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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 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 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 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 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 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 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 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-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-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 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 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 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 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 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 ML20207E2711999-05-25025 May 1999 Ack Receipt of in Response to & Insp Rept Confirming Commitment as Stated by M Taylor During Telephonic Exit Meeting on 990413 ML20207A8711999-05-24024 May 1999 Informs That NRR Reorganized,Effective 990328.Forwards Organization Chart 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-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-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-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 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 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 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 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 A93443, Forwards Responses to NRC 990315 RAI Concerning GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-05-19019 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-1998-003-01, 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 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 ML20204F7211999-03-17017 March 1999 Forwards Amended Fitness for Duty Program Performance Data for Six Month Period Beginning Jul-Dec 1998 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 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 ML20207C3461999-02-16016 February 1999 Forwards Exam Outline & Associated QA Checklist for Written Exam to Support Plant RO Retake Exam Scheduled 990423.Please Withhold Exam Matls from Public Disclosure Until After Exam Completion ML20203C5271999-02-0505 February 1999 Forwards follow-up Items Re Proposed Conversion to Improved TS Sections 1.0,3.2,3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Submittal Not Supplement to 970517 Amend Request & Not Reviewed by Onsite Review Committee or Nuclear Safety Review Board 1999-09-15
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1901 Chauteau Avenue Post Office Box 149 St. Louis, Mssoun 63166 1
314-5$4-2650 4
Uuron Janu ry 20,1995 Donald f. Schnell Etscnuc C;. !* *"*'
s U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ULNRC-3127 Gentlemen:
REPLY TO NOTICE OF VIOLATION INSPECTION REPORT NO. 56433/94012 CALLAWAY PLANT This responds to Mr. W. D. Shafer's letter dated December 6,1994, which transmitted a Notice of Violation and an unresolved item for events discussed in Inspection Report 50-483/94012. As agreed in the NRC/ Union Electric meeting on December 21,1994, this response is due by January 20,1995. Our response to the violation and unresolved item is presented in the attachment. It should be noted that Union Electric contests the violation. Additionally, UE does not agree with conclusions in the inspection report regarding management oversight of certain elements of the Fire Protection (FP) program. Our position regarding this conclusion is also addressed in the attachment.
None of the material in the response is considered proprietary by Union Electric Company.
If you have any questions regarding this response, or if additional information is required, please let me know.
Very truly yours, Donald F. Schnell DFS/tmw
Attachment:
- 1) Response to Violation and Untr.: solved Item 9501240390 950120 PDR ADOCK 05000403
,gg P
G PDR
d ULNRC-3127 Page 2 of 2 cc:
J. B. Martin - Regional Administrator, USNRC Region III M. J. Farber - Chief, Reactor Projects Section 3A, USNRC Region III L. R. Wharton - USNRC Licensing Project Manager (2 copies)
USNRC Document Control Desk (Original) -
W. D. Shafer, Chief Maintenance and Outage Section, USNRC Region III Manager - Electric Department, Missouri Public Service Commission B. L. Bartlett - USNRC Senior Resident Inspector T. A. Baxter - Shaw, Pittman, Potts, and Trowbridge
Attachment to ULNRC-3127 Page 1 of 7 Response to Violation 50483/94012-01 Statement of Violation Durir.g an NRC inspection conducted on October 31 through November 4,1994, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions",10 CFR Part 2, Appendix C, the violation is listed below:
Technical Specification 6.8.1 requires adherence to fire protection program implementing procedures.
Callaway Administrative Procedure, APA-ZZ-00742, " Control of Ignition Sources", Revision 11, requires that a Hot Work Fire Watch, if required, shall be posted at the work site before initiation of the hot -
work.
Contrary to the above:
On November 1,1994, the inspector observed grinding and welding activities in the emergency diesel generator room without a person performing the duties of a fire watch (50-483/94012-01(DRS)).
This is a Severity Level IV violation (Supplement I).
Basis for Disputing ' Ibis Violation Union Electric believes ne violation of NRC requiraments or the referenced Callaway procedure occurred. Therefore, UE contests the violation. The following provides our basis for disputing the violation.
Description of Occurrence During the Diesel Generator / Essential Service Water (DG/ESW) outage on November 1,1994, a welding job was being worked in the Diesel Generator Building.
This job involved installing a cap on a 1" branch from a 6" ESW line. The job was in a tight location, and the welders recognized that it would not be possible to get a grinding wheel onto the weld afterwards. The welders decided to ' hot pass' (one -
welder passes the welding stick to another while the weld is being made) the stick to assure a quality weld was made initially. As a result, during the course of the work, the welders recognized that for a short duration (five to ten seconds) both welders would have their face shields down and both would be conce.Mrating on the welding.
