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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl 1999-09-20
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl ML20205H4051999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3891999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1).Page 2 in Third Amend Power Sales Contract of Incoming Submittal Not Included ML20205A9441999-03-25025 March 1999 Forwards VEGP Unit 1 Cycle 9 Colr,Per TS 5.6.5.d ML20205H3811999-03-24024 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3621999-03-22022 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81, as Requested IAW 10CFR50.75(f)(1) ML20204G4361999-03-18018 March 1999 Forwards Summary Rept of Present Level & Source of on-site Property Damage Insurance Coverage for Vegp,Iaw Requirements of 10CFR50.54(w)(3) ML20204C0591999-03-17017 March 1999 Forwards Rev 0 to WCAP-15160, Evaluation of Pressurized Thermal Shock for Vegp,Unit 2 & Rev 0 to WCAP-15159, Analysis of Capsule X from Vegp,Unit 2 Reactor Vessel Radiation Surveillance Program ML20207K9551999-03-11011 March 1999 Forwards Response to Rai,Pertaining to Positive Alcohol Test of Licensed Operator.Encl Info Provided for NRC Use in Evaluation of Fitness for Duty Occurrence.Encl Withheld,Per 10CFR2.790(a)(6) ML20207L9721999-03-10010 March 1999 Forwards Rev 15 to EPIP 91104-C of Manual Set 6 of Vogtle Epips.Without Encl ML20207B0191999-02-25025 February 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 980701-1231,IAW 10CFR26.71(d) 05000424/LER-1998-009, Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 9812291999-01-27027 January 1999 Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 981229 ML20199F7701999-01-13013 January 1999 Submits Revised Response to RAI Re Licensee 980713 Proposed Amend to Ts,Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Protection Channels. Corrected Copy of Table,Encl ML20199F7981999-01-13013 January 1999 Forwards Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage. Change Bar in Margin of Affected Pages Denotes Changes to Rept ML20199G1381999-01-13013 January 1999 Forwards Copy of Permit Renewal Application Package for NPDES Permit Number GA0026786,per Section 3.2 of VP Environ Protection Plan 05000424/LER-1998-007, Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.731999-01-13013 January 1999 Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.73 ML20198F6131998-12-18018 December 1998 Forwards Revised Certification of Medical Exam Form for License SOP-21147.Licensee Being Treated for Hypertension. Util Requests That Individual License Be Amended to Reflect Change in Status ML20198L6631998-12-18018 December 1998 Forwards Amend 37 to Physical Security & Contingency Plan. Encl 1 Provides Description & Justification for Changes & Encl 2 Contains Actual Amend 37 Pages.Amend Withheld,Per 10CFR73.21 ML20198D9291998-12-16016 December 1998 Forwards Requested Info Re Request to Revise TSs Elimination of Periodic Pressure Sensor Response Time Tests & Elimination of Periodic Protection Channel Response Time Tests ML20198D9991998-12-16016 December 1998 Forwards Responses to 980916 RAI Re Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations ML20198D8171998-12-14014 December 1998 Forwards NRC Form 396 & Form 398 for Renewal of License OP-20993.Without Encls ML20206N3051998-12-0808 December 1998 Submits RAI Re Replacement of Nuclear Instrument Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys 1999-09-20
[Table view] Category:UTILITY TO NRC
MONTHYEARELV-02056, Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam1990-09-0606 September 1990 Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam ELV-01599, Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator1990-09-0404 September 1990 Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator ELV-02059, Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B1990-08-30030 August 1990 Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B ELV-01956, Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request1990-08-30030 August 1990 Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request ELV-02050, Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required1990-08-30030 