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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210H6381999-07-30030 July 1999 Forwards SE Accepting Relief Request for Approval for Use of Alternate Exam Requirement for Plant Inservice Insp Program A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 ML20210B4021999-07-19019 July 1999 Ack Receipt of Facility Emergency Plan Implementing Procedure EIP-ZZ-00101, Classification of Emergencies, Rev 23,issued on 990513,under Provisions of 10CFR50,App E, Section V ML20210B4401999-07-19019 July 1999 Ack Receipt of Revs to Facility Radiological Emergency Response Plan,Chapters 8.0 & 4.0,issued Respectively on 990512-14,under Provisions of 10CFR50,App E,Section V ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209E5591999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.TAC MA0531 Closed ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20196J9501999-07-0202 July 1999 Ack Receipt of Plant Ep,Rev 22,received on 981207 & Submitted Under Provision of 10CFR50,App E,Section V.Changes Does Not Decrease Effectiveness of EP & Continues to Meet Stds of 10CFR50.47(b).NRC Approval Not Required ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 ML20196H2521999-06-25025 June 1999 Forwards Insp Rept 50-483/99-05 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20196F8181999-06-24024 June 1999 Forwards RAI Re 990111 Request for Relief from Certain ASME Code ISI Requirements for Containment Liners.Response Requested within 30 Days from Date of Agreement ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve IR 05000483/19990041999-06-18018 June 1999 Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1 ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H0971999-06-14014 June 1999 Discusses Une 990407 Request That Proprietary Document Entitled, Thermal Stability Assessment - Electrosleeved Tubes, Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20207H3751999-06-14014 June 1999 Discusses 990407 Une Request That Proprietary Version of Document Entitled, Evaluation of Severe Accident Simulation, Dtd April 1999,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20207G3201999-06-0707 June 1999 Ack Receipt of Change Notice 98-008 Dtd 980918,which Transmitted Changes to Callaway Plant Ep,Rev 21,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required.No Violations Identified ML20207G3151999-06-0707 June 1999 Ack Receipt of Callaway Plant EP Implementing Procedure EIP-ZZ-001001M,Classification of Emergencies,Rev 22,issued on 981222 Under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS 1999-09-22
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS ML20196L2911999-05-19019 May 1999 Forwards Responses to NRC 990315 RAI Concerning GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves A36791, Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl1999-05-17017 May 1999 Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl ULNRC-04034, Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions1999-05-17017 May 1999 Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions 05000483/LER-1998-003, Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept1999-05-12012 May 1999 Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept ML20206Q9551999-05-12012 May 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-04.Corrective Actions:Une Commits to Make Available for NRC Review,Action Plan Outlining Scope & Completion Dates of Project ULNRC-04027, Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 9905281999-05-0404 May 1999 Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 990528 ML20206E3211999-04-28028 April 1999 Forwards Special Rept 98-03 Re Inservice Insp of CP Sgs,Per Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage.Rept Is Being Resubmitted Due to Typos in Original Rept ML20206E5781999-04-23023 April 1999 Informs That R Schukai Is No Longer Employed with Amerenue & Info Sent Is No Longer Required.Name Should Be Removed from Mailing Lists.Mailing Label Used by Company Which May Assist in Matter,Submitted ULNRC-04018, Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date1999-04-21021 April 1999 Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date ML20205Q7751999-04-16016 April 1999 Forwards Special Rept 98-03 Concerning ISI of Callaway SGs Performed in Apr 1998 During Callaway Plants Ninth Ro. Rept Documents Final SG Insp Results ULNRC-04015, Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.211999-04-15015 April 1999 Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.21 ULNRC-04005, Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.7901999-04-0707 April 1999 Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.790 