1 Attachment to I
ULNRC-3127 l
Page 2 of 7 The welders were both aware of Callaway's hot work permit system, procedures and j
expectations. They had checked the area for combustibles, and had discussed the fire.
l watch expectations. 'Ihey had obtained a fire extinguisher and evaluated the work i
i place. The work was being performed within two feet above the concrete floor of the DG room. There were no gratings or drains close to the work. There was no diesel fuel or oil on the floor. The welders determined that no additional craft were required I
to support the evolution, and that the non-welding craftsman would function as the fire watch as the other welded. 'Ihe short duration of time when both would have their.
j hoods down was considered inconsequential. The purpose of the fire watch is to L
identify fires as they begin. Expectations at Callaway have always allowed the l
designated fire watch to perform incidental activities while functioning as the fire l
watch. In this case, the ' hot pass' was an incidental activity.
j Mre Watch Expectations During Hot Work 1
l Fire watches at Callaway provide a first line identification of a fire for activities involving hot work. 'Ihe purpose of the fire watch is to identify a fire in its earliest j
stage and assure notification and extinguishment are accomplished directly. The fire
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watch is to have a fire extinguisher present to extinguish the fire.
l The fire watch also reviews the expected work and work area, determining the need for additional abatement, containment and personnel to accomplish fire watch duties. If l
the work is over grating for example, fire blankets and possibly even additional fire watches might be needed for each elevation. If combustibles are present that cannot be i
removed, appropriate measures are taken (e.g., wrapping in fire blankets, canceling the hot work until the combustibles can be removed or protected, etc.).
l The fire watch may perform other incidental activities, as long as such activities do not i
require leaving the immediate area or distract the fire watch from monitoring the work i
area. The incidental activities can be: gathering and organizing tools, housekeeping, j
cleaning tools or parts, tightening bolts, knocking slag off welds, direct support for the person doing the hot work (as long as the fire watch is able to watch the work area for a fire). As such, it is recognized that there will be short periods of time where the fire i
watch may not be directly viewing the work area. The fire watch is to assure that those l
time periods remain short so even a small fire will be identified in a timely manner..
The fire watch is expected to discuss the work and his evaluation of the work area with j.
the craft performing the work. When the fire watch responsibilities are shared between j
two craft, the discussion assures the craft member not performing the hot work will be the fire watch.
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Page 3 of 7 -
l Mitigating Cimunstances j
During this particular incident, the safety of the plant was not jeopardized. The Diesel i
Generator was tagged out for maintenance, and numerous individuals were in the room.
The mechanical craft supervisor (also a qualified fire watch) witnessed performance of
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the welding. Since the craft were meeting Callaway expectations, there was no
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requirement for coaching or remedial action during the hot work.
The craft made a safe and conscious decision on how to progress with this work, taking j
into consideration the physical limitations for accomplishing the weld, the status of the safety related equipment, the expectations for fire watch at Callaway, the physicai location of the' work close to the concrete floor of the room, the minimal amount of j
combustibles, the accanibility of a fire extinguisher and knowing the location of other fire extinguishers in the room. The craft did not take credit for the management, craft, i
operators, and others in the room during the hot work activity. Had they been the only j
two people in the room, the work and fire watch would have been accomplished in the same i
Corrective Actions i,
!j Union Electric does not believe any specific corrective action is required since no violation of regulations occurred. A fire watch was posted in accordance with our 3
procedure. The actions taken by the craft met management expectations and procedural requirements. The present program is effective in controlling hot work, and personnel are aware of and support the expectations outlined above. The craft involved did think j
through the hot work evolution and its impact on plant equipment and tie potential for l
a fire. The craft showed excellent use of the " STAR" (Stop - Think - Act - Review) technique in anticipating difficulties with using a grinder and showed good initiative and use of their technical skills in formulating an approach that satisfied procedural l
requirements.
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Rawd on the above Union Electric believes no violation occurred and, therefore, contests the violation.
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ULNRC-3127 Page 4 of 7 Unresolved Item 50'483/94012-02 i
Statement of Unresolved Item Failure to conduct periodic discharge tests to ensure an 8-hour minimum battery power j
supply for the emergency battery lights is considered an unresolved item.
Union Electric's Position i
j-A review of Callaway commitments, the FSAR, Code of Federal Regulations, Nuclear Regulatory Commission documents BTP CMEB 9.5-1, Generic Letter 86-10,-
a Inspection Procedure 64100 and Information Notice 90-69 indicate that Callaway has -
not committed to perform eight-hour discharge tests on the Emergency Battery Lights l
(EBL) associated with fire protection.
1 The eight-hour battery discharge test is discussed in section 5.3 of the EPRI, EmerBency Battery Unit Maintenance and Application Guide. The guide states that the need for periodic discharge tests on EBL batteries is a controversial topic. 'Ihe only
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operating characteristic that the test verifies is battery capacity at the time of the test. It does not guarantee post test capacity. The guide states that the performance of a j
discharge test is frequently questioned as to whether the limited information gained by the test justifies the expense. A new EPRI study is currently in process which is designed to establish a correlation between EBL battery conductance and impedance l
with battery capacity. This will provide an economical and reliable methosi of trending and predicting battery capacity without the potentially detrimental effects of a battery discharge test. Union Electric is presently studying battery conductance trending for l
capacity verification and battery replacement prediction and supports the project EPRI l
is pursuing.
