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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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1901 Chouteau Avenue Post 0ffce Bra 149 St. tcuis. Missouri 63166 314-554-2650 Union nar 22, 1998 o sch c" ;
Etscruic ilu" ,',,*" '""""' i l
351 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station F1-137 Washington, D. C. 20555-0001 Gentlemen: l ULNRC-3377 l TAC NO. M90030 i I
l CALLAWAY PLANT i DOCKET NUMBER 50-485 l CALLAWAY PUMP AND VALVE INSERVICE TESTING PROGRAM !
References:
- 1) ULNRC-3043 dated July 14, 1994
- 2) NRC letter dated June 2, 1995 i
Reference 1 transmitted the Pump and Valve i
Inservice Testing Program (IST) for Callaway's second 10-year interval. This program was developed to i comply with the rules and regulations of 10CFR50.55a !
and Section XI of the ASME Boiler and Pressure Vessel l Code, 1989 Edition.
The NRC staff, with technical assistance from Brookhaven National Laboratory, reviewed the information concerning the second 10-year IST program. As stated in Reference 2, IST program relief requests were granted or approved for implementation provided action items as identified in Section 5.0 of the Technical Evaluation Report were addressed.
Enclosed please find (1) the resolution of each action item from TER Section 5.0 and (2)
Revision 15 of the IST program. Revision 15 incorporates changes made to the IST program as a result of NRC's comments and action items, and provides a general update to the program.
9605290054 960522
- 7 l PDR ADOCK 05000483 AIr l P PDR 01
. . l l
If you have any questions concerning this submittal,-please contact us.
l 1
Very truly yours, C
1 Donald F. Schnell i
WEK/CJD/
Attachments: 1) Action Item Resolution ,
- 2) IST Program Revision 15 l 9
STATE OF MISSOURI -)
) SS CITY OF ST. LOUIS )
Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Senior Vice President-Nuclear and an officer of 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.
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By Donald F. Schnell Senior Vice President Nuclear SUBSCR BED and sworn to before me this ddM day of , 1996.
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,hns4s-u S.l N J BARBA J.PFAk NOTARY PUBUC-STATE OF MISSOURI MY COMMIS$10N EXPIRES APRIL 22,1991 ST, LOUIS COUNTX
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l cc: T. A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.
Washington, D.C. 20037 l M. H. Fletcher l
Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855-2432 l L. Joe Callan l Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 l
l Senior Resident Inspector j Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road i Steedman, MO 65077
! Kristine M. Thomas (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E16
, 11555 Rockville Pike ,
! Rockville, MD 20852-2738 ;
t Manager, Electric Department i Missouri Public Service Commission P.O. Box 360 l
Jefferson City, MO 65102 l
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ULNRC-3377 Attachment 1 l
Page 1 of 8 Callaway Plant Pump and Valve Inservice Testing Program l Regponse to Recommended Action Items l Callaway's second 10-year interval Pump and Valve Inservice Testing Program (IST) complies with the rules and regulations of 10CFR50.55a and Section XI of the ASME Boiler and Pressure i
Vessel Code, 1989 Edition. The NRC staff, with technical assistance from Brookhaven National Laboratory, reviewed the second 10-year IST program. IST program relief requests were approved for implementation provided the action items in Section 5.0 of the Technical Evaluation Report (TER) were addressed. The resolution of each action item from TER Section 5.0 is discussed below.
NRC Item 5.1 In Pump Relief Request #P02 (TER 2.2.1), the licensee seeks relief from measuring vibration of the submerged fuel oil transfer pumps. It is recommended that interim relief be granted in accordance with 10CFR50.55a (f) (6) (i), for a period of one year, or until the next refueling outage, whichever is later, on a basis of the impracticality of immediately imposing Code requirements. The licensee should subsequently revise and submit this relief request to indicate an alternative course of action, such as the institution of a regular maintenance and spare parts program for these pumps which includes provisions to inspect the pump bearings and perform maintenance when the storage tanks are drained ano the bearings are accessible (e.g., once every ten years).
Union Electric Response - Item 5.1 Union Electric will disassemble the Fuel Oil Transfer Pumps to inspect the pump bearings and perform maintenance once every ten years. Relief Request #P02 was revised to reference this ten year bearing inspection and pump maintenance, and included in Revision 15 of the IST Program.