August 1990 Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required ELV-02028, Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d)1990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d) ELV-02022, Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld1990-08-22022 August 1990 Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld ELV-02027, Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively1990-08-20020 August 1990 Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively ELV-01973, Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical1990-08-14014 August 1990 Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical ELV-01918, Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion1990-08-0303 August 1990 Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion ELV-01943, Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned1990-07-27027 July 1990 Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned ELV-01949, Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable1990-07-26026 July 1990 Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable ELV-01500, Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities1990-07-25025 July 1990 Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities ML20055H6441990-07-23023 July 1990 Submits Summary of Snubber Types & Sample Plans for Functional Testing to Be Performed During Sept 1990 Outage ML20044B0311990-07-13013 July 1990 Forwards Vogtle Electric Generating Plant Unit 1 Reactor Containment Bldg 1990 Integrated Leakage Rate Test Final Rept. ML20044B1541990-07-12012 July 1990 Responds to NRC 900612 Ltr Re Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Eop Step Deviation Documents to Be Upgraded,Adding More Justification & Temporary Change Issued to Correct EOP Deficiencies ELV-01867, Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered1990-07-12012 July 1990 Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered ML20055F1651990-07-0909 July 1990 Forwards Comments Re NUREG-1410 ELV-01858, Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete1990-07-0606 July 1990 Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete ML20044A8851990-07-0606 July 1990 Forwards Response to NRC Question on Steam Generator Level Instrumentation Setpoints,Per Revised Instrument Line Tap Locations.Tap Location Will Be Changed from Above Transition Cone to Below Transition Cone ELV-01834, Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21)1990-06-28028 June 1990 Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21) ML20044A2791990-06-25025 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Indicating Status of Each Generic Safety Issue Encl ML20043J0171990-06-22022 June 1990 Discusses Corrective Actions for Plant Site Area Emergency, Per 900514 Ltr.Jacket Water High Temp Switches Calibr for Diesel Generators,Using Revised Calibr Procedure ML20043H3061990-06-15015 June 1990 Forwards Rev 3 to ISI-P-014, Inservice Insp Program, for Review & Approval,Per Tech Spec 4.0.5 Re Surveillance Requirements.Rev Includes Withdrawal of Relief Requests RR-45,47,48 & 54 ML20043G2071990-06-12012 June 1990 Forwards Amend 18 to Physical Security & Contingency Plan. Amend Withheld (Ref 10CFR73.21) ML20043G1021990-06-0606 June 1990 Requests Temporary Waiver of Compliance from Requirements of Action Statement 27 of Tech Spec 3.3.2 for Period of 6 H When Two Operating Control Room Emergency Filtration Sys Trains Shut Down for Required Testing ML20043E6901990-06-0505 June 1990 Forwards Rev 12 to Emergency Plan & Detailed Description & Justification of Changes.W/O Rev ML20043G7651990-06-0505 June 1990 Forwards Rev 13 to Emergency Plan & Description & Justification of Changes ML20043B5991990-05-25025 May 1990 Forwards Scope & Objectives Re 1990 Annual Emergency Preparedness Exercise to Be Conducted on 900801 ML20043B5981990-05-24024 May 1990 Responds to Violations Noted in Insp Rept 50-424/90-05 on 900217-0330.Corrective Actions:Locked Valve Procedure Revised to Eliminate Utilization of Hold Tag on Valves Required by Tech Specs to Be Secured in Position ML20043B6291990-05-22022 May 1990 Forwards Rev 