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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 l seos onArior sTanzT sr. Louis, Miesount JOHN M, SRYA M ,30 g43 i m..... August 19, 1981 er. aui = ouai..i.. !
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Mr. Harold R. Denton Director of Nuclear Reactor Regulation
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! U. S. Nuclear Regulatory Commission ( , ,: '=
Washington', D.C. 20555 ~;
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Dear Mr. Denton:
ULNRC- 4 8 3 i
DOCKET NUMBERS 50-483 AND 50-486 CALLAWAY PLANT, UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT On May 14, 1981, a meeting was held between the NRC Power SysteFas Branch and the GNUPPS utilities concerning auxiliary systems. This letter serves to close out items 430.2,
, 430.3.3, 430.3.4, and 430-15 and also provides a description of I the hydrogen storage system (item 430.43). This information was previously given to the NRC project manager for Callaway, but was not transmitted formally.
l This information will be incorporated into the Callaway l Plant FSAR in the next revision. This information is hereby l incorporated into the Callaway Application.
, Ver truly yours, i
(
db Jo n K. Bryan
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l 8108210147 ts10819 N PDR ADOCK 05000460=
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y 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.
1 /
By e .- f geg i
. Rryan f ice Presidenti) uclear SUBSCRIBED and sworn to before me this 19th day of August, 1981 N# Vin A; <. L
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F.1ARG ARET S. HElDA HOTARy ILEt;;_3tAyl Of f.flSSOURI S T. Lolin; coun;y MY CWW33'0's t J. f $ jq.UMY t MR2
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9 cc: Glenn L. Koester Vice President 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 i 1330 Baltimore Avenue Kansas City, Missouri 64141 Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 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 i
~
. / ;
4 been removed, and all valves are in the proper position to permit a manual start of the equipment.
After the unit has been satisfactorily started and load tested, return the unit to ready automatic standby service and under the control of the control room operator.
, Provide a dir,cussica of how the above requirements have been implemented in the emergency diesel generator system design and how they will be considered when the plant is in commercial operation, i.e., by what means will the above requirements be enforced.
Response: For responses to Item 430.3.1 and 430.3.2, refer to Standard Plant P.esponses.
- 3. The Callaway approach to Emergency Diesel Maintenance will adequately cover these concerns.
Administratively, maintenance results of all safety-related components will be approved by the Superintendent, Maintenance, or his designee. In addition, it is intended that completion documents of significant maintenance activities (and certainly Emergency Diesel Maintenance is significant) be reviewed by cognizant engineers. The two 3 , individuals are responsible to take any action j necessary to ensure optimum operability. Files will i be built containing history of repairs.
4 i This will ensure that if a component malfunctions repeatedly, the proper corrective action will be taken.
- 4. Maintenance Procedures will provide for a final equipment check upon completion of repairs or maintenance.
I
-f 430.3-2
. . . _= . _ . - . .
, . . . =. .
, , SNUPPS-C Item 430.15 You state in section 9.5.4.3 that diesel oil is '
(9.5.4) normally delivered to the site by tanker truck and
' if road transportation is unavailable, it can be delivered onsite by railroad tanker. Discuss per sources where diesel quality fuel oil will be available and the distances required to be travelled from the source to the plant.- Also discuss how fuel oil will be delivered onsite under extremely unfavorable environmental conditions including maximum probable
- flood conditions.
i Response: The source of fuel oil has not been contracted at this time. (Iowever, there are multiple access routes to the
{ site. The Callaway plant is sited above the PMF level, j
and it is not anticipated that all access routes would
,' be blocked for an extended period of time to preclude fuel delivery as needed. Some possible source of fuel j
oil for the Callaway Plant and the distances to these 4
sources are as follows:
J. D. Frame Oil Co.
Fulton, Missouri 14 miles l Tri-County Oil Co.
Jefferson City, Missouri 34 miles MFA Oil Co.
Columbia, Missouri 40 miles .
