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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 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 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 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 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 ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 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 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 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 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 ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 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 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 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 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 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 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-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 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 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-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-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-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 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:STATE/LOCAL GOVERNMENT TO NRC
MONTHYEARML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML18094A6231989-08-11011 August 1989 Requests Addition of Ofc of Peoples Counsel to NRC Svc Lists for Insps,Events & Mgt of Facilities.Ofc of Peoples Counsel Represents Residential Customers of Utils Regulated by State of MD PSC ML20206C5901988-11-0909 November 1988 Forwards Withdrawal of Request of State of Tn to Participate as Interested Party,Per 10CFR2.715(c).Requests That Mh Mobley Remain on Svc List for Purpose of Receiving All Pertinent Correspondence,Filings & Notices ML20207M0691988-09-29029 September 1988 Comments on Environ Assessments & Finding of No Significant Impact Documents Re Alchemie Facilities.Blind Approach of Addressing Stable Isotope Enrichment Appalling ML20154A0931988-08-30030 August 1988 Forwards Comments on from Alchemie,Inc Re Radiological Hazards.Clarification Desired ML20153E9121988-07-22022 July 1988 Suggests That NRC Propose to State Historic Preservation Officer That Properties Identified by Util Are Eligible for Inclusion in Natl Register Re Properties Threatened W/Damage from Operations & Maint Activities.W/O Encls ML20151G6531988-07-18018 July 1988 Advises That State of Tn Will Forgo Appearance at 880721 Prehearing Conference in Knoxville,Tn Based on Concerns Already or in Process of Being Addressed ML20195G6951987-09-0202 September 1987 Opposes Plant Restart Pending Revs to Radiological Emergency Response Plan.Current Plan,Dtd May 1985,inadequate W/Respect to Response Time,Evacuation Procedures & Reception Ctrs ML17347A5661987-06-0505 June 1987 Advises That Verbal Notification of Release of Amends to NRC Licenses in State of Fl Not Necessary.Written Notification of Proposed Amends Soliciting Comments & Written Rept of Release Adequate ML20235G2131987-05-28028 May 1987 Requests Info Re NRC Insp of Detroit Edison Safeteam Files, Including Insp Results,Corections to Problems,Adequacy of Util Investigations & Manner NRC Selected Files to Examine ML20204F2681987-03-19019 March 1987 Requests Removal from Distribution List for Listed Dockets ML20213G5481987-03-12012 March 1987 Requests Timely Review of Encl Draft Legislation Creating Onsite Monitoring Presence for State of Me at Facility & MOU Between NRC & State of or ML20211G5061987-02-13013 February 1987 Advises of Change of Address for State of Oh Dept of Health. Functions of Power Siting Commission Transferred to Board Operating Under Auspices of Puc of State of Oh ML20211G5301987-01-14014 January 1987 Forwards Rept of Emergency Evacuation Review Team on Emergency Response Plans for Perry & Davis-Besse Nuclear Power Plants. Rept Concluded That Current Emergency Response Plan Inadequate.Served on 870128 ML20237C8811986-12-22022 December 1986 Forwards Rept to Governor on Emergency Preparedness for Accident at Pilgrim Nuclear Power Plant, Presented on 861216.Governor Accepted Finding That Current Offsite Radiological Emergency