5 to ISI-P-008, Inservice Testing Program, Per Tech Specs 4.0.5 Re Surveillance Requirements & Generic Ltr 89-04 ML20043B6351990-05-22022 May 1990 Forwards Rev 2 to ISI-P-016, Inservice Testing Program, Per Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. ML20042H0601990-05-14014 May 1990 Forwards Summary of Corrective Actions for 900320 Site Area Emergency Due to Loss of Offsite Power Concurrent W/Loss of Onsite Emergency Diesel Generator Capability.Truck Driver Disciplined for Lack of Attention ML20042G7301990-05-11011 May 1990 Forwards Revised Pages for May 1989,Jan & Mar 1990 Monthly Operating Repts for Vogtle Electric Generating Plant,Units 1 & 2.Revs Necessary Due to Errors Discovered in Ref Repts ML20042E2911990-04-18018 April 1990 Forwards Amend 17 to Security Plan.Amend Withheld (Ref 10CFR2.790) ML20042E7481990-04-0909 April 1990 Requests Approval to Return Facility to Mode 2 & Subsequent Power Operation,Per 900320 Event Re Loss of Offsite Power Concurrent W/Loss of Onsite Emergency Diesel Generator Capability ML20012E9001990-03-28028 March 1990 Provides Supplemental Response to Station Blackout Rule,Per NUMARC 900104 Request.Mods & Associated Procedure Changes Identified in Sections B & C W/Exception of Mods to Seals Will Be Completed 1 Yr from Acceptance of Analysis ML20012E8581990-03-28028 March 1990 Suppls Response to NRC Bulletin 88-010,Suppl 1 Re Traceability Reviews on Molded Case Circuit Breakers Installed in safety-related Applications.All Breakers Procured & Installed in Class 1E Equipment Reviewed ML20012E9761990-03-27027 March 1990 Requests Withdrawal of Inservice Insp Relief Requests RR-45, RR-47,RR-48 & Conditional Withdrawal of RR-54 Based on Reasons Discussed in Encl,Per 900206 Conference Call ML20012D8561990-03-22022 March 1990 Submits Special Rept 1-90-02 Re Number of Steam Generator Tubes Plugged During 1R2.One of Four Tubes Exceeded Plugging Limit & Required Plugging.Remaining Three Tubes Plugged as Precautionary Measure.No Defective Tubes Detected ML20012D6641990-03-22022 March 1990 Provides Followup Written Request for Waiver of Compliance to Make Tech Spec 3.04 Inapplicable to Tech Spec 3.8.1.2 to Permit Entry Into Mode 5 W/Operability of Diesel Generator a & Associated Load Sequencer Unverified ML20012D3681990-03-19019 March 1990 Forwards Proprietary & Nonproprietary Suppl 2 to WCAP-12218 & WCAP-12219, Supplementary Assessment of Leak-Before-Break for Pressurizer Surge Lines of Vogtle Units 1 & 2, Per 900226 Request.Proprietary Rept Withheld (Ref 10CFR2.790) ML20012D3401990-03-19019 March 1990 Submits Response to 891121 Request for Addl Info Re Settlement Monitoring Program.Current Surveying Procedures Used by Plant to Monitor Settlement of Major Structures Outlined in Procedure 84301-C.W/41 Oversize Drawings ML20012D6631990-03-15015 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in Lwrs.Overfill Protection Sys Sufficiently Separate from Control Portion of Main Feedwater Control Sys & Not Powered from Same Source ML20012C4681990-03-0606 March 1990 Provides Summary Rept of Property Damage Insurance Levels, Per 10CFR50.54(w)(1) ML20012B2891990-03-0606 March 1990 Forwards Plant Pipe Break Isometrics,Vols 1 & 2 & Advises That Encl Figures Have Been Revised to Be Consistent W/Pipe Analysis in Effect at Time That Unit 2 Received Ol,Including Revs Through 890930.W/309 Oversize Figures ML20012B2421990-03-0606 March 1990 Forwards Cycle 3 Radial Peaking Factor Limit Rept & Elevation Dependent Peaking Factor Vs Core Height Graph ML20011F5291990-02-26026 February 1990 Withdraws 881107 Proposed Amend to Tech Spec 3.8.1.1, Revising Action Requirements for Inoperable Diesel Generator to Clarify Acceptability of Air Roll Tests on Remaining Operable Diesel Generator ML20011F5261990-02-26026 February 1990 Forwards 1989 Annual Rept - Part 1. Part 2 Will Be Submitted by 900501 ML20011E8911990-02-12012 February 1990 Advises That Hh Butterworth No Longer Employed by Util 1990-09-06
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F Georgia Fbwer Company
. Fbst Offic] Box 282 Waynesborn Georgi 3 30830 Telephone 404 554 9961 404 724-8114 Southern Company Services, Inc.
