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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
[Table view] |
Text
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UNION ELECTRIC COMPANY 1901 GRATloT STREET ST. Louis. Missouri July 6, 1981 ,,, ,,,,,,,,,
JOHN K. .RYAN p, o, g,x g4, v======= .r. wu. ui ou.. .....
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($ &p@9 k-k i
Director of Nuclear Reactor Regulation 'g 6
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U.S. Nuclear Regulatory Commission #
Washington, D.C. 20555 ,
Dear Mr. Denton:
ULNRC-460 DOCKET NUMBERS 50-483 and 50-486 CALLAWAY PLANT, UNITS 1 AND 2 FINAL SAFETY ANALYSIS REPORT
Reference:
NRC letter dated June 10, 1981 from R. L. Tedesco The referenced letter requested additional information concerning the Callaway Plant FSAR. Transmitted herewith are responses to questions in the referenced letter. This information will be formally incorporated into the Callaway Plant FSAR in the next revision. This information is hereby incorporated into the Callaway Application.
Very truly yours, m s mz John K. Bryad
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T10,'OB0191 810706 ) -
PDR ADOCK 05000483x A
PDR{
STATE OF MISSOURI )
) SS CITY OF ST. LOUIS )
John K. Bryan, of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows
.the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By o a J6hn K.' Bryan Sg lice Presiden(t uclear SUBSCRIBED r.nd sworn to before me this 6th day of July, 1981 pf, 17 MARGARET S. HEIDA NOTARY PUBLIC-STATE OF MISSOURI ST. LOUIS COUNTY MY COMMISSION EXPlRES JANUARY 2,1982
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cc: Glenn L. Koester Vice President i Operations ,
Kansas Gas & Electric )
P.O. Box 208 Wichita, Kansas 67201 John E. Arthur Chief Engineer Rochester Gas & Electric Company 89 East Avenue Rochester, New York 14649 A. V. Dienhart Vice President Plant Engineering and Construction Northern States Power 414 Nicollet Mall Minneapolis, Minnesota 55401 Donald T. McPhee '
Vice President Kansas City Power and Light Company 1330 Baltimore Avenue Kansas City, Missouri 64141 Gerald Charnoff, Esq. !
Shaw, Pittman, Potts & Trowbridge 1810 M. Street, N.W.
Washington, D.C. 20036 Nicholas A. Petrick Executive Director SNUPPS 5 Choke Cherry Road Rockville, Maryland 20850 W. Hansen Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077 t
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- SNUPPS-C ITEM 240.lC: Figure 2.1 does not show the location of the inlet nor pipeline (as indicated in the second paragraph of section 2.4.1.1). Revise that figure or provide another figure to show the location as discussed in the
, text.
RESPONSE: The correct reference is Figure 2.1-2, which shows the inlet and pipeline. This correction was included in Revision 3 to the FSAR Addendum, dated May 1981.
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240.1C-1
- SNUPPS-C ITEM 240.2C: Figure 2.1-4 does not show the location of the UHS retention pond (as indicated in the fourth paragraph of section 2.4.1.1). Revise that figure or provide another figure showing the retention pond as discussed in the text.
RESPONSE: The correct reference is Figure 2.1-3, which shows the location of the UHS retention pond. This correction was included in Revision 3 to the FSAR ddendum, dated May 1981.
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SNUPPS-C ITEM 240.3C: The U.S. Army Corps of Engineers hypothetical flood 1 studies for the Missouri River (1970) cited in section 2.4.3 does not appear in the list of references.
Pro, vide the complete title at:d other pertinent
, information. If the referen.:e is to a written communication from the Corps of Engineers, please provide a copy of the communication.
RESPONSE: The reference to data provided by the U.S. Army Corps of Engineers (1979) concerning hypothetical flood studies for the Missouri River cited in Section 2.4.3 of the FSAR Addendum is one of several personal communications received from the Corps of Engineers in 1979 listed in the references for Section 2.4. A copy of the written communication in question is attached.