1 The issue of an eight-hour discharge test at Callaway was initially brought up during an NRC inspection in November 1990. At that time the technical reasons against performing the discharge test were discussed with the inspector. At the request of the j
inspector, several EBLs selected by the inspector were eight-hour tested. All EBLs j
tested met or exceeded the eight-hour test. The issue of the eight-hour EBL test was 1
brought up again during the recent NRC inspection in November 1994. Callaway's technical position against performing the test has not changed based on the following i
assessment.
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Attachment to ULNRC-3127 j
Page 5 of 7 Assessment of 8-hour EBL Test l
Battery capacity is a function of the specific gravity of the electrolyte, the float charge i
voltage level being maintained on the battery, and the amount of plate material within the battery. At float voltages a negligible amount of battery material is displaced from the plates and the capacity of the battery remains relatively constant throughout the rated life of the battery, barring deep discharges and other detrimental battery 3
conditions.
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The negative impacts of eight-hour discharge tests include:
1)
Eight-hour discharge tests cause the battery to undergo a deep discharge cycle.
8 Sulfating from the deep discharge cycle can cause active material to be lost I
when the bettery recharges. Any permanent removal of plate material reduces l
battery capacity.
4 2)
If performed properly and with temperature effects on the battery rating taken j
into consideration, the eight-hour test can indicate a pass / fail condition of an EBL. However, the pass / fail test does not provide any trendable data to predict
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battery failure. An EBL tht demonstrates design compliance on one test cati i
suddenly fail the next test. The internal design of these batteries does not allow monitoring of individual cells during the testing. The voltage of the battery i
may hold to an acceptable level during the test, but given the 75% battery cutoff voltage, an individual cell could approach cell polarity reversal.
3)
If a service discharge test is to be performed, the discharge test must be
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j performed on the EBL as a unit, because the real parameter of concern is lighting. The eight-hour battery test would result in an exce.sive deep discharge i
of the battery and is not a practical test for small EBL batteries. The cost of a single performance test on a battery would exceed the cost of a new battery, and j
r.s such replacement of the battery without the test would be morejustifiable and cost effective.
SummaEE i
I In summary, Callaway has no commitment to perform eight-hour testing on the EBL's.
l Technically, no useful trendable information is obtainui from the test and it is potentially detrimental to the EBL batteries.
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1 Attachment to ULNRC-3127 Page 6 of 7 '
NRC Cancineian R*eardine Ma===*mant Overaleht
'Ihe inspection report transmittal letter contains a conclusion that " management oversight was weak in control of hot work, the impairment system, transient combustibles and the use of fire wat:hes". As discussed in the December 21 meeting with NRC, Union Electric disagrees with this conclusion. Although any program devised is capable ofimprovement, we believe management oversight of fire protection as presently constituted is streng. The following discussion provides our basis for this conclusion.
As stated in the NOV response, we believe no violation of fire watch requirements occurred.
A number of inspection observations in the report indicate the Callaway fire protection program is performing well, including:
a low number of fires and proper fire brigade response a low number ofimpairments a low backlog of fire protection equipment repairs excellent licensee audits and surveillances of fire protection thorough.50.59 evaluations of fire protection changes no areas containing substantial quantities of combustibles that pose a threat to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> barriers fire protection equipment in good material condition.
l As noted in the NOV response, the mechanical craft supervisor wm present at e
l the location of the presumed violation during performance of the welding.
This is an example of good management eversight.
We have a consistent record of satisfactorily handling multiple impairments of e
fire protection hardware.
l Although not mentioned in the report, the inspector noted as positive the e
diverse training and experience of fire protection personnel. - He also acknowledged the low threshold for problem identification and corrective action.
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Attachment to ULNRC-3127 Page 7 of 7 The report indicates a fire watch was i ot briefed that two boundaries (between a diesel generator room and a switchgt:ar room and between two switchgear rooms) required a continuous fire watch. Callaway's position is that a continuous fire watch was maintained for the two switchgear rooms and that a continuous fire watch is not required for the Diesel Generator room boundary.
The fire watch therefore had been preperly briefed and was aware of his duties. This was verified in subsequent discussions with the Plant Fire Marshal.
There were other less significant points of disagreement discussed at the December 21 meeting. We believe the foregoing record substantiates the strong performance of our fire protection program, including management oversight. Union Electric, therefore, does not agree with the NRC conclusion regarding weak management oversight.
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ULNRC-3127 i
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bec:
A160.0761 (QA Record) (CA-460)
A170.0103 (94012) (CA-460)
A170.0103 (94012 - File / Logging)
E210.0001 D. F. Schnell (Chrono)
G. L. Randolph J. V. Laux/F, W. Eggers Licensing and Fuels (A. C. Passwater/D. E. Shafer) (470)
H. D. Bono NSRB (G. A. Hughes/S. L. Dale) (470)
M. P. Barrett (100)
M. G. Williams (WCNOC)
K. A. Carroll (NOVs only)
G. J. Czeschin J. F. Hogg l
C. D. Naslund J. A. McGraw C. S. Petzel l
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