Fbst Office Box 2625 Birmingham, Alabama 35202 Telephone 205 870-6011 Vogtie Proj.ect August 11, 1986 Director of Nuclear Reactor Regulation File: X2BQ02 Attention: Mr. B. J. Youngblood Log: GN-1037 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C. 20555 REF: NRC LETTER TO GEORGIA POWER COMPANY DATED JULY 10, 1986 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 ADDITIONAL INFORMATION REGARDING V0GTLE STRUCTURAL DESIGN LIVE LOAD
Dear Mr. Denton:
Attached is the response to the NRC staff's request (enclosure of reference) for additional information regarding the Vogtle Electric Generating Plant (VEGP) Structural Design Live Load. Also attached is a proposed change to the VEGP FSAR that expands the definition of live load in accordance with the application of live load on VEGP. This information was discussed with the NRC staff during meetings on July 23, 1986 and July 29, 1986.
Should you have any additional questions, please inquire.
Sincerely,
/ J. A. Bailey Project Licensing Manager JAB /sm Attachments xc: R. E. Conway NRC Regional Administrator R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire W. C. Ramsey M. A. Miller (2) L. T. Gucwa B. Jones, Esquire Vogtle Project File G. Bockhold, Jr.
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ATTACHMENT RESPONSE TO NRC REQUEST FOR l ADDITIONAL INFORMATION REGARDING STRUCTURAL DESIGN LIVE LOAD !
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I. BACKGROUND The following background concerning the use of live load in structural design on VEGP is considered useful before responding to specific requests for additional information.
A. VEGP DEAD LOAD VEGP dead load includes all permanent items or permanently attached items such as:
o Building Structure o Substructures o Platforms o Equipment o Piping and Supports o Raceway _and Supports o Conduit'and Supports o HVAC and Supports o Electrical Control Panels and Consoles B. VEGP LIVE LOAD VEGP live load includes loads that vary with intensity and occurrence depending upon the. load condition, plant status, and the function of a specific area:
o Floor Area Occupancy Loads o Equipment Laydown Loads o Moveable Equipment Loads o Trucks and Other Vehicular Traffic Loads o Fuel Casks and Fuel Cask Equipment Handling Loads o Railroad Equipment Loads o Other Minimum Design Live Loads Such As Snow Loads, Office and Partition Loads, etc.
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C. TYPICAL VEGP STRUCTURAL DESIGN PROCESS In order to establish the specific magnitude'of live load to be used in the analysis and to perform the detailed structural design, the design engineer reviews the level of functional activity anticipated in the various areas of the plant during the different plant conditions.- Next the engineer reviews the loading combination equations (FSAR tables 3.8.4-1,-3.8.4-2 and 3.8.4-3) to determine which equations will govern based on the relative significance of the live loads for the different plant conditions.
listed below:
Pre-fuel load condition:
This' condition includes such things as localized effects of tower crane anchorage, vehicular traffic, temporary storage during construction of bulk materials and equipment, and maximum design live loads for floor area occupancy due to workers, tool boxes, scaffolding and localized cribbing.
Post-fuel-load condition:
This condition includes such things as equipment laydown loads, moveable equipment loads, and the maximum anticipated live loads for floor area occupancy.
The live loads used in design for equipment laydown and moveable equipment reflect the actual equipment weight as determined from vendor documents or specific calculations.
-For loading combination equations including earthquake generated loads, the maximum anticipated live loads for floor area occupancy are chosen to reflect 100% of the' live load occupancy level which could be expected to be-present during post-fuel load conditions, and are considered to be no less than 25% the pre-fuel load maximum design live load.for floor-area occupancy. The 25% is used as a_ conservative lower bound in areas that do not have a specific occupancy function, and is based on Bechtel's cumulative experience and judgment acquired by reviewing actual floor area occupancy levels on operating generating stations.
