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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
[Table view] |
Text
- Gecrg.a Power Company Post Off ce Ecx 4545 230 Peachtres Street N W.
At:anta. Gecrg.a 30302 Teieor.one 404 522-60E0 W. E. Ehrensperger November 27, 1979 Sen.or Vice P esce .t Puer Sacc'y Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKETS 50-424, 50-425 CONSTRUCTION PERMITS CPPR-108, CPPR-109
_ ALVIN W. V0GTLE NUCLEAR PLANT UNITS 1, 2
Dear Mr. Denton:
The put;ose of this letter is to inform you on behalf of Gerogia Power Company ("GPC"), Oglethorpe Power Corporation ("0PC"), the Municipal Electric Authority of Georgia ("MEAG"), and the City of Dalton (" DALTON") of two developments which may relate to the various requests and communications of Georgians Against Nuclear Energy ("GANE"):
(1) A new Georgia territorir' load forecast of peak demands for electricity has been pertormed, and it indicates annual growth rates of 2.64% to 6.37% between years in the period 1979 - 1980, and averaging over the period 4.03% compounded annually. Attachment 1 is the current Georgia territorial generation expansion plan for meeting this anticipated load. Attachment 2 is the current Southern Company System generation expansion plan reflecting the new Georgia territorial forecast and revised forecasts for other system affiliates.
(2) GPC and Florida P;wer & Light Company ("FP&L") have begun discussions which may lead to FP&L joining as a co-owner of up to 30% of Plant Vogtle, with GPC reducing its ownership correspondingly. If the negotiations are successful, regulatory approvals would have to be obtained prior to consummating the arrangement. One of the required approvals, of course, would be that of the Nuclear Regulatory Commission, and because of the Commission's antitrust mandate, GPC assumes that some portion of the plant that would otherwise be owned by FP&L may instead be owned by Florida municipal or cooperative power suppliers. The negotiations are at an early stage, and it is
- The GANE communications, and to a lesser extent the two Directors' Denials, treat the various load forecasts, generation plans, and other power needs data as pertaining to " Georgia Power Company" when in fact they are observa-tions concerning the combined systems of GPC, OPC, MEAG and Dalton. Similarly, Plant Vogtle has not been intended to serve the needs of GPC, which owns only approximately one-half of the plant, but of the combined needs of all four g
power suppliers, hp /
\475 \b8 tD 7o12049 4%
Georgia Power d Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation November 27, 1979 Page Two not possible at this point to estimate when they will be concluded.
It is GPC's expectation, however, that the discussions will take place over months, not years, and if they are successful that application for amendments to the construction permits would be made to the Commission shortly after conclusion. Attachment 3 is a long-hand revision of Attachment 2 showing the generation capacity impact on the Southern System of a FP&L arrangement.