ULNRC-04004, Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld1999-04-0707 April 1999 Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld ULNRC-04007, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date1999-04-0707 April 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date ULNRC-04000, Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w)1999-04-0101 April 1999 Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w) ULNRC-03998, Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.751999-03-30030 March 1999 Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.75 ML20205G2211999-03-25025 March 1999 Submits Rev 28A to Callaway Plant Physical Security Plan, Incorporating Addendum Re Security Sys Replacement Transition Plan,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20205R5251999-03-25025 March 1999 Forwards Special Rept 98-03 Re Results of Tenth SG Tube Inservice Insp,Per Requirements of Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage ULNRC-03988, Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 101999-03-19019 March 1999 Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 10 ULNRC-03991, Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette1999-03-19019 March 1999 Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette ML20204F7211999-03-17017 March 1999 Forwards Amended Fitness for Duty Program Performance Data for Six Month Period Beginning Jul-Dec 1998 ML20204E1331999-03-17017 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-02 on 990208-12.Corrective Actions:Will Revise Security Plan to Increase Min Staffing by Three Armed Security Force Response Personnel Per Shift ML20207C3631999-03-12012 March 1999 Forwards Exam Matl & Associated QA Checklist for Written Exam to Support Plant RO Retake Exam Scheduled for 990423. Exam Matls Requested to Be Withheld from Public Disclosure Until After Exam Completion 05000483/LER-1998-001, Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability1999-03-10010 March 1999 Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability ULNRC-03979, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date1999-03-0909 March 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date ULNRC-03975, Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl1999-03-0505 March 1999 Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl ULNRC-03971, Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded1999-02-26026 February 1999 Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded ML20207A4311999-02-17017 February 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for Period of 980701-981231 1999-09-15
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059G2971990-09-0404 September 1990 Notifies of Implementation of Procedure on 900831 to Correct wide-range Gas Monitor Display for Noble Gas Spectrum ML20059G4991990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-Jun 1990 & Rev 0 to APA-ZZ-01003, Odcm ML20059C3371990-08-23023 August 1990 Advises That Util Plans to Remove Some Thimble Plugging Devices from Plant During Upcoming Refueling Outage.No License Amend Required.Revs to Tech Spec Bases 3/4.2.2 & 3/4.2.3 That Reflect All Removal of Thimble Plugs Encl ML20058N2051990-08-0707 August 1990 Advises of Implementation of Amend 55,rev to Tech Spec 3/4.7.1.2 Re Auxiliary Feedwater Sys,Effective 900807 ML20081E1971990-07-27027 July 1990 Forwards Rev 6 to Indexing Instruction T210.0002/Q101, Qualification/Certification Documentation & Rev 6 to T210.002/R353, Required Reading/Personnel Form 2 ML20044B1821990-07-0909 July 1990 Forwards Westinghouse Revised Proprietary RCS Flow Measurement Uncertainty Calculation Supplementing Setpoint Studies Submitted in Attachment to Util 900412 Ltr.Encl Withheld ML20055E5261990-07-0505 July 1990 Forwards Revised marked-up Tech Spec Pages for 900306 Application for Amend to License to Place cycle-specific Core Operating Parameters in Core Operating Limits Rept ML20055E7861990-07-0505 July 1990 Forwards Callaway Plant 1990 Annual Exercise Scenario on 900530 ML20044A6601990-06-25025 June 1990 Forwards Requested Info Re Seismic Design of safety-related above-ground Vertical Liquid Storage Tanks,Per 900404 Ltr. All Stresses on Tank Roof Angle,Connecting Cylinder to Roof,Remain within Code Allowables Under Postulated Loads ML20043H8371990-06-21021 June 1990 Forwards Response to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issues at Facility ML20043H2721990-06-12012 June 1990 Forwards 10CFR50.59 Annual Rept Summaries of Written Safety Evaluations of Changes Approved & Implemented for Plant from 890330 to Present ML20043E2161990-06-0505 June 1990 Forwards Endorsements 42-48 for Nelia Policy NF-264 & Endorsements 28-34 for Maelu Policy MF-111 ML20043G9331990-06-0404 