NRC Item 5.2 In Valve Relief Request #V07 (TER 3.2.1), the licensee proposed to use non-intrusive techniques to verify full open l capabilities of the ECCS injection line check valves. Relief l
is not required for this request however, the licensee should
! confirm that each branch line will have temporary instrumentation installed during the ECCS flow balance.
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ULNRC-3377 Attachment 1 Page 2 of 8 Union Electric Response - Item 5.2 Valve Relief Request #V07 has been removed from Revision 15 of the IST Program. Temporary instrumentation is installed on each branch line during the ECCS flow balance to measure individual branch line flow.
NRC Item 5.3 In Valve Relief Request Nos. EN-01, EN-02, EN-03, EP-02, and FC-01, it is recommended that the proposed alternative testing of check valve disassembly and inspection be authorized provided that all critaria of Position 2 is complied with, including adherence to the sample composition (e.g., all valves in the group must be the same size and see the same service conditions. Two of the valves identified in EN-02 are 10 inch pump discharge valves and the other two are 12 inch pump suction valves). The licensee should revise relief request EN-02 and ensure that the information to support compliance with Position 2 guidance is documented in the IST Program, as GL 04 requests.
Union Electric Response - Item 5.3 Relief Request #EN-02 was revised to remove the Containment Spray Pump discharge check valves, ENV0004 and ENV0010. These check valves were placed in a new relief request, #EN-05. This new grouping complies with Position 2 of Generic Letter 89-04.
Relief Requests Nos. EN-01, EN-02, EN-03, EN-05, EP-02, and FC-01 have been revised to include information to support compliance with the guidance given in Generic Letter 89-04, Position 2.
NRC Item 5.4 General comments on programmatic aspects of deferral testing are as follows:
(a) If a check valve has two safety positions, i.e., open and closed, the licensee must provide a discussion of the impracticality of verifying both positions quarterly, and at cold shutdowns, as the case may be. Although the forward flow exercise may be impractical quarterly or during cold shutdowns, the licensee may practically verify closure without testing the forward flow. For example, the impracticality of verifying closure quarterly or during cold shutdowns is not discussed in deferrals #EM-01 and #EM-05. Also, in some cases (e.g., #EM-03), the impracticality of part-stroke exercising is not explained.
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ULNRC-3377 Attachment 1 Page 3 of 8 (b) The valve table could be enhanced if the test frequencies for each test were added to the table, e.g., quarterly, cold shutdown, refueling outage, as the case may be. Also, for safety / relief valve testing either a 5 year or 10 year frequency should be noted.
(c) It is recommended that the licensee review all the systems in the program and verify that safety and relief valves that fall under OMa-1988, Part 10, 1 3.4, which references the safety and relief valve testing requirements of OM-1-1987, are in the program. There are numerous cases where relief valves installed in Code Class piping are omitted from the IST Program (e.g., KAV703, 704, 705, 706; EGV170, 159; ENV057; EP8855A-D, KJV716A, B, 717A, B; and the valves identified in TER Section 5.12).
Union Electric Response - Item 5.4 (a) Cold Shutdown and Refueling Justifications #AL-01, #BG-04,
- BG-05, #EM-01, and #EM-05 have been added to Revision 15 of the IST Program. In response to the comment regarding partial-stroke testing of EM8815 in Refueling Justification #EM-03, this Refueling Justification, as well as other Refueling or Cold Shutdown Justifications have been clarified by specifying full or partial stroke exercising as appropriate.
(b) The valve table has been enhanced by the addition of test frequencies for each test contained in the table.
(c) Per ASME/ ANSI OMa-1988, Part 10, Table 1 only active safety / relief valves need to be included in the IST Program.
All of the relief valves removed from Revision 14 of the IST Program are classified as passive valves.
