG06EFF3 C575063 971015 INSTALL NEW CIRCUIT BREAKER (EGD01H)
EGD02A NG07FDF5 C575073 970924 INSTALL NEW CIRCUIT BREAKER (EGD02A)
EGD02B NG08FDF5 C575084 971017 INSTALL NEW CIRCUIT BREAKER (EGD028)
EGD02C NG07FDF3 C57f370 970923 INSTALL NEW CIRCUIT BREAKER (EGD02C)
EGD02D NG08FDF3 C575082 971016 INSTALL NEW CIRCUIT BREAKER (EGD02D)
UHS Cooling Tower Sump Heaters SEF02A N007FDF6 C575074 970731 INSTALL NEW CIRCUIT BREAKER (SEF02A)
SEF02B NG08FDF6 C575085 970912 INSTALL NEW CIRCUIT BREAKER (SEF02B)
. Attachment 2 to ULNRC-3725 February 10,1998 Page 2 l Composent ClasslAcation Breaker ID Wk's requiring Enforcement Discretion SEF02C NG07FDFl C573068 970612 INSTALL NEW CIRCUIT BREAKER (SEF02C)
SEF02D NG08FDF1 C575080 970911 INSTALL NEW
' CIRCUIT BREAKER (SEF02D)
Lighting Transformer XQB50 NGOSEEF3 C575049 970925 INSTALL NEW CIRCUIT BREAKER (XQB50)
XQB51 NG06EFF2 C575062 M1210 INSTALL NEW CIRCUIT BREAKER XQB52 NG07FDF2 C575069 970611 INSTALL NEW CIRCUIT BREAKER (QB52)
XQB53 NG08FDF2 C575081 970716 INSTALL NEW CIRCUIT BREAKER (QB53)
XQB60 NG02AAF2 C574904 970228 INSTALL NEW CIRCUIT BREAKER XQE61 NG01AHFS C574883 970314 INSTALL NEW CIRCUIT BREAKER (QB61)
XQB65 NG01AHF2 C574881 970313 INSTALL NEW CIRCUIT BREAKER (QB65)
XQB70 NG02AAFI C574903 970227 INSTALL NEW CIRCUIT BREAKER XQB75 NG01AllF1 C574880 970312 INSTALL NEW CIRCUIT BREAKER (QB75)
XQB80 NG01BJF1 C574900 970313 INSTALLNhW CIRCUIT _ BREAKER (QB80)
'. .qB 85 NG02BJF1 C574960 960812 INSTALL NEW CIRCUIT BREAKER (QB85)
XQB90 NG01BJF2 C574901 970314 INSTALL NEW CIRCUIT BREAKER (QB90)
XQB95 NG02BJF2 C574961 960726 INSTALL NEW CIRCUIT BREAKER Plant Computer Inverter PQO2 NG02AAF3 C574905 970205 INSTALL NEW CIRCUIT BREAKER (PQO2)
PQO3 NG01AIIF3 C574823 951122 INSTALL CIRCUIT BREAKER
. _. - - - - . - - = - -. .. -- . . . _ - . - -
Attachment 2 to ULNRC-3725 February 10,1998 Page 3 Component Classification Breaker ID WR's requirina Enforcement Discretion i2 CRDM Coolina Fans CGN01B NG02BJF5 R471525A 900727 VERIFY LOAD SHED NG02BJF5 l R479611A 950210 VERIFY LOAD SIIED NG02BJF5 C546356 950210 REPLACE CIRCUIT BREAKER (DCGN01B)
CGN01D NG01BJF5 C530861 931207 REPLACE i CIRCUIT BREAKER (CGN01D) _
Beric Acid Transfer Pumps PBG02A NG01AHF4 C574882 961003 INSTALL NEW CIRCUIT BREAKER O'BG02A)
PBG02B NG02AAF4 C574906 960719 INSTALL NEW CIRCUIT BREAKER UHS Coollag Tower Equip. R n. Sump Pumps , .
PEF 02A NG07FDF4 C575071 980121 INSTALL NEW BREAKER (PEF 01 A) _
PEF 02B NG08FDF4 C575083 (TSD)990219 INSTALL NEW BREAKER (PEF 02B)
ESW Pump House Holst IIKF041 NG06EEF2 C575059 960509 INSTALL NEW CIRCUIT BREAKER OIKF41)
PASS Transforener XSJ01 NG01BKF4 C574902 970314 INSTALL NEW CIRCUIT BREAKER
@J146)
Inimediate Borate Valve BGHV8104 NG04CPF2 C574811 960125 INSTALL NEW CIRCUIT BREAiGR
, . Attachment 2 to ULNRC-3725 l FebruaN 10,1998 !
Page 4 Comiponent Classincation Breaker ID WR's requiring Enforcennent Discretion Battery Charmers PK21 NG0102 P499382 930413 CLEANANSPECT LC BREAKER (PK21)
P531932 941013 CLEANHNSPECT LC BREAKER (PK21)
P558651 971218 CLEANANSPECT LC BREAKER (PK21)
PJ31 NG0202 P496027 921109 CLEANANSPECT LC BREAKER (PJ31)
P524704 940526 CLEANANSPECT LC BREAKER (PJ31)
P552955 970918 CLEANANSPECT LC BREAKER (PJ31) .
PK23 NG0110 P496931 930423 CLEAN AND INSPECT LC (PK23)
P532517 941017 CLEANANSPECT ,
LC BKR(PK23)
P559372 971031 CLEANANSPECT LC BKR(PK23)
PK24 NG0410 P523655 940623 CLEAN / INSPECT LC BREAKER (PK24)
P554058 971211 >
CLEAN / INSPECT LC BREAKER (PK24)
PK22 NG0409 P523657 940630 CLEANANSPECT LC BREAKER (PK22)
P554335 971010 CLEAN / INSPECT LC BREAKER (PK22) '