As a design option, in lieu of using the post-fuel load maximum anticipated live load for floor area occupancy, the design engineer may choose.to substitute a more conservative uniformly applied equipment dead load (i.e., dead load greater than the maximum anticipated live load, af ter accounting for load factor differences) on floor areas _not occupied by equipment, to simplify the design process.
An example of this structural design process is shown in Figure 1.
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FIGURE 1 Example of Structural Design Process
- 1. Structural Element: Reinforced concrete slab panel
- 2. Identified Live Loads for Different Plant Conditions:
Pre-Fuel Load Condition L g = Tower crane anchorage loads L = Maximum design live load for floor area occupancy due to 2
workers, tool boxes, bulk material laydown, etc.
Post-Fuel Load Condition L3= Equipment.laydown load L - Maximum anticipated live load for floor area occupancy 4
expected to be present during plant operation-(outside designated laydown area), but not less than L /4* 2
- 3. Governing Load Combination Equations *:
- a. Pre-fuel load condition Equation 1: 1.4 D + 1.7 L = 1.4 D + 1.7 (L y + L2) I[ U
- b. Post-fuel load condition Equation 3:
1.4 D + 1.7 L + 1.9 E = 1.4 D + 1.7 (L3+L)+ 4 1.9 [(D + L 3 + L4 )a] j[ U where:
a = Seismic design acceleration in "g"'s
- Refer to FSAR Table 3.8.4-3 3
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, II. ' RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION-
} A. REQUEST NO. 1:
i Provide a list of Category I structures and structural elements for g I which the application of " live load" in structural design was
? based on criteria other than those committed to in FSAR Section 3.8.4.3.1.1 and FSAR Tables 3.8.4-1, 3.8.4-2, and 3.8.4-3 l
i (i.e., where live load values of less than 100% of the " maximum j design" live load were applied). Describe chronologically when-such live load criteria was adopted and the design control' procedures and structural reevaluation tasks instituted to ensure.
l that the usage of the less than 100% live load criteria was 4 appropriate.
i j Response:
1 i VEGP criteria for. live load application acknowledges that live load I . intensity varies depending upon the status of plant operation-2 (i.e., pre-fuel load condition versus post-fuel load condition),
j and the level of functional activity for a. specific area. : Tables 1 j- through 4 identify all structural elements by building for which 2 the post-fuel load maximum anticipated live load for floor or roof j occupancy differs from the pre-fuel load maximum design live load j for floor or roof occupancy.- For structural elements not -
identified in these tables, post-fuel load maximum anticipated live load magnitudes are either equivalent to or greater than the pre-j fuel load maximum design live load magnitudes.
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( As can be seen from these tables, the areas where the post-fuel .
load maximum anticipated live loads differ from the pre-fuel load I maximum design live loads are limited to the grating and platforms
! inside the containment, localized roofs of some miscellaneous
} structures or tunnels, the basemats for several structures, columns
! at the lowest elevation of the Auxiliary Building and the NSCW l Valve House structure at all levels. The justification or i disposition of'these differences is provided in.the tables.. ;
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j The VEGP criteria-for live load application in combination with j- seismic induced loads, as summarized in the body of'Section I, was
- first issued for use on February 28, 1974. This criteria j specifirally limits the live load intensity in loading combinations including earthquake motion to the live loads expected to be present during plant operation.-~ Subsequent revisions to the
- criteria have resulted in only slight variations in the wording.
B. REQUEST No. 2:
The definition of live load discussed in_your May 23, 1986 letter,-
I- differed from the definition of live load.as given in FSAR
. Section 3.8.4.3.1.1 in that it broke down the live load into the l " maximum design" live load and " anticipated" live load. Provide 4
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the basis of this redefinition, Also, explain the basis for redefining the live load without amending FSAR Section 3.8.4.3.1.