NRC Item 5.5 Deferral requests #BB-08, #BB-11, and, #BB-07 and #BG-02 relate to the RCP pump seals. #BB-11 deals with the inlet component cooling water supply to the thermal cooling coils where the licensee concludes appropriately that these valves should be tested at refueling outages when the RCPs are stopped. #BB-08 deals with the outlet component cooling water supply to the thermal barrier cooling coils where the licensee concludes that j
testing at cold shutdowns is appropriate. #BB-07 deals directly with the seal water injection flow where the licensee concludes appropriately that these valves should be seat leak closure tested at refueling outages. #BG-02 deals directly with seal water return flow and the licensee concludes that testing at cold shutdowns is appropriate. The conditions for l
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ULNRC-3377 Attachment 1 Page 4 of 8 seal damage are nearly as great at cold shutdowns as they are during operation, and consequently the licensee is being asked to review deferral requests #BB-08 and #BG-02.
Union Electric Response - Item 5.5 Relief Requests #BB-08 and #BG-02 have been revised to specify testing during refueling outages as opposed to cold shutdown frequencies.
NRC Item 5.6 It is not evident why the IST valve program table identifies the need for leak testing Category C check valves EJ8969A, B.
This testing is not described in deferrals #EJ-02 and #EJ-09.
The licensee should review these deferrals, and revise if required.
Union Electric Response - Item 5.6 The test code "LT" has been removed from the " Tests Performed" column of the IST valve program table for EJ8969A, B in Revision 15 of the IST Program. These valves will not be leak tested.
NRC Item 5.7 In deferral request #KA-01 for the compressed air system's air-operated isolation valve, KAV0029, the valve is required to be fail-safe tested but the frequency is missing. The licensee should revise this deferral to include fail-safe testing and its frequency.
Union Electric Response - Item 5.7 Fail-safe testing of KAFV0029 is performed during the valve stroke test. The requirement to perform the fail-safe test at the same frequency as the valve stroke test, e.g., on a cold shutdown frequency, was implied in Relief Request #KA-01. For clarity, a reference to the fail-safe test of this valve was added to Relief Request #KA-01 in Revision 15 of the IST Program.
NRC Item 5.8 Prior to performing an IST systems review, a comparison of the valves in the IST program under Section XI, IWV, and under OMa-1988, Part 10, was made for deferral testing by using the previous Callaway IST program SERs (Ref. 14 thru 20). The
l ULNRC-3377 Attachment 1 Page 5 of 8 following items were found but changes in testing or test configuration may explain the differences:
(a) ALV006, 9) 12, 15, essential service water supply check valves to the suction of the auxiliary feedwater pumps. Valve table indicates full-stroke exercising but does not identify disassembly / inspection. The SER of August 19, 1987 (Ref. 16) states valves will be disassembled / inspected. These valves were not identified in the present relief requests for disassembly / inspection. Although relief is not required the licensee should advise if this is still the case. The present valve table indicates quarterly full-stroke exercising.
(b) BMHV0001, 2, 3, 4, the steam generator blowdown isolation valves. The previous SER (Ref. 15) states these valves cannot be exercised during power operations because failure of a valve )
in the closed position during testing would isolate normal '
blowdown flow, which would disrupt steam generator chemistry limits, which would require a plant shutdown and could cause ,
steam generator damage. These valves would be exercised during l cold shutdowns and refueling outages. The valve table indicates quarterly full-stroke exercising. The licensee should review the test procedure for these valves.
I (c) EMHV8802A, B are._the isolation valves in the safety l injection headers to the RCS hot legs, and cannot be exercised j during power operations because they are required to remain closed with power removed from their actuators by plant Technical Specifications. These valves must open to allow safety injection hot leg recirculation. The valve table indicates quarterly full-stroke exercising. The licensee should review the testing for these valves and document a test deferral, if necessary.
l Union Electric Response - Item 5.8 (a) Check valves ALV0006, 9, 12 and 15 are tested per OMa-1988, Part 10, Section 4.3.2.4.b, therefore, disassembly is not required.
(b) Relief Request #BM-01 was removed from the IST Program in Revision 11 as the basis for relief was no longer valid. Plant operating experience and chemistry calculations have shown that these valves may be closed for up to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> before chemistry conditions will force plant shutdown. Following removal of Relief Request #BM-01, the subject valves were placed on a quarterly test frequency.
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ULNRC-3377 t Attachment 1
- Page 6 of 8 (c) As a result of a recent evaluation, we determined that EMHV8802A and B may be exercised during power operations as
- long as EMHV8821A and B are maintained closed and Technical i Specification Action Statement 3.5.2.a is entered. Therefore, Relief Request #EM-06 was removed from the IST Program and these valves were placed on a quarterly test frequency.