Response Plans for Plant Inadequate ML20211A9381986-10-0909 October 1986 Requests to Be Placed on Mailing Lists for Publications Re Perry,Davis-Besse & Beaver Valley Nuclear Plants.Puc of Oh Directed to Conduct Investigations. Comprehensive Assessment of Perry First Study to Be Conducted ML20205F3051986-08-15015 August 1986 Withdraws State of Oh Support for Evacuation Plans & Expects NRC to Withhold Full Power Ols,Pending State Review of 860131 Earthquake Near Perry & 850609 Event at Davis-Besse. Full Exercise of State Rights Anticipated.Served on 860818 ML20204F2571986-07-29029 July 1986 Requests Notification Before Issuance of License Amends for State of Il Nuclear Power Plants,Per 10CFR50.91(b) ML20204F1911986-07-29029 July 1986 Requests Notification Prior to Issuance of Amends to OLs Per 10CFR50.91(b).NRC Adherence to State Notification Practice Generally Acceptable,W/Some Exceptions ML20199L5831986-05-0707 May 1986 Raises Concerns Re NRC Poor Record of Enforcing High Safety Stds in State of Oh.Reconsideration of Earthquakes as Safety Issue Requested ML20206U8211986-02-25025 February 1986 Responds to Acceptance Appraisal on 851017-18.One Technician Added to Div of Labs & Split Sampling Program for Cooper Nuclear Station Initiated in Jan 1986 ML20154L4851986-02-25025 February 1986 Ack Receipt of Re Acceptance Appraisal Rept 99990004/85-10 on 851017-18 for Proposed Nrc/State of Ne Environ Monitoring Agreement Around Fort Calhoun & Cooper Plants.Response to Rept Concerns Listed ML20137A3631986-01-0707 January 1986 Advises of No Adverse Findings as Result of Review of Proposed Tech Spec Amend to License NPF-37 Re Closure of Valves SI 8809A & B During Check Valve Surveillance Testing ML20136F6741986-01-0303 January 1986 Requests That NRC Continue to Send Copies of Correspondence W/Util to State & Delete as Cauger & EA Eisen from Svc List.Ltr to Wl Clements & NRC 841211 Memo Encl ML20136A5621985-12-11011 December 1985 Lists New Address for Cd Jones,Director,State of Il Emergency Svcs & Disaster Agency ML20138R9591985-11-15015 November 1985 Informs That as Cauger to Be Replaced by CR Rogers as Assistant General Counsel for State of Mo PSC ML20213F3831985-07-15015 July 1985 Requests Suspension of Low Power Testing at Facility Until Investigation of Accident Causing Hot Shutdown of Plant & Review of Training of Personnel & Condition of Equipment Complete ML20213F3871985-07-11011 July 1985 Requests Immediate Halt of Low Power Testing at Facility Until Investigation of 850710 Accident in Which Valve Sys in Primary Containment Bldg Improperly Left Open Releasing Gas Into Atmosphere Complete ML20137E9721985-07-11011 July 1985 Discusses Interim Environ Surveillance Program Under Cooperative Agreement NRC-31-83-671.Proposed State Program Will Be Implemented by End of 1985 ML20127N5501985-06-27027 June 1985 Discusses Proposed Exemption from 10CFR50.71 to Submit Updated FSAR for Both Plants 12 Months After Issuance of Braidwood Unit 2 Ol.Updated FSAR for Byron Should Be Issued by 880214,per 850627 Discussion W/L Olshan ML20215L2171985-05-23023 May 1985 Notifies That Agreement Between Valley Stream Union Free School District Thirteen,American Red Cross & Util Re Use of Congregate Care Ctrs in Event of Nuclear Plant Emergency Nonexistent.Served on 850603 ML20215L2201985-05-20020 May 1985 Notifies That Roslyn Board of Education Agreement W/Util Re Use of Congregate Care Ctrs in Event of Plant Emergency Nonexistent.Served on 850603 ML20215L2271985-05-17017 May 1985 Notifies That Island Park School District Agreement W/Red Cross & Util Re Relocation in Event of Radiological Emergency Nonexistent.Served on 850603 ML20215L2381985-05-13013 May 1985 Notifies That Westbury Union Free School District Agreement W/American Red Cross or Util Re Svc as Relocation Ctr in Event of Plant Emergency Nonexistent.Served on 850603 ML20215L2491985-05-10010 May 1985 Protests That Willingness to Participate W/American Red Cross in Event of Natural Emergency Extended by Red Cross to Include Any Emergency Occurring from Plant Atomic Energy Generators.Served on 850603 ML20215L2581985-05-0909 May 1985 Notifies That Freeport Public Schools Not Consulted by Util Re Emergency Evacuation Plan & Unaware of Inclusion in Plan Until After Publication.Served on 850603 