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. :.y A DEPARTMENT OF THE ARMY
- f. ST. LOUIS DISTRICT, CORPS OF ENGINEERS
. / f5.T f 210 NORTH 12TH STREET
' Ik' ET. LOUIS, MISSOURI 63101 l
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LMSED-HE 2 July 1979 Mr. Gary Lake Dames and Moore Consulting Engineers 605 Parret Street Denver, Colorado 80215
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Dear Mr. Lake:
Reference is made to your telephone conversation on 20 June 1979 with Mr. Gary Dyhouse, Chief, Hydrologic Engineering Section, this office, concerning hypothetical flood information on the Lower Missouri and Mississippi Rivers for use in Callaway Nuclear Power Plant Siting at Mile 115, Missouri River. This letter is intended to supplement that conversation.
This office is not aware of any specific, detailed studies which have been made to identify either a standard project or probable maximum flood on the Lower Missouri or Middle Mississippi Rivers.
The Kansas City District is responsible for the Missouri River and should also be contacted on this subject. Various hypothetical floods were analyzed during the 1950's to define and/or compare
( design discharges for levee grade establishment along the Middle and Lower Mississippi River. The hypothetical flood giving the greatest discharge on the Middle Mississippi River (mouth of the Missouri to mouth of the Ohio River) was designated as Hypothetical Flood 52-A.
This flood is the result of a ecmbination of actual large storm events and was developeo by Corps of Engineers' studies.
Hypothetical Flood 52-A was developed from the combination of the 7-11 May 1943 storm transposed over the Missouri and Upper Mississippi Basins, but with the rainfall decreased 20 percent, followed three days later by the actual 15-20 May 1943 stom over all drainage areas above the latitude of Red River landing, and two days later by the. actual 28-30 June 1928 stom over all areas above Cairo, Illinois. -
The design floods eventually adopted for the Middle Mississippi.
River levee system .were a 50-year and 200-year event for agricultural and urban areas, respectively, un=odified by reservoirs. Hypothetical Flood 52-A was thus used primarily as a comparison with the levee design event.
LMSED-HE 2 July 1979
- Mr. Gary Lake
. The comparison was made by using the Mississippi River Basin physical model (MBM) at Clinton, Mississippi. The flood hydrograph from Hypothetical Flood 52A was introduced at St. Louis and downstream peak water surface elevations would be obtained from model measurements. The effects of various combinations of reservoirs on Mississippi River discharges were to be estimated as well. , These tests, incorporating many actual and hypothetical floods to be analyzed for the Mississippi Basin, were initiated in 1959 and conducted through 1969 After initial testing was underway, it was decided to incorporate portions of the Missouri and Mississippi Rivers upstream of St. Louis. In particular, water surface elevations for hypothetical events on the Missouri River from Sioux City, Iowa, to the mouth were now required. Upon
()
introducing the 52-A hydrographs at the upstream end of the model and at tributary outflow points to the Missouri River and routing flows using the MEM, it was found that a significantly reduced hydrograph resulted at St. Louis as compared to the results using simplified techniques.
The original test data input, from which the Hypothetical Flood 52-A hydrograph was obtained at St. Louis, was developed through the techniques available at that time - rather simplified hydrologic routing methods co=puted and routed by hand to the St. Louis Gage.
It was felt that this difference in hydrographs at St. Louis was due to the inadequacy of the hydrologic routing techniques performed during the 1950's to develop the hypothetical flood hydrograph at St. Louis. To differentiate between these two conditions, the hypothetical flood 52-A (simplified hydrologic routings) was redesignated as M 52-A (routing with MBM).