June 1990 Forwards Rev 13 to Operating QA Manual. ML20043D7101990-05-31031 May 1990 Forwards NPDES Renewal Application Submitted to State of Mo Dept of Natural Resources on 900518 ML20043B5841990-05-22022 May 1990 Responds to NRC 900423 Ltr Re Violations Noted in Insp Rept 50-483/90-04.Corrective Actions:Security Post Instructions Modified to Require Check of Security Container in QA Area ML20042F2831990-04-30030 April 1990 Forwards Rev 11 to Inservice Testing Program. ML20042F1161990-04-30030 April 1990 Provides Clarification to SALP 9 Rept 50-483/90-01 for Sept 1988 - Jan 1990.Licensee Voluntarily Retested Few Remaining Const Workers Originally Approved for Unescorted Access Using mini-IPAT ML20042F2901990-04-27027 April 1990 Forwards Util 900402 Ltr Documenting Agreement Between State of Mo Historic Preservation Officer & Util Re Cultural Resources ML20042D8491990-04-0202 April 1990 Forwards Listing of Present Level of Nuclear Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w) ML20012F1601990-03-29029 March 1990 Submits Supplemental Info Re Util Response to Station Blackout.Callaway Will Comply W/Numarc Station Blackout Initiative 5A Re Emergency Diesel Generator ML20012D1901990-03-19019 March 1990 Forwards Rev 15 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20012D7441990-03-16016 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. No Changes or Implementation Schedule Need Be Provided in Response to Generic Ltr 89-19 ML20012C6791990-03-0808 March 1990 Advises That Installation Date for Regulatory Effectiveness Review Concern 2.6.1 Revised to 900531.Deficiency Will Be Under Continuous Surveillance Until Correction Made ML20012C3111990-03-0606 March 1990 Forwards Addl Info Re Storage of Enriched Fuel in Spent Fuel Pool Area,Per NRC 900216 Request ML20012B3691990-02-28028 February 1990 Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums ML20012A4141990-02-23023 February 1990 Requests NRC Concurrence That Leak Chase Sys Is Integral Part of Containment Boundary & Does Not Need to Be Vented During Containment Integrated Leak Rate Test ML20006E1401990-02-12012 February 1990 Requests Clarification Re Positive Test Results for Controlled Substances,Specifically How Second Confirmed Positive Test Results Are Handled ML20011E7941990-02-0202 February 1990 Requests Emergency Relief from Tech Spec 3.1.3.1.b Due to Electrical Problem W/Rod Control Sys.Action Required to Prevent Plant Shutdown from 100% Power When Adverse Weather Conditions Exist in Svc Area ML20006D1061990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Dredge & Visual Shoreline Insps of Missouri River Near Plant Intake Indicated Presence of Small Numbers of Asiatic Clams ML20006C2311990-01-24024 January 1990 Forwards Callaway Plant Annual Exercise,891011, Emergency Exercise Scenario for 1989 Exercise ML20006B1371990-01-19019 January 1990 Forwards ECCS Evaluation Model Revs 10CFR50.46 Annual Rept. Util Will Provide Followup Rept Based on Results of Westinghouse Investigation to Be Completed in Second Quarter 1990 ML20005E8161990-01-0303 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of high-hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design ML20005E5141990-01-0202 January 1990 Certifies That fitness-for-duty Program That Meets Requirements of 10CFR26 Will Be Implemented on 900103 ML20005G3511989-12-28028 December 1989 Forwards Addl Info Supporting NRC Review of Proposed Revs to Tech Spec 3/4.1.3, Movable Control Assemblies. ML20005E5221989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. ML19353B0041989-12-0404 December 1989 Forwards Response to NRC 891016 Ltr Re Results of Regulatory Effectiveness Review on 890918-21.Encl Withheld (Ref 10CFR73.21) ML19332F1861989-11-30030 November 1989 Responds to Generic Ltr 89-15 Re Emergency Response Data Sys.Sys Will Be Implemented by Jul 1991,to Allow Addl Features to Be Developed for Plant Computer Sys & to Be Installed in Conjunction W/New Plant Computer Sys ML19332E9881989-11-30030 November 1989 Discusses Visual Insp of Hafnium Rod Cluster Control Assemblies During Refuel-2 in Fall 1987.Results Indicate Guide Card Fretting Wear Per NRC Info Notice 87-019.All Hafnium Rods Replaced W/Silver/Indium/Cadnium Assemblies ML19332D4441989-11-22022 November 1989 Responds to Generic Ltr 89-21,forwarding Table Providing Implementation Status of Each USI at Facility ML19327C0741989-11-0707 November 1989 Forwards Executed Amend 3 to Indemnity Agreement B-93, Reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements. ML19324C4291989-11-0707 November 1989 Responds to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded-Case Circuit Breakers. Bulletin Provisions as Clarified by Suppl Met & Documentation Associated W/Review Being Maintained at Facility ML19332B6121989-10-31031 October 1989 Provides Individual Plant Exam Method & Schedule.Completion of Level 1 PRA Scheduled for Jul 1991.Containment Performance Analysis Will Be Completed in Feb 1992.Results Will Be Provided in Sept 1992 ML20005D6181989-10-23023 October 1989 Submits Response to Suppl 1 to Generic Ltr 89-07 Re Safeguards Contingency Planning for Surface Vehicle Bombs. Short-term Actions Included to Protect Against Attempted Radiological Sabotage Involving Land Vehicle Bomb ML19325C9251989-10-0404 October 1989 Submits Corrected Wording to Encl to 890929 Ltr Supporting 10CFR50,App J Exemption to Allow Leak Chase Plugging During Integrated Leak Rate Test ML20248E4831989-09-29029 September 1989 Forwards Addl Info to Support 10CFR50,App J Exemption to Allow Leaving Leak Chases Plugged During Type a Integrated Leak Rate Test ML20248G0871989-09-28028 September 1989 Responds to NRC Bulletin 88-011 Re Pressurizer Surge Line Thermal Stratification.Action Items 1.a & B Completed & 1.d Actions Re Stress & Fatigue Ongoing Through Westinghouse Owners Group ML20248C1951989-09-21021 September 1989 Forwards Summary of Refueling Water Storage Tank Seismic Design Analysis Which Includes Effects of Tank Wall Flexibility.Issue Not Applicable to Condensate Storage Tank at Facility ML20246J7011989-08-30030 August 1989 Forwards Semiannual Radioactive Effluent Release Rept for First Half 1989.W/o Encl ML20246K9451989-08-29029 August 1989 Forwards Relief Request 0 to Plant Inservice Insp Program Plan,Per Observations During Refuel III ML20246E0521989-08-18018 August 1989 Forwards Info on Operator Licensing Exam Schedule,Per Generic Ltr 89-12 1990-09-04
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UNION ELECTRIC COMPANY loot onATeor einerr Sr. Louis Missoung April 13, 1983 uuu ~. .o o.. ...
DONALO P. .CHNELL P.O. SON 84.
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Mr. W. S. Little, Chief Project Engineering Branch U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road ,
Glen Ellyn, IL 60137 ULNRC- 618
Dear Mr. Little:
INSPECTION REPORT NO. 50-483/82-20
,, This reply is in response to your letter of March 15, 1983 which transmitted the report of the inspection conducted at Callaway Plant, Unit 1 during the period of December 13-14, 1982 and January 5-7, 1983. Our responses to the Items of Noncompliance are presented below in the order listed within the body of Inspection Report Number 50-483/82-20.
None of the material in the inspection report or in this response is considered proprietary by Union Electric Company.
(50-483/82-20-01) SEVERITY LEVEL V VIOLATION 10 CFR 50, Appendix B, Criterion III, states, in part, that " Measures shall be established to assure that applicable... design basis...for those structures, systems, and components...are correctly translated into specifications, drawings, procedures, and instructions.
,10 CFR 50, Appendix B, Criterion V, states s in part, that " Instructions, procedures, or drawings shall include appropriate quantitive or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished."
Standardized Nuclear Unit Power Plant System (SNUPPS)
"QA Program for Design and Construction", Revision 4, dated December 1981, Paragraph 17.1.3 states, in part, that "The SNUPPS
- utilities quality assurance program requires that the design of l the safety-related structures, systems, equipment and components of the SNUPPS nuclear power plants be controlled so that l applicable regulatory requirements and design bases are properly translated into specifications and drawings. The SNUPPS
( utilities require that the major contractors identify sequential j review requirements and assignments for each function throughout l the design and engineering process, such as: conceptual and l 8305060293 830503 l
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Mr. W. S. Little April 13, 1983 preliminary design and development of drawings, specifications and supporting calculations."
Contrary to the above, the architect engineer's design control relative to the piping suspension systems was considered to be deficient in the following areas:
- a. The program lacked design criteria that would ensure piping seismic movement was sufficient to allow snubber lock up and compression to reach its full load capacity. Several of the observed snubber installations had not been evaluated to ensure their functionability,
- b. The inspection instructions for the stiff re-enforced pipe clamps provided by the architect engineer were not adequate to ensure sufficient critical load bearing surfaces were achieved to maintain overall snubber design structural assembly spring stiffness.