Response
Our letter of May 23, 1986 (GN-921) addresses the basis for the usage of varying magnitudes of live load expected during different plant conditions. The terms " maximum design" live load and
" anticipated" live load are used to differentiate between these varying magnitudes, i.e. pre-fuel load condition versus post-fuel load condition. The pre-fuel load maximum design live loads for floor area occupancy include such things as temporary storage during construction of bulk materials and equipment, and maximum occupancy due to workers- tool boxes, scaffolding, and localized cribbing. The post-fuel load maximum anticipated live loads for floor area occupancy, pertaining to loading combinations including earthquake generated loads, are live load occupancy levels expected to be present during plant operation.
Because of the confusion surrounding this subject, it is acknowledged that a clarification to the FSAR is warranted. A proposed FSAR amendment concerning live load application in loading combinations including earthquake generated loads is previded in the attachment.
C. REQUEST h0. 3 The articipated live load is defined as 25% of the maximum design live load in some cases. Provide theoretical justification for this assumption. Also, as applicable, discuss and justify other percentages (less than 100% other than 25%) of the maximum design live load which may have been used in other cases.
Response
The maxiwum anticipated live load for floor area occupancy during plant operation is defined as 100% of the live load occupancy level expected to be present during post-fuel load conditions. The actual magnitude of this load can vary from area to area depending upon the level of functional activity imposed by operational requirements. In accordance with established Bechtel practice, the magnitude of the maximum anticipated live load for floor area occupancy is limited to no less than 25% of the pre-fuel load maximum design live load for floor area occupancy. As discussed in section I, the 25% is used as a conservativa lower botind in areas that do not have a specific occupancy function, and is tased on Bechtel's cumulative experience and judgment acquired by reviewing actual floor area occupancy levels on operating generating stations.
It should be noted that the live load reduction identified in Taole 4 for level D columns in the Auxiliary building is based on 5
live load reduction due to the size and number of supported tributary floor areas, as provided for in the design criteria in accordance with the Uniform Building Code.
- D. REQUEST NO. 4:
The anticipated live load, not the maximum design live load, is used in the load combination equations involving earthquake load effects. Provide the basis for the adoption of such design criteria.
Response
The load combination equations defined in FSAR Tables 3.8.4-1, 3.8.4-2, and 3.8.4-3 reflect a broad range of operational,
} environmental and abnormal conditions. The specific load terms (e.g., D, L, E, etc.) used in each equation reflect the condition 4
being investigated and should be compatible with the definition of-the status of the defined condition. The earthquake load combination equations reflect a post-fuel load plant condition, and therefore the maximum anticipated live load for floor area occupancy used in these equations should reflect 100% of the occupancy live load expected to be present during post-fuel load 3 conditions. The VEGP post-fuel load maximum anticipated live load for floor area occupancy reflects 100% of the live load occupancy level expected to be present during post-fuel load conditions, and are the values used in the structural design.
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ATTACRMENT 1 PROPOSED FSAR AMENDMENT SECTION 3.8.4.3.1.1 PRESENTLY STATES:
L Live-loads or their related internal moments and forces, including any movable equipment loads and other loads which vary with j intensity and occurrence, as lateral soil pressures. Live load intensity varies depending upon the load condition and the type of structural element.
, PROPOSED CHANGE:
L Live loads or their related internal moments and forces, including
. any moveable equipment loads and other loads which vary with intensity and occurrence, such as: floor area occupancy loads, moveable equipment loads, equipment laydown loads, nuclear fuel
, casks and fuel cask equipment loads, vehicular traffic loads, railroad equipment loads, and lateral soil pressures. Live load intensity varies depending upon the status of plant operation (i.e., pre-fuel load condition versus post-fuel load condition),
the level of functional activity for a specific area, and the type of structural element. The pre-fuel load maximum design live loads for floor area occupancy include such things as temporary storage during construction of bulk materials and equipment, and maximum occupancy due to workers, tool boxes, scaffolding, and localized cribbing. The post-fuel load maximum anticipated live loads for floor area occupancy, pertaining to loading combinations including earthquake generated loads, are 100% of the live load occupancy levels expected to be present during plant operation, and are considered to be not less than 25% of the pre-fuel load maximum design live load for floor area occupancy.