ML20215L2661985-05-0808 May 1985 Notifies That Permission to Include School in Evacuation Plan,Consistent W/Plan Evacuation Schedule,Granted to No One.Served on 850603 ML20215L2621985-04-0808 April 1985 Informs That No Legal Agreement Exists Between Nassau County & Util Re Use of Plant.Served on 850603.W/service List & Certificate of Svc ML20136F6811985-02-14014 February 1985 Forwards Info to Update Svc Lists Per NRC 841211 Memo ML20213F1201984-12-20020 December 1984 Supports Resolution, Sense of Legislature Resolution Requesting That NRC Permit Suffolk County to Present Oral Arguments Opposing Util Request for Low Power License for Shoreham Nuclear Power Plant. Resolution Encl ML20213F1081984-12-19019 December 1984 Decries Licensee Refusal to Provide Info to Public Re Status of Fuel Loading.Immediate NRC Order Directing Util to Provide Regular,Full & Accurate Disclosure of Fuel Loading & Low Power Testing Requested ML20215L2421984-12-0707 December 1984 Requests Opportunity to Present Oral Arguments Against Issuance of Low Power License for Plant.Served on 841213 ML20133H6931984-11-14014 November 1984 Discusses Concerns Re Decision by PSC of Mo Concerning Inservice Criteria for Facility.Rept & Order - Phase I Re Procedural History Encl.Ack NRC Jurisdiction Over Facility Safety ML20128Q7911984-11-14014 November 1984 Addresses NRC Concern Re Inservice Criteria for rate-setting & Effect Criteria May Have on Unduly Speeding Up Plant Const.Order on Inservice Criteria Encl ML20095E0091984-07-0505 July 1984 Requests NRC Safety Investigation Repts for Past 8 Months & Notification of Current Investigations.Info Needed to Determine Possible Financial Effect on State of Ak,Which May Need to Fund & Buy Energy from Facilities ML20084G2101984-05-0202 May 1984 Requests Mo Public Svc Commission Representative Be Allowed to Accompany NRC on 840510 Site Visit to Wolf Creek. Representative Will Be at Fulton,Mo for NRC Meeting Re Callaway to Ensure NRC Rules Not Violated ML20084G2131984-04-19019 April 1984 Requests Resumption of Caseload Forecasts for Facilities. Independent Caseload Forecasts Useful in Estimating Project Costs,Scheduling Plant Audits & Preparing Rate Cases ML20086T8061984-02-29029 February 1984 Apologizes for Slow Response to 840208 Request for Addl Info on Wheeling Contract.No New Addl Info Available.Agreement Not Yet in Sight ML20087L8361984-02-17017 February 1984 Requests Explanation as to Why Facility Not Considered for Insp for Cracks in Vent Header Similar to Crack Found at Hatch ML20080F0811984-01-30030 January 1984 Informs NRC of Efforts of Missouri Joint Municipal Electric Util Commission to Obtain Transmission Agreement W/Util 1990-02-05
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November 14, 1984 751 3234 P.O.80X360 jfr/EASONo77 9g** *...e .e * , ' MIS 50URIss t02
- Commissioner James Asselstine Nuclear Regulatory Commission C =ias n: 1717 H Street, N.W.
WILLIAM D. STUNMUER Washington, D.C. 20555 Chair-an CHARLOTTE MUSGRAVE
Dear Comissioner Asselstine:
ALLAN C MUELLER CoNNtE B HENDREN It has come to my attention that you and other members of JAMES M TISCHER the Nuclear Regulatory Comission (NRC) have voiced concerns about the decision of the Missouri Public Service Comission (Misscuri RostRTI SCainstR Comission) in Case Nos. ER-84-168 and EO-85-17 pertaining to the 5"H S= " in-service criteria, for the Callaway Nuclear Plant, Unit 1 (Callaway). In particular, it was suggested that our in-service HARVEY C. HUBS 5 Criteria for rated 3 king purposes would somehow encourage Union 5" " "'7 Electric Company to unduly expedite completion of the plant, at the expense of ssiety of the plant. I would like to address this f
KENT M. RACSDALE ConCeIn.
1 Cenen1 C.unnel First, the Missouri Comission believes that the NRC's requirecents for safeguarding the health, safety, and welfare of the public stand alone. The Missouri Comission's requirements for ,
ratemaking recognition of Callaway are not oblivious to the exclusive jurisdiction of the NRC over nuclear plant safety. The Missouri
'. Comission's Report and Order of August 22, 1984 concerning the
- in-service criteria for Callaway requires first and foremost that the NRC-approved testing and licensing requirements must be satisfied before the plant may be included in rates.