Response
Union Electric Nuclear Engineering and the lead A/E are continuing to evaluate this item. A response to this item will be transmitted to Region III no later than June 1, 1983.
(50-483/82-20-03) SEVERITY LEVEL V VIOLATION 10 CFR 50,_ Appendix B, Criterion X states, in part, "A program for inspection of activities affecting quality shall be established and executed by or for the organization performing the-activity to verify conformance with the documented instructions, procedures, and drawings for accomplishing the activity."
Standardized Nuclear Unit Power Plant System (SNUPPS)
"QA Programs for Design and Construction", Revision 4, dated December 1981, Paragraph 17.1.10 states, in part, that, "The SNUPPS utilities have assigned the responsibility for detailed implementation of inspection to the following: Bechtel, Westinghouse, each site A/E, and each construction manager or constructor for their respective scope of work. Each utility has or will establish provisions for auditing the implementation of their involvement in the inspection of activities affecting quality. Since many of the activities associated with design and construction are performed by major contractors, the SNUPPS utilities place emphasis on audit and surveillance of inspection activities performed by these organizations. This surveillance supplements the detailed inspections utilized by the major contractors."
l
Mr. W. S. Little April 13, 1983 Contrary to the above, the present QC inspection program did not require final piping suspension system inspection until all components were installed and fasteners tightened. As a result, deficiencies could not be identified by the QC staff in a timely manner and thus initiate management corrective action and preventive measures.
Corrective Action Taken and the Results Achieved:
QCP-200 has been revised to more clearly describe in-process inspections. General configuration and location is now defined to include item dimensions, angularity / perpendicularity, axial orientation, fit-up inspection, and location verification using pipe location together with building and column lines and elevations.
Corrective Action To Be Taken to Avoid Further Noncompliance:
Exhibit BI of QCP-200, Revision 17 (Component Support Inspection Checklist) has been revised to more accurately reflect the stage of inspection. This was achieved by incorporating an additional matrix in the checklist.
The Date When Full Compliance Will Be Achieved:
Full compliance was achieved on January 22, 1983.
(50-483/82-20-04) SEVERITY LEVEL V VIOLATION 10 CFR 50, Appendix B, Criterion XVI, states that,
" Measures shall be established to assure that conditions adverse to quality, such as failure, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected. In the case of significan: conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition. The identification of the significant condition adverse to quality, the cause of the condition, and the corrective action taken shall i be documented and reported to appropriate levels of management".
l j Standardized Nuclear Unit Power Plant System (SNUPPS) l "QA Program for Design and Construction," Revision 14, dated December 1981, Paragraph 17.1.16 states, in part, that, "The SNUPPS utilities have established a corrective action program which determines the need for corrective action and assures that conditions adverse to quality are promptly identified, reported, corrected and that the corrective action is appropriate and effective. The program requires that the cause of the adverse i
condition be determined, corrective action be taken to preclude repetition, and verification be made that these actions have been implemented in a timely manner in accordance with specified requirements."
- Mr. W. S. Little April 13, 1983 Contrary to the above, the corrective actions taken in relation to an item of noncompliance for not establishing an adequate piping suspension QC inspection program were considered to be deficient in the following ways:
- a. Program and installation deficiencies continued to be identified during this inspection.
- b. The licensee failed to implement their commitment to Region III in that the present procedure does not include the time limitation requirement of inspection within 30 days subsequent to the hardware installation completion.
As of the date of this inspection, more than 1,000 restraint / support assemblies, among the approximately 4,000 units installed, did not receive adequate inspections in the areas of support location, configuration, orientation, and condition.
Correction Action Taken And The Results Achieved:
At the time of the NRC Inspection, 1290 hangers were identified which were essentially completed, but had not been final inspected within a thirty (30) day time frame. That number has now been reduced to 489. Final inspection of these completed hangers will be accomplished on a system priority basis. No schedule has been set for final inspection of the remaining hangers; however, we will continue to track and reduce this number, as discussed with the Inspector at the Callaway NRC Exit Meeting.
Also at the time of the NRC Inspection, 613 hangers (estimated at 550 at the Exit Meeting) were identified which were in some stage of erection, without an inspection status. This Jpecific category of hangers has been inspected and statused under the new inspection program utilizing the new checklist.