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430.15-1 i
- SNUPPS-C l
i The storage vessels are refilled from an over-the-road trailer as required. The anticipated refill cycle is four weeks.
l The storage tanks are of the horizontal cylindrical type and
! are located approximately 350 feet from the power block.
l A fire hydrant and hose house are located within 200 feet of the gas storage area.
2.2.1.2.3.4 Hydrogen l l Refer to Section 2.2.2 for a description of the hydrogen I system.
l l 2.2.1.2.3.5 Carbon Dioxide Carbon dioxide is stored on site as a pressurized refrigerated liquid in an insulated storage vessel. It is vaporized elec-trically as required and piped to the power block through l Schedule 80 steel pipes laid in the same vented masonry trench l as the hydrogen pipes. These supply lines are fitted with
! pressure relief valves.
The storage vessel is refilled with liquid from an over-theroad trailer as required. The anticipated refill cycle is four weeks.
The storage tank is of the horizontal cylindrical type. The l axes are not directed towards any buildings within the plant
( site.
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2.2-3 Rev. 4 l
/81
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- SNbPPS-C s
I hazardous commodity was shipped per day, _nd the maximum quan- ;
- tity likely to be transported on any one train was between 30 ,
j and 40 cars (Janovec, 1979). The only spur or siding within a !
5-mile radius of the site is one leading directly north from I the rail line to the plant site. !
I Although chlorine was reported to 'have been transported en the l i railroad in previous years, none was transported in 1978. i
- Chlorine is a commodity that is not shipped on a regular basis !
] and no projections of future shipments can be made (Doyle, {
l 1979). !
l 2.2.1.5 Water Transportation !
i l The Missouri River, approximately 5 miles southeast of the a site, is a transportation artery for barge traffic. Maximum ,
cargo loads are a function of barge size and river depth. The ,
largest cargo load reported by Sioux City and New Orleans Barge !
Lines was 1,600 short tons during a period of seasonally high I' water levels. Maximum cargo loads are usually 1,200 short
- tons, and the maximum number of barges in a single tow as many -
an 8 to 10 depending on barge size and water (Hynes,
- j levels 1979). Nine hundred fifty-five thousand four hundred and I eighty-three (955,483) tons of hazardous commodities, listed in ;
j Table 2.2-5, were shipped on the Missouri River between Kansas
] City and St. Louis in 1979. Forty-one thousand nine hundred ,
i and seventy-four (41,974) passengers used the river between t Kansas City and the mouth of the river in 1977 (U.S. Army Corps l
, of Engineers, 1977).
2.2.1.6 Pipelines j No pipelines or tank farms are located within 5 miles of the site. The nearest pipeline, Williams Brothers' 8-inch diameter products pipeline, approximately 8 miles north of the site, runs from St. Charles to Columbia, Missouri, and carries refined petroleum products. The pipeline route is shown on
, Figure 2.2-3 (Steuerwalz, 1979).
a i 2.
2.2 DESCRIPTION
S i l The description of products (other than hydrogen) manufactured, stored, or transported offsite as well as the maximum quan-tities of hazardous materials likely to be processed, stored, or transported on site, are fully described in Section 2.2.1. ;
llazardous materials are listed in Tables 2.7-1, 2.2-4, and 2.2-l 5. The description of the hydrogen syste follows.
1 1
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1 2.2-9 Rev. 4
/81 i
- SNUPPS-C l 2.2.2.1 Hydrogen System l Tha hydrogen system (HS) is designed to provide low pressure I gaseous hydrogen continuously to the turbine and auxiliary l buildings for volume control tank purge, generator fill and I generator leakage make-up. This system description relates I only to components of the site HS outside the Standard Power l Blocks.
l 2.2.2.1.1 Design Basis l 2.2.2.1.1.1 Safety Design Basis l The HS has no Safety Design Basis.
l 2.2.2.1.1.2 Pcwer Generation Design Basis l The HS is designed to provide hydrogen continuously to tl.e l Standard Power Block as required for components related to I power generation.