At meetings the with Loeer Miasissippi Valley Division, Missouri River Division, and St. Louis Dis trict personnel, it was determined that Hypothetical Flood M 52-A was the more accurate estimate of the discharges that could be expected ,from an actual occurrence of this rare flood event. Consequently, the adopted discharges from the hypothetical flood woult be those derived from M 52-A. There is no frequency associated with this hypothetical flood; however, it is felt that it is a reasonable representation of discharges which might be experienced from storms of standard project proportions over the Missouri and Upper Mississippi River Basins. Discharge values for Hypothetical Floods 52-A and M 52-A, along with the flood ,
of record information, are given in the accompanying table. The results for different combinations of possible reservoir conditions are also shown.
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i LMSED-HE 2 July 1979 Mr. Gary Lake I trust the above information will be suitable for your needs. Any further qubstions should be directed to Mr. Gary Dyhouse at (314) 263-5849 Sincerely, t
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1 Incl JACK R. NIEMI As stated Chief, Engineering Division e
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, HYPOTHETICAL FLOODS LOCATION FLOOD E EN END
, Mississippi River at St. Louis, Ho 52-A 1,900,000 1,670,000 1,585,000 Mississippi River at St. Louis, M0 M 52-A 1,380,000 1,180,000 1,080,000 Missouri River at Hermann, Mo M 52-A 980,000 790,000 700,000 Group E-(Existing) - Reservoirs that were existing and under
- construction in 1959, at the start of model testing.
Group N (Near future) - Reservoirs scheduled for construction and expected to be operable by 1970, based on study and construction A schedules available in the late 1950's.
Group D (Distant future) - Reservoirs that are expected to become operable after 1970 that will complete the ultimate system of reservoirs. Reservoirs in Group D vere estimated in the late 1950's, based on upcoming planning studies.
Group EN is considered to best represent the current condition of the Mississippi River. The actual reservoirs in operation today include a few from the D group. Some reservoirs in the N group have not been constructed.
FLOODS OF RECORD LOCATION YEAR DISCRARGE (C.F.S.)
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Mississippi River at St. Louis, MO 1844 1,300,000 Mississippi River at Alton, IL 1973 535,000 Missouri River at Hermann, MO 1844 892,000 The 1844 values were estimated in the early 1900's based on measurements from the 1903 flood at Chester and Thebes, Illinois.
The values at St. Louis and at a ensann are considered to be rough estimates at best and may be conservative. The highest discharge measured by modern gaging techniques at these two points occurred in 1973 at St. Louis (852,000 c.f.s.) and in 1951 at Hermann (618,000 -
c.f.s.).
SNUPPS-C s
ITEM 240.4C: a) Your analysis of forces on the UHS retention pond
, safety related structures is based upon thermal expansion of an ice layer with a thickness that has a recurrence interval of 100 years (1 percent l chance per year). This is not an adequate design basis for safety related structures with respect to natural phenomena as required by General Design Criterion 2 of 10 CFR 50 Appendix A and does not meet Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Power Plants." Also, no basis for the assumed temperature rate of rise at 5 F per hour is provided.
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Provide an analysis to determine the upper limit of ice thrust forces that could be exerted on safety related structures in the UHS retention pond.
Provide all historical data (and their source) used in your analysis. Provide details of any frequency analyses performed and describe any joint probability considerations between ice layer thickness and rate of temperature rise. If the mechanical and/or heat transfer prope ties of the ice layer are used to limit the thrust forces, provide the basis for all coefficients assumed.
/ b) If all safety related structures in the UHS retention pond cannot be shown to withstand the upper limit of ice thrust forces determined in response to a) above, discuss procedures to be included in the plant technical specifications to limit the thrust forces, protect the structures, or shut the plant down during times of ice buildup.
RESPONSE: a) Use of the 100 year ice thickness is considered to be an adequately conservative design condition.
The forces associated with the 100 year ice condition have been used as normal live loads (see Section 3.8.4.3.1) and have been combined separately with extreme environmental loads (see Table 3.8-2) such as PMP, SSE, etc., to demonstrate that the design is conservative. To design for conditions more severe than the 100 year ice condition in combination with extreme environmental events would not significantly add to the conservatisms already included in the design and is therefore not justified. The 100 year ice condition is adequately conservative such that the design is in compliance with the requirements of General Design Criterion 2 and the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Power Plants."