WP-200 (Field Fabrication and Installation of Safety
, Related Piping and Component Supports), Revision 20, and QCP-200 l
(Inspection of Fabrication and Installation of Safety Related L Piping and Component Supports), Revision 17, more clearly define in-process inspection requirements. In addition, Exhibit BI of QCP-200 incorporated an additional matrix into the checklist which more accurately reflects the stage of inspection. All new erections of pipe hangers are subject to the revised inspection program and new checklist which are designed to assure timeliness.
The procedure revisions described above provide "real j
time" inspection, i.e., inspections are made as soon as l
Construction completes each erection phase.
F Mr. W. S. Little April 13, 1983 Corrective Action To Be Taken To Avoid Further Noncompliance:
Implementation of WP-200 and QCP-200 is designed to avoid further noncompliance.
The Date When Full Compliance Will Be Achieved:
Procedure revisions and documented training to implement the program were completed by January 22, 1983.
The group of hangers (613) which were in some stage of erection, without inspection status, has been inspected and statused. This action was completed by March 24, 1983.
(50-483/82-20-05) SEVERITY LEVEL V VIOLATION 10 CFR 50, Appendix B, Criterion XV states, in part, that " Measures shall be established to control materials, parts, or components which do not conform to requirements in order to prevent their inadvertent use or installation. These measures shall include, as appropriate, procedures for identification, documentation, segregation, disposition, and notification to affected organizations."
Standardized Nuclear Unit Power Plant System (SNUPPS)
"QA Programs for Design and Construction", Revision 4, dated December 1981, Paragraph 17.1.15 states, in part, that, "The quality assurance program established by the SNUPPS utilities provides measures to prevent inadvertent use or installation of safety-related materials, parts and components when determined not to be in compliance with the requirements of applicable codes, standards, drawings, specifications or other procurement documents. The program requires identification, classification, resolution and followup of material nonconformances which are detected during the course of design, procurement, construction and preoperational testing activities." " Reviews are made of material nonconformance reports to determine quality trends. For activities within the scope of the SNUPPS concept, these reviews are performed by the SNUPPS organization and results are documented and submitted to each utility. For activities outside the scope of the SNUPPS concept, .these reviews are performed by each utility's OA organization and results are documented and submitted to the utility's management.
Contrary to the above, the present "QC Hanger Discrepancy Report" system contained in DIC Procedure WP-200, and the " Minor Discrepancy Report" system contained in DIC Procedure AP-VII-02 were considered to be inadequate based on that fact that there were no specific scope and limitations prescribed for use of these systems. In addition, there were no instructions provided for the site personnel on how these systems should be implemented.
a
. Mr. W. S. Little April 13, 1983 Corrective Action Taken And The Results Achieved:
Daniel has performed a review of the overall program utilized in reporting minor discrepancies. ICP-1 to AP-VII-02, Revision 11 proceduralized the " Hanger Discrepancy Report" (HDR) and the " Minor Discrepancy Report" (MDR) on January 14, 1983.
Revision 12 of AP-VII-02 was issued on April 6, 1983, officially incorporating the ICP.
WP-200, Revision 20 and QCP-200, Revision 17 were issued effective January 22, 1983. Documented training sessions for appropriate Quality and Engineering personnel were completed by January 22, 1983.
While the above actions have substantially strengthened the MDR/HDR Program, we consider those actions to be interim.
Further refinement is proposed and in-process.
Corrective Action To Be Taken To Avoid Further Noncompliance:
Meetings are currently being held to establish further refinement and develop specific uses for an MDR/HDR. Site procedures will be revised to incorporate further changes which result from the meetings.
Following completion of the above actions, documented l training sessions will be held for appropriate Quality and Engineering personnel.
The Date When Full Compliance Will Be Achieved:
i ICPs will be issued to appropriate site procedures by April 30, 1983. Full compliance will be achieved by May 31, 1983, upon completion of documented training and incorporation of
! ICPs into site procedures.
If you have any questions regarding this response or if additional information is required, please let me know.
Very truly yours, O
/
j Donald F. Schnell JGJ/ mal i
cc: Mr. H. M. Wescott, NRC Region III NRC Resident Inspector, Callaway Plant
! Missouri Public Service Commission I
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