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I ATTACHMENT 1 PROPOSED FSAR AMENDMENT
TABLE 3.8.4-1(*)
EQN D L Pa To ..........
Service Load Conditions 1 1.0 1.0 ..........
2 1.0 1.0 ..........
3 1.0 1.0 .......... !
4 1.0 1.0 1.0 .......... l i
- a. See paragraph 3.8.4.3 for definition of load symbols . . . . . . . . . . . . . . . . . .
PROPOSED CHANGE:
EQN D L Pa To ..........
Service Load Conditions 1 1.0 1.0 ..........
2 1.0 1.0 ..........
3 1.0 1.0 ..........
4 1.0 1.0 1.0 ..........
- a. See paragraph 3.8.4.3 for definition of load symbols including the definition of L during pre-fuel load and post-fuel load conditions.....
- The footnotes to table 3.8.4-2 and 3.8.4-3 will also be revised as shown above.
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Table 1 CONTAIN'JENT INTERNAL STRUCTURES, DIESEL FUEL OIL STORAGE TANK PUMPHOUSE AND FUEL HANDLING BUILDING +
PRE-FUEL LOAD POST-FUEL LOAD
' STRUCTURE MAXIMUM DESIGN MAXIMUM ANTICIPATED
& LOCATION LIVE LOAD (PSF) LIVE LOAD (PSF) COMMENTS CONTAIPWENT INTERNAL STRUCTURE GRATINGS & PLATFORM 150 37.5 REFLECTS MAXIMUM ANTICIPATED FLOOR AREA OCCUPANCY LEVEL DURING POST-FUEL LOAD CONDITION DIESEL FUEL DIL STORAGE TANK PUMPHOUSE ROOFS (UPPER AND LOWER) 150 37.5 REFLECTS MAXIMUM ANTICIPATED ROOF AREA OCCUPANCY LEVEL DURING POST-FUEL LOAD CONDITION FUEL HANDLING BUILDING LEVEL 3 ROOF 30 30 SLAB THICKNESS CONTROLLED BY (7.5 USED) TORNADO MISSILE CRITERIA.
INHERENT RESERVE CAPACITY EXISTS.
30 PSF LIVE LOAD USED IN LOADING COMBINATIONS FOR TORNADO WIND CONDITIONS.
BASEMAT 100 FLOORS 25 FLOORS FLOORS REFLECT MAXIMUM ANTICIPATED 30 ROOF 30 ROOF FLOOR AREA OCCUPANCY LEVEL DURING (7.5 USED) POST-FUEL LOAD CONDITION FOR EVALUATION OF CONTRIBUTION TO BASEMAT DESIGN. ROOF DIFFERENCE IS INCONSEQUENTIAL. (USED FOR BASEMAT DESIGN ONLY)
- FOR ALL AREAS OF REFERENCED BUILDINGS NOT LISTED, POST-FUEL LOAD MAXIMUM ANTICIPATED LIVE LOAD MAGNITUDES USED WERE EITHER EQUIVALENT TO OR GREATER THAN THE PRE-FUEL LOAD MAXIMUM DESIGN LIVE LOAD MAGNITUDES.
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Table 2 DIESEL GENERATOR BUILDING, NSCW VALVE HOUSE AND TOWER
- PRE-FUEL LOAD POST-FUEL LOAD STRUCTURE MAXIMUM DESIGN MAXIMUM ANTICIPATED
& LOCATION LIVE LOAD (PSF) LIVE LOAD (PSF) COMMENTS DIESEL GENERATOR BUILDING BASEMAT 250 BASEMAT 250 BASEMAT REFLECT MAXIMUM ANTICIPATED FLOOR 100 FLOORS 25 FLODRS AREA OCCUPANCY LEVELS DURING POST-i 30 ROOF 30 ROOF FUEL LOAD CONDITION NSCW VALVE HOUSE ROOF 30 30 SLAB THICKNESS CONTROLLED BY (7.5 USED) TORNADO MISSILE CRITERIA.