l 2.2.2.1.1.3 Codes and Standards l The following codes av.5 standards are used as guidelines in the l design of the Hydroger. System and equipment and, where required I by law, the system and equipment conform to the applicable I standards:
I a. National Fire Protection Association (NFPA)
I b. Occupational Safety and Health Standards (OSHA)
I c. American Nuclear Insurers (ANI) l 2.2.2.1.2 System Description l 2.2.2.1.2.1 Location l The location of the US bulk storage fa ility and the dis-l tribution piping outside the Standard Power Blocks are shown on l Figure 2.2-4. A flow diagram of the HS is s town in Figura 2.2-l 5. The hydrogen storage system is located plant South of and I approximately 350 feet away from the Power Block. The axes of I the pressure vessels are oriented plant East-West and are not I directed at any of the buildings within the plant site. Due to l the distance between the Power Block and the hydrogen storage l area a fire in the storage area does not pose any hazard to l systems required for safe shut-down. The hydrogen storage sys-l tem for each unit will sit en its own grade-level concrete I foundation slab and the rest of ti.e fenced gas storage area I will be rock-covered and kept brush free to prevent any brush I fire from impinging on the storage tanks. There is a fire hy-1 drant and hose house within 160 feet of the storage facility.
2.2-9a Rev. 4
/81
SNUPPS-C ;
I 2.2.2.1.2.2 Facilities l The HS consists of multiple pressure vessels with l appurtenances, pressure regulators, excess flow control valves, l unloading facilities and distribution lines to each turbine l building.
l 2.2.2.1.2.2.1 Storage l The hydrogen is stored in gaseous form at a maximum pressure of l 2250 psig and the design usable storage capacity is 95,600 scf I for one Power Block. This capacity is divided between the l primary section, consisting of six high pressure tubes and an l identical six-tube secondary section. The secondary section i does not provide gas until the useful capacity of the primary I section has been consumed. The primary and secondary sections I are independent in the sense that a problem in one section will I not affect the operation of the other. Each high pressure I storage tank is fitted with a rupture d' e pressure relief l device. There are two pressure relief valves in the high pres-I sure header between the storage tanks and the pressure I regulator, and two more in the low pressure piping downstream l of the regulator.
l 2.2.2.1.2.2.2 Supply l The storage vessels will be refilled from an over-the-road tube l trailer as required. The anticipated refill cycle is four I weeks. The truck unloading stanchion will have equipment to I electrically ground the trucks to the site grounding system to I which also the control cabinet, piping, steel franiing and the I storage tubes are connected. The unloading stanchion will be l provided with a check valve, a shut-off valve, a purge valve l and a pressure regulator. The purge gas will be piped away I from the operator and vented upwards to the atmosphere. The I open end of the purge line will be protected against the en-l trance of the precipitation, dust and other debris.
l 2.2.2.1.2.2.3 Transfer and Distribution l The pressure regulators reduce the pressure of the gas to the l levels required by the power blocks. The gas is piped to the l power blocks in Schedule 80 carbon steel pipes laid in ven-I tilated masonry surface trenches wherever possible but buried -
l when it is necessary to cross roads, drainage ditches and other l interferences. An excess flow valve is provided in the line to I cach unit to shut off the supply of hydrogen at excessively I high flow rates. The pressure relief valves fitted to the sup-1 ply lines are 200 feet from the oxygen pressure relief valves l and vent 10.5 feet above ground. The hydrogen piping is laid I in the same trench as the carbon dioxide piping.
2.2-9b Rev. 4
/81 2
SNUPPS-C l 2.2.2.1.2.2.4 Source /
l Union Electric has contracted with a reputable and qualified I company, experienced in the handling of this product, to I replenish the 3:orage vessels as required.
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- 93. Ga5 STORAst ARIA UNION ELECTRIC COMPANY CALLAWAY PLANT UNITS 1 AND 2 FINAL SAFETY ANALYSIS REPORT FIGURE 2.2 -4
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