Second, under the " file and suspend'; method of proceedings set by statute in Missouri, electric utility rates must be ruled upon by the Ccemission within a maximum of eleven (11) months after the filing of the tariffs requesting an increase in rates. Although the suspension period in which the Missouri Comission may act is constrained by law, the timing of the utility's tariff filing is
- within its sole discretion. Thus, Union Electric Company initiated the schedule with which you are concerned. Prior to deciding the l matter of the Callaway in-service criteria, the Missouri Commission sought to address Union Electric Compcny's concern that Callaway might not be'in-service by the end of the eleven (11) month rate case period that Union Electric Company set in motion by the filing of
- tariffs on February 15, 1984. In fact, ve have established an extraordinary procedure in this case to try to assure that a whole new rate case record need not be begun even though the in-service criteria are not met by the end of the current rate case. In addition, the Missouri Comission han stated that AFUDC may continue 950BO90460 850627 FDR FOIA BELL 85-354 PDR /
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. Connicci:ner Jams 3 Assol: tine :
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- November 14, 1984 P:ss 2 - l to be accrued on Callaway for ratemaking purposes if there is any lag between the in-service date and an order giving rate recognition of 4 the plant. These devices should give Union Electric Company ample and adequate protection such that the Company has no incentive to unduly expedite plant completion and power ascension testing at the ,
expense of safety considerations. l l
Third, I would point out that Section 393.135, RSMo 1978 was adopted by popular referendum on November 2, 1976. Said section provides that the plant of an electrical corporation must be " fully operational and used for service" before any charge may be made or
- demanded based on the costs of said property. While it is true that J Callaway is Missouri's first nuclear plant, it has not been singled out for the application of "in-service criteria." In-service criteria have been set and applied by the Missouri Commission to nine (9) coal-fired units in the eight years since Section 393.135, RSMo 1978'became law. Our in-service criteria for Callaway are designed to assure that the plant.is fully operational and used for service, and is safe and reliable, before the risks of the plant are shifted to ratepayers and costs of the plant are included in rates.
4 I have taken the liberty of enclosing a copy of our Report and Order on in-service criteria for Callaway, for your reference.
In summary, let me say that we have the utmost confidence in the quality and adequacy of the NRC's safety requirements for the Callaway (and Wolf Creek) nuclear plants, and fully recognize your exclusive jurisdiction over the safety of those plants. Your safety requirements must be fully met before those plants may operate commercially, regardless of the criteria we have established for rate '
recognition of the plants. In fact, our in-service criteria for ratemaking purposes include successful completion of the NRC's safety '
requirements. Therefore, I can conceive of no manner in which our
! in-service criteria could adversely affect the safe completion of Callaway.
- If the Missouri Commission can be of assistance regarding this or any other matter, please do not hesitate to contact me.
f Si c,erely.
- ll.7 . y. *
(jl40%$
liam D. Ste nue e i Chairman Enclosure ec: Chairman Nunzio Palladino Commissioner Thomas h. Roberts Commissioner Frederier M. Bernthal l Commissioner Lando W. Zech, Jr.
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' '. i BEFORE THE PUBLIC SERVICE ColMISSI0tt 0F THE STATE OF MISSOURI
.i CASE NO. ER-84-168 l In the matter of Union Electric Company of St. Louis, Missouri, for authority to file tariffs increasing rates for electric service provided to cusi,cmers )
in the Missouri service area i of the Company. I CASE NO. 80-85-17 !
l In the matter of the determination of in-service criteria for the Union Electric Company's Callaway l Nuclear Plant and Callaway rate base and related issues. I i
i APPEARANCES: Paul A. Asathen, Attorney at Law, and Gerald Charnoff Attorney at Law, P. O. Box 149, St. Louis, Missouri 63166, '
I i for Union Electric Company.
William Claric Kelly, Assistant Attorney General, P. O. Box 599, Jefferson City, Missouri 65102, for the State of Missouri. -
William M. Barvick, Attorney at Law,124 East High Street, Jefferson City, Missouri 65101, for the City ,
of Jefferson, et al.
Richard V. French, Assistant Public Counsel, P. O. Box 7800, Jefferson City, Missouri 65102, for the Office of the Public .
Counsel and the Public. l Villiam C. Harrelson, Deputy General Counsel, P. O. Box 360, Jefferson City, Missouri 65102, for the Staff of the Missouri l Public Service Commission j REPORT AND ORDER - PHASE I PROCEDURAL HISTORY On February 15, 1984, the Union Elgetric Company (hereinafter Company) 1 filed revised tariffs seeking authority to increase rates for electric service
- provided to custcaers in the Missouri service area of the Company. The tariffs bore an effective date of March 16, 1984.
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1 , .