NRC Item 5.9 The review performed for this TER did not include verification that all pumps and valves within the scope of 10CFR50.5En and Section XI are contained in the IST Program, and did not ensure that all applicable testing requirements have been identified.
The scope of the IST Program, however, was reviewed for several systems. The pumps and valves for the reactor coolant, chemical and volume control, high pressure coolant injection, safety injection, residual heat removal, main steam, feedwater, component cooling water, and essential service water systems were reriewed against the requirements of Section XI and the regulations. Technical input was obtained from the Callaway FSAR (Ref. 12) and IPE (Ref. 13). In general, the scope of the Callaway IST program for selected systems appears complete, I however, certain valves were identified that may be within the ,
scope of IST. It is recommended that the following valves be reevaluated for inclusion in the IST Program if the valves are Code Class 1, 2, or 3, and the function of the valves is credited in the plant's safety analysis.
5.9.1 Chemical and Volume Control System o BGHV8145, pressurizer auxiliary spray control valve, a3 inch air-operated globe valve, normally closed, which opens to supply pressurizer spray if normal spray is lost.
- BBV0084, 2 inch check valve, normally closed, which opens to allow pressurizer auxiliary spray from the CVCS.
- If throttle valves BGHV8357A, B to the RCP seals are open during an accident then check valves BGV0589, 590 should also open.
- Relief Valve: BG8124 - CCP suction header, 1 inch.
5.9.2 High Pressure Coolant Injection System l
- If the boron injection tank (BIT) has been replenished with boric acid since the SER of October 26, 1987 (Ref. 16) , as
ULNRC-3377 Attachment 1 Page 7 of 8 would be indicated by deferral #BG-04, then AOVs EMHV8883, EMHV8870A, B should be put back into the program to close, if in the recirculation mode, since they receive an SIS signal to close in an accident.
- Relief Valves: EM8853A, B: RHR pumps discharge, 3/4 inch.
EM8858A, B: SI pumps suction, 3/4 inch.
EM8851: SI cold leg injection, 1 inch.
5.9.3 Residual Heat Removal System o Relief Valves: EJ8856A, B: RHR pumps discharge, 3/4 inch.
EJ8842: RHR hot leg recirculation, 3/4 inch.
EJV156, 157: RHR pump cooling, 3/4 inch.
EJV084: RHR heat exchanger, 1/2 inch.
5.9.4 Main Steam System o ABV0345, 0346, 0347, 0348, 0349, 0350, 0351, 0352 - Air supply and nitrogen backup supply to the steam generators PORVs. Loss of air and nitrogen supply will cause S/G PORVs to remain closed. (It appears that these valves are Code Class 3 based on the piping designation (i.e., HBC).)
Union Electric Response - Item 5.9 5.9.1 Union Electric has determined that BBV0084 and BGHV8145 are not credited in the Callaway Plant safety analysis.
Therefore, these valves need not be included in the IST Program. Check valves BGV0589 and 0590 are added in Revision 15 of the IST Program. Refer to the response to Item 5.4 (c) for discussion on BG8124.
5.9.2 Callaway Plant modification CMP 90-1008 removed the Boron Injection Tank, EMHV8883, and EMHV8870A, B from the system. Relief Request #BG-04 has been revised to reference the boron injection header instead of the Boron Injection Tank.
Refer to the response to Item 5.4 (c) on Page 3 for discussion of the relief valves.
5.9.3 Refer to the response to Item 5.4 (c) for discussion of the relief valves.
5.9.4 Union Electric has determined that valves ABV0345, 0346, 0347, 0348, 0349, 0350, 0351, 0352 and similar valves ALV0148, 0149, 0150, 0151, 0152, 0153, 0154, 0155 are not ASME Code Class components. These valves were purchased as appurtenances to the valve operators. The valve operator data sheets show
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g ULNRC-3377 Attachment 1 Page 8 of 8-the check valves to be commercial grade components. Therefore, they are not required to be in the IST Program.
l Additional Information l The TER, Section 3.1.1 discusses why Relief Request #V02 is not required. Therefore, Relief Request #V02 has been. removed from ;
the IST Program. l l
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