240.4C-1
SNUPPS-C 4
i I The assumed temperature rate of rise of 5 F per
' hour for ice thrust is based on the recommendations of Cold Regions Research and Engineering Laboratory (Ref. 1). The reference states that in most cold
, regions the mean rise of air temperature rarely l exceeds 5 F per hour for extended periods of time.
Some extremes in temperature rises are reported in
, the literature but because of their very short durations they are not representative of the temperature fluctuations inside the ice sheet itself which has a great thermal inertia.
b) All safety related structures in the UHS retention pond are designed to withstand the ice thrust force as described above.
REFERENCE:
- 1. Michael, B., " Ice Pressure on Engineering Structures." Cold Regions Science and Engineering Monograph III-B1 b, June, 1970.
4 240.4C-2
SNUPPS-C s
ITEM 240.5C: Provide the basis for the wind speeds used in the computation of drag forces on the ice surface in the ultimate heat sink retention pond. Justify that the severity meets the intent of General Design Criterion 2 and Position 2 of Regulatory Guide 1.27. Provide the drag coefficient used and the thrust forces calculated.
Discuss the impact forces that would result if the pond >
was only partially covered by ice and ice sheets were driven by wind into the ESWS pumphouse. Provide the basis for all assumptions used in your analysis.
RESPONSE: The drag force due to wind acting on the ice surface in the Ultimate Heat Sink Retention pond is determined considering the different winter wind speeds at the site. Based on climatological data collected at Columbia, Missouri during the years 1931 through 1960 and 1970 through 1973, the fastest wind speeds for the months of December, January, and February are 58, 56, and 45 mph, respectively (based on 1 minute maximum duration) (FSAR Table 2.3-7). The mean monthly wind speeds for these months are 10.7, 10.7, and 11.9 mph, respectively.
The drag coefficient is evaluated considering turbulent flow over ice (smooth surface) and using the figures given in Schlicting (Ref. 1) and Vennard (Ref. 2). The average drag coefficient is 0.002. The drag force computations assume that the entire pond surface is covered with ice and the the entire thrust force is transmitted to the pumphouse, with a frCatal contact width of 31.5 ft. The wind drag forces on the retention pond outlet structure are based on a contact with 7 ft. of concrete at the normal operating water level of 836 f t.
, The actual wind drag forces exerted on the pumphouse '
l and outlet structure due to a 40 mph wind acting on a two foot thick layer of ice are 24 and 99 lbs/ft ,
respectively. The Callaway FSAR Site Addendum describes the method by which the wind induced ice force is combined with other forces to determine the structure section strength required to resist design loads. This information is in Section 3.8.4.3.1 and Table 3.8-2. Because the magnitude of the wind induced ice force is very small compared to the other forces, more severe wind conditions were not evaluated.
The effect of impact forces on the pumphouse and outlet structure due to wind driven ice or ice sheets has never been considered as a design basis. However, the pumphouse and outlet structures have been designed for natural phenomena that produced more severe effects than wind driven ice, i.e., SSE, tornado, missiles, i
240.5C-1
SNUPPS-C s
etc. The design of these structures is
' conservative with respect to the SSE and- tornado missiles and therefore is expected to withstand the effects of the wind driven ice.
REFERENCES:
- 1. Schlicting, H., " Boundary Layer Theory," McGraw Hill Book Company, 1968.
- 2. Vennard, J.K., " Elementary Fluid Mechanics," John Wiley and Sons, Inc., 1961.
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ITEM 240.6C: Provide additional details regarding the determinat.on i of the probable maximum wind for determination of t ve action on the UHS retention pond. Describe the origin of the data used in the analysis and show the maximum likelihood frequency estimate and 95% confidence interval. Discuss the effect of recent regional windspeed data (collected since Thom's report) on the frequency estimate.