Th3 Company has proposed fsur criterin while the Staff has proposed six criteria. Missouri Retailers Association, which participated in the prehearing
- conference only, supports Staff. The Public Counsel and the City of Jefferson, et al., support Staff's criteria 1 through 5 but oppose Staff's criterion 6. All parties argue that their respective positions propose criteria which necessarily must I
be satisfied to support a finding by the Commission that the Callaway Nuclear Plant 1
is " fully operational and used for service" within the meaning of Section '93 135, RSMo 1978.
The Company takes the position that the plant should be declared "in-service" when the plant is providing safe and reliable power. The Company's "in-service" criteria is as follows:
Criterion 1. The Company as granted an operating license by the Nuclear Regulatory Commission to operate the plant at high power levels.-
Criterion 2. The turbine generator and nuclear steam supply system have demonstrated the capability to sustain reliable power operation.
Criterion 3 The plant has supplied electricity to the Company's system with output scheduled by the system load dispatcher.
Criterion 4. All components of the plant needed to generate at 100 percent of capacity are capable of operation.
Company's four criteria will be satisfied at 50 percent power although the Company intends to complete all testing required by the Nuclear Regulatory Commission (hereinafter NRC) and complete full power ascension to 100 percent power prior to i
j declaring the plant "in service". The minimum standard for declaring the plant "in service" under the Company's criteria is at the 50 percent power level after having operated at that level for 25 to 30 days. The company desires to retain the flexibility to declare the plant ain-service" somewhere between 50 and 100 percent power in the event the Company is restrained at some power level between 50 and 100 percent. Such restraint could be imposed by the NRC or it could be self-imposed 1
because of some equipment problem.
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moittura carricd over with the cteam, cinc3 it is important to renovo as su:h moisture as possible so as not to endanger the turbine generator. A high noisture carryover could affect design efficiency and turbine longevity.
l Although the Company intends to complete testing at all power levels prior to declaring the plant "in service" if everything goes well, it does not intend to complete the above-referenced warranty testa prior to declaring the plant "in-I service" since these tests are not required by the NRC.
The Staff includes both warranty tests in its criteria as well as the l l
requirement that the plant be operated for 100 continuous hours at full power (95 to 100 percent) to demonstrate the performance of the entire plant at the full power level. The 100-hour test proposed by Staff any or any not be satisfied during the NSSS acceptance test depending on the circumstances.
The Company maintains that the plant need not reach full power in order to be determined "in-service". In addition, the Company argues that the Staff's Criterion 1 is overly stringent since it not only requires that the plant reach full power but requires ths completion of warranty tests. In the Company's view these warranty tests are not necessarily related to a determination of whether the plant is operational and are based solely on the specific contract entered into by the Company and the annufacturer.
With respect to the moisture test, the Company further argues that it should not be required since the Company asserts it has no near term significance with respect to the operability or reliability of the steam generator.
Criterion 2. The preoperational test program shall be successfully completed. -
The preoperational test program consists of a series of tests which verify that plant components and systems fulfill their designed intent, demonstrate proper system and component response to postulated accidents and familiarize plant staff with the plant operations.
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Th3 purpobo cf thic criterin 10 ts dem:nstrate that Comptny pers:nnal ora l
capable of operating the plant in a competent manner and that no hardware problems exist which interfere with reliable operation of the plant. Staff maintains that Criterion 5 in conjunction with Criterion 1 assures reliable plant operations.
The Company objects to Criterion 5 on the ground that it is inappropriate for the Staff to duplicate the role of the NRC. In addition, the Company argues that the reporting requirments for each delay of over 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> is too burdensome. If l such a requirement is imposed on the Company, the Company recommends that it report l
any single event which causes a delay of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> or more in a milestone event or in the overall schedule. The Company asserts that only milestone events are reviewed by management and, therefore, restricting Criterion 5 to milestone events will focus on possibly significant events. Events other than milestone events can be altered at will by test schedulers and do not require management approval. The Company argues that scheduled alterations are inevitable and are not necessarily significant.
Milestone events are designated by black circles and arrows on Exhibit A4, Schedule A.
In addition, the Ccapany contends that the requirement to report each 100-
., hour delay is overly stringent since the NRC requires a,pproval for modification to the test program of delays that exceed 30 days regarding tests occurring at below 50 percent power level and 14 days when the power level exceeds 50 percent.