INHERENT RESERVE CAPACITY EXISTS.
30 PSF LIVE LOAD USED IN LOADING COMBINATIONS FOR TORNADO WIND CONDITIONS MEZZANINE 100 25 REFLECTS MAXIMUM ANTICIPATED FLOOR AREA OCCUPANCY LEVEL DURING POST-FUEL LOAD CONDITION BASEMAT 100 25 REFLECTS MAXIMUM ANTICIPATED FLODR AREA OCCUPANCY LEVEL DURING POST-FUEL LOAD CONDITION NSCW TOWER PLATFORM AT ELIMINATOR 100 25 POST-FUEL LOAD MAXIMUM ANTICIPATED LEVEL FLOOR AREA LIVE LOAD (USED IN OVERALL BLDC. ANALYSIS ONLY)
TOP OF BtHTRESS 100 25 REFLECTS MAXIMUM ANTICIPATED FLOOR AREA OCCUPANCY LEVEL DURING POST-FUEL LOAD CONDITION
- FOR ALL AREAS OF REFERENCED BUILDINGS NOT LISTED, PCST-FUEL LOAD MAXIMUM ANTICIPATED LIVE LOAD MAGNITUDES USED WERE EITHER EQUIVALENT TO OR GREATER THAN THE PRE-FUEL LOAD MAXIMUM DESIGN LIVE LOAD MAGNITUDES.
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Table 3 CATECORY 1 TUNNELS.
PRE-FUEL LOAD POST-FUEL LOAD STRUCTURE MAXIMUM DESIGN MAXIMUM ANTICIPATED
& LOCATION LIVE LOAD (PSF) LIVE LOAD (PSF) COMMENTS D.C. PIPING TUNNEL (T3A & T38) 100 25 DETAILED SAME AS ROOF WHERE SEPARATION FLOOR (0 USED) 250 PSF LL WAS USED D.C. ELECTRIC TUNNEL (T4A & T48)
SHAFT ROOF 30 30 DETAILED SAME AS ANOTHER TUNNEL (7.5 USED) SHAFT ROOF WHERE 124 PSF LL WAS USED
- FOR ALL AREAS OF TUNNELS NOT LISTED AND FOR ALL OTHER TUNNELS, POST-FUEL LOAD MAXIMUM ANTICIPATED LIVE LOAD MAGNITUDES USED WERE EITHER EQUIVALENT TO OR GREATER THAN THE PRE-FUEL LOAD MAXIMUM DESIGN LIVE LOAD MAGNITUDES.
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Table 4 CONTROL BUILDING AND AUXILIARY BUILDING.
PRE-FUEL LOAD POST-FUEL LOAD STRUCTURE MAXIMUM DESIGN MAXIMUM ANTICIPATED
& LOCATION LIVE LOAD (PSF) LIVE LOAD (PSF) COMMENTS CONTROL BUILDING BASEMAT 100 (TYPICAL) FLOORS 25 FLOORS FLOORS REFLECT MAXIMUM ANTICIPATED 30 ROOF 30 ROOF FLOOR AREA OCCUPANCY LEVEL DURING (8 USED) POST-FUEL LOAD CONDITIONS FOR EVALUATION OF CONTRIBUTION TO BASEMAT DESIGN. ROOF DIFFERENCE IS INCONSEQUENTIAL (USED FOR BASEMAT DESIGN ONLY)
AUXILIARY BUILDING LEVEL 'D' COLUMNS ONLY 100 72 LL REDUCTION BY TRIBUTARY AREAS PER UBC PROVISIONS
- FOR AREAS OF REFERENCED BUILDINGS NOT LISTED, POST-FUEL LOAD MAXIMUM ANTICIPATED LIVE LOAD MACNITUDES USED WERE EITHER EQUIVALENT TO OR CREATER THAN PRE-FUEL LOAD MAXIMUM DESIGN LIVE LOAD MAGNITUDES.
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