RESPONSE: The probable maximum wind was determined based on the method of Thom (1968). Thom used meteorological data collected over a 21-year period from 150 monitoring stations to provide isotachs of the 0.50, 0.10, 0.04, 0.02, and 0.01 quantiles for the annual extreme fastest wind speed for the United States. Thom then provided an empirical method to use these data to determine the fastest wind speed for other quantiles at any U.S.
location. This method was used to determine the fastest wind speed likely to occur at the 0.001 quantile; the 1000-year mean recurrence interval.
The data provided by Thom do not allow the calculation of the 95 percent confidence interval for estimates of wind speed at this quantile, s Since Thom's isotach's and statistics are based on a specific 21-year data base, more recent data cannot be taken into account, except as a comparison of actual extreme speeds with those predicted by Thom.
As an example, the fastest mile wind speed recorded by the National Weather Service station at Columbia, Missouri from August 1889 through 1979 (a 90-year period) was 63 miles per hour. This compares with values determined from Thom's method of 72 miles per hour (50-year recurrence interval) and 85 miles per hour (100-year recurrence interval).
REFERENCES:
Thom, H.C.S., 1968, New distribution of extreme winds l in the United Stated, in Journal of structural l
division. Proceedings of the American Socloty of Civil Engineers, vol. 94, no. st. 7 (July).
U.S. Departmen' of Commerce, 1979, Local climatological data, annual summaries for 1979. National Oceanic and Atmospheric Administration, Asheville, Nerth Carolina.
240.6C-1
. SNUPPS-C ITEM 240.7C: a) Provide details of your transient analyses of temperature and water supply for the UHS cooling tower system during the critical 30-day period as discussed in Position 1 of Regulatory Guide 1.27.
b) Discuss a pre-operational testing program and the analysis of the resulting data to be used to verify the conservation of estimates made in response to part a) above.
RESPONSE: a) The following details of the UHS transient analysis supplement the information provided or referenced in Table 9.2-5:
- 1. Power block heat rejection rates and emergency make-up water requirements are provided in Standard Plant Section 9.2.5, including Tables 9.2-17 and 9.2-18 and Figures 9.2-6 through 9.2-11.
- 2. Meteorological data are discussed in Table 9.2-5.
- 3. Cooling tower performance data are provided in Table 9.2-4.
- 4. Transient analysis conservatism and design allowances for water inventory are discussed in Section 9.2.5.2.2. These design allowances are based on the original retention pond transient analysis. Since that time, it has been determined that the UHS cooling tower is designed to maintain 95 F cold water temperature with 81 F entering wet bulb temperature rather than 81 F ambient wet bulb temperature as committed to in the PSAR. The manufacturer estimates that under worst case conditions tower recirculation (increase in inlet air temperature) will not exceed 4 F, and cold water temperature with 81 F ambient (85 F entering) wet bulb temperature will not exceed 97.4 F. This represents a cold water elevation of 2.4 F. However, the following conservatisms in the original analysis support the overall design bases for the UHS.
- a. The minimum heat transfer analysis produced a maximum pond outlet temperature of 89.5 F. Indicating a 5.5 F margin between ESW design temperature of 95 F.
240.7C-1
SNUPPS-C
- b. The original tower analysis assumes a constant 95 F pond outlet temperature throughout the 30 day period for establishing cooling tower inlet temperatures. This represents a margin of s 6 F to 19 F throughout the 30 day period.
The range of 6 F to 19 F is based on calculated pond outlet temperature from the original analysis.
- c. Cooling tower evaporation loss and discharge water temperatures were calculated considering both units in LOCA.
- d. The original analysis indicated a 25 percent margin in UHS retention perd volume.
- e. Wind speeds during the minimum heat transfer periods average less than 5 MPH (never exceeding 7.5 MPH). This indicates elevation of entering temperature due to recirculation effects will be less than the manufacturer's estimate of 4 F with 10 MPH
_ cross wind.