Company states that it is willing to meet with Staff and other interested parties on a rsgular basis to explain the progress of the start up schedule. The
'. Company is concerned that Criterion 5 in and of itself could delay the "in-service" date because of the time involved in the preparation and Staff review of the information required.
Criterion 6. Exemptions from Criterion 1-5 may be granted or the determination made that the plant is fully operational at some power level less than the rated full power originally proposed
,' for good cause shown.
3 f
Criterion 1. .The UE's Startup Testing Program, which is outlined in Exhibit 14, Schedule A, shall be successfully completed. This shall include a successful uninterrupted run of at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> during which power is furnished to the grid at a level between 95 percent and 100 percent. 100 percent is 3425 Mw thermal with a gross turbine output of 1185.8 MWe.
Since the Moisture Carryover test will demonstrate design efficiency and turbine longevity, the Commission detemines that the test should be completed. The Company is confident that the unit will have a low moisture carryover. Although the Company maintains that the moisture carryover is an efficiency concern rather than a reliability concern and is therefore not a near-tem problem, Company witness did state that a very . great moisture carryover would be quite serious.
The Commission determines that it is appropriate to require the completion of the NSSS warranty test since the test demonstrates the capability of sustained operation at the rated themal output. The Company expects to operate the plant when available at full load and therefore completion of the NSSS test will provide a high level of assurance that the steam supply system can perfom as expected and as warranted by the manufacturer.
If all goes well, the moisture test, the NSSS test and the 100-hour test I
can be completed simultaneously. The Company plans to complete these tests and '
' \
according to the Company's test schedule contained in Exhibit A4, Schedule A, the l tests will be completed ta to 15 days after the completion of power ascension. The Company proposes to declare the plant "in service".when power ascension is complete absent some restriction. In the Commission's opinion, the delay of 14 to 15 days is well worth a high level of assurance that the plant has demonstrated the capability of sustained operations at full power as warranted.
Criterion 2. The Prooperational Test program shall be successfully completed. ,
I Criterion 3 The plant and associated transmission facilities have been tested capable of supplying to the Company's Missouri customers their full share of its rated power and can do so with the single most critical transmission line out of service.
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operations. -
Criterion 6. Exemptions from Criterion 1-5 may be granted or the determination made that the plant is " fully operational" at some power level less than the rated full power originally proposed for good cause shown.
The Commission believes that flexibility is important since these criteria are being established absent evidence of facts regarding the operating experience during start-up testing.
Criterion 7 The plant is supplying electricity to the Company's system with output scheduled by the system load dispatcher. l The Commission has added Criterion 7 to ensure that the electricity is being supplied to customers.
The Commission deterinines that the criteria established herein provide ,
protection to the Company's customers against the risk of paying for a plant that turns out to be seriously defective. In the Commission's opinion the satisfaction of
, Criteria 1 through 5 clearly will provide the greatest assurance that the Callaway Plant is capable of providing safe, adequate, reliable a'nd efficient service.
. Therefore, Criteria 1 through 5 set an optimal standard for determining when the Callaway Plant will be eligible for inclusion in rate base, but are not necessarily the minimum legal standards required to support a finding of " fully operational and used for service" under Section 393 135, RSMo 1978. l
, Prior to receiving any evidence regarding the operating experience of the
.' plant the Cummission is not prepared to make a finding at this juncture that a demonstration of safe and reliable plant operations at some power level less than 100 percent will never constitute " fully operational and used for service" within the meaning of section 393 135, RSMo 1978.
Section 393 135, asMo 1978, prohibits charges based on costs associated with property before the property is fully operational and used for service. The statute does not mandate that such oosts be included in rates upon a minimum showing that the statutory requirements have been met. Therefore, the Commission has Exh5 bit A4, Schedule A constitute tests required under Criterion 1. If Staff and
' Company cannot reach' agreement as to which events constitute tests, the issue should be brought to the Commission's attention.
ORDERED: 4. That this Report and Order shall becces effective on the
, 27th day of August, 1984.
BY THE C0t94ISSION m k.,h A$ L HarveyG(Hubbs Secretary (S E A L)
Steinmeier, Chm., Musgrave, Mueller, Hendren and Fischer, CC., Concur.
C.ortify ocupliance with the provisions of Section 536.080, RSMo 1978.
De,ed at Jefferson City, Missouri, this 22nd day of August,1984.
6 7