A final analysis incorporating updated cooling tower performance and power block heat loads will be performed. Based on the above reasons, it is expected that this analysis will indicate a significant margin on UHS volume. The methodology for the final analysis will be available in September 1981.
b) The UHS cooling tower system performance test data will be utilized to verify the conservatism of the information used as the basis for the final transient analysis. Details for the test are under Preparation and will be included in the test abstracts for the system (Chapter 14.0 of the Power Block FSAR). The abstracts will be available in September 1981.
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240.7C-2
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i ITEM 249.8C: - Discuss provisions to replace make-up water in the UHS i retention pond in the event that the Missouri River intake and pumping system should remain inoperable
! after 30 days.
RESPONSE: Section 9.2.5.3 has been revised to describe provisions i for trucking in make-up water should the Missouri River l intake and pumping system remain inoperable after 30 days.
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SNUPPS-C Regulatory Guide 1.27 of the single failure of man-made structural features does not apply. The UHS pond is designed to withstand the most severe natural phenomena expected. See Section 2.4.3 for coincident wind wave activity and Section 2.4.5 for surge and seiche sources. Slope stability is discussed in Section 2.5.5. The UHS pond is so located that its function is not to be affected by postulated accidents incurred by traffic on the plant railroad or vehicle access road or other site-related events.
The nearest nonseismic Category I structure to the seismic Category I ultimate heat sink cooling towers is the fire pumphouse and portable ,
water plant located approximately 90 feet northeast of the unit one l
tower, as shown in Figure 1.2-1. A postulated structural failure of this nonseismic Category I building would not impose a hazard to the cooling towers since the tower enclosures are designed as tornado-resiqtant structures.
Conformance with Regulatory Guide 1.27 is tabulated in Table 9.2-5.
A single failure analysis for the UHS is contained in Table 9.2-6.
SAFETY EVALUATION THREE - The UHS retention pond normal capacity is 55.35 acre-feet. Less than 44 acre-feet are needed for 30 days of makeup water for the two units conservatively assumed to be experiencing a LOCA Under maximum evaporation conditions for this period. The total pond water volume remaining after 30 days is 11.8 acre-feet. The usable portion of this volume is 10.7 acre-feet, which is above the ESWS pumphouse forebay sill. This margin is 25 percent of the total water volume requirement. Adequate submergence is provided for the ESW pumps when the retention pond is at the minimum water level.
In the event normal plant facilities are not in operation within 30 days (plus the number of days for depleting the 25 percent margin in the UHS pond).after an emergency shutdown, approximately 22 acre-feet of water are available from the water treatment plant clarifiers.
This water can be pumped into the UHS retention pond by portable pumps for UHS heat dissipation purposes. In the event the clarifiers I have been damaged, water will be trucked from offsite. An adequate l number of 40,000 to 45,000 pound capacity bulk liquid carriers are l available in the metropolitan area. These trucks would be mobilized I to obtain water from Fulton (10 miles), Jefferson City (25 mi'es), or l Columbia (32 miles). In the extremely unlikely event water would i not be available from any of the above cities, portable pumps will be 1 obtained and water can be pumped from the Missouri River (6 miles) to I fill the trucks.
9.2.5.4 Testing and Inspections The UHS is designed to include the capability for testing through the full operational sequence that brings the system into operation for reactor shutdown and for loss-of-coolant accidents, incitding 9.2-17
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ITEM 240.9C: State whether any pemanent underdrain or ground water dewatering systems are installed, being constructed or planned at the plant site. If so, provide the information called for in Branch Technical Position
. HMB/GSB-1, " Safety-Related Permanent Dewatering Systems."
RESPONSE: As discussed in Section 2.4.13.5 and Section 3.4, the normal water table at the plant site is 10 to 30 feet below grade and all the safety-related structures are designed for full hydrostatic loading to El, 840 ft.
MSL (Standard Plant Elevation 1999.5 ft.) which is the plant grade. No permanent underdrain or gound water dewatering systems are installed or planned at the site.
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