Very truly yours, hb ud k #
W. E. Ehrensperger r LTG:MAC/mb Attachment xc: Gary Flack, Esquire 1515 Healey Building 57 Forsyth Street, NW Atlanta, Georgia 30303 Stephen G. Burns Of fice of Executive Legal Director U. S. Nuclear Regulatory Commission Washington, D. C. 20555 G. F. Trowbridge, Esquire Ruble A. Thomas M. A. Carlton 1475 139
OCT6BER38e1979 CECaCIAPOWERCOMPANT REPORT NO. 1 PACE 1
, STSTEMEIPANSIONPLAN 79R1-REV.3-CPC 1988 - 1998 NET UNIT DATE ADJUST. SYSTEM MW LOAD MWRESERVE I RESERVE C6PACITY CAPACITT PROJECTED INITIAL CENERATION 12/31n9 13789.5 PEAXING 43 MW COMB.TURB 2/89 43.5 43.0 VALLACE EAM 1-6 Hi[R0 5/89 325.8 325.9 SEPA PREFERENCE ADJJSTMENT 6/88 38.2 39.2 SEPA HIER0 ADJUSTMBli 6/88 -38.2 -38.2 CRISPCOUllTISEPAADJUSTMENT 6/8f f.5 -0.5 TOTAL 7/31/88 14156.5 19781.8 3455.5 32.29 B0 WEN 1 FRECIP IMPROVEMENTS 1/81 198.5 lif.f TVA INTERCHANGE ADJJSTMENT 6/31 -42.0 -42.8 SEPA HIDR 0 ADJUSTMEIT 6/81 -34.9 -34.9 SEPA FREFERENCE ADJJSTMENT 6/81 34.9 34.9 CRISP COUttif SEPA ADJUSTMENT 6/81 -f.6 -8.6 TOTAL 7/31/81 14213.9 11031.5 3182.9 28.85 SCHERER 1 858 FC (23.51 CPC) 2/82 898.8 898.9 SEPA HIDR 0 ADJUSTMEli 6/82 -48.7 -49.7 SEPA PREFERENCE ADJJSTMENT 6/82 48.7 48.7 CRISP COUNTT SEPA ADJUSTMENT 6/82 -f.7 -0.7 TOTAL 7/31/82 15921.1 113^5.0 3626.1 31.82 TOTAL 7/31/83 15921.1 12128.8 2981.1 23.94 ATKINSON 1 RETIRE 1/84 -55.4 -55.4 SCHERER 2 EIS FC (23.51 CPC) 2/84 898.8 888.8 TOTAL 7/31/84 15773.7 12847.8 2926.7 22.78 V0CTLE 11158 NUCLEAR 11/84 1159.5 1159.8 RUSSELL DAM SEPA HfDRO 12/84 159.9 158.9 TOTAL 7/31/85 17873.7 13498.8 3665.7 27.34 4ck""
1475 140 (pw / as a)
LOV 27 2
OCTOBER 351979 CECRCIAPOWERCOMPANT REPORT NO. 1 PACE 2 STSTEMEIPANSIONPLAN 79R1-REV.3-CPC 1988 - 1918 NET UNIT DATE ADJUST. S1 STEM MW LOAD E RESERVE IRESERVE CAPACITT CAPAC!li PROJECTED TOTAL 7/31185 17073.7 13488.8 3665.7 27.34 CASTON A RETIRE (531) 1/86 -7.9 -7.9 fARTLETTS FERRT HTCR0 ADDIT 10ft 1/86 199.5 188.9 10TAL 7/31/86 17165.8 13959.8 3215.8 23.95 ROCXT MOUtiTAIN 1-3 PUMP STOR 11/86 675.8 675.8 ARKWRICHT 1 RETIRE 1/87 -42.2 -42.2 ATXINSCN 2 RETIRE 1/87 -57.3 -57.3 RUSSELL DAM SEPA P/S 1/87 159.9 158.9 SCHERER 3 888 FC (33.51 CPC) 2/87 808.9 444.0 TOTAL 7131/87 18295.3 14649.8 3646.3 24.89 V0GTLE 2 1150 NUCLEAR 11/87 1159.9 1156.8 ARXWRIGHT 2 RETIRE 1/88 -43.5 -43.5 TOTAL 7/31/88 19481.8 15215.8 4186.8 27.52 ARXWRICHT 3L4 RETIRE 1/89 -86.7 -86.7 MITCHELL 102 RETIRE 1189 -41.9 -41.3 C0AT ROCK HTCR0 ADDITION 1/89 67.8 67.9 SCHERER 4 808 FC (33.51 CPC) 2/89 898.8 464.g TOTAL 7/31/89 19745.1 15616.8 4129.1 26.44 ARXWRICHT SAtSB RETIRE 1/98 -26.1 -26.1 TOTAL 7/31/96 19719.0 16163.8 3536.8 21.85 1475 141 prraswr 1 LON27 1979 (##8e 3 *# :')
CDEF.iT!01 EIPMSIC1 PLAN 7991(REV3) e PRCF3iED 1%CET AC FORECAST FLA4 (198i-1989)
(1999-im CONTICD.CT FLAN)
PEM F0bR CAFEILITYe 5.ESERVES:ANDC0P!05111010FCAPABILITT IIR.b31G !EFA FREFERENCE CUST0PER LOAD)
E-N A C I 0F LOA 3
- c. 1929 CFAElllii (HBCES:
- CA FEAMING 43 d COMB TUT.B CA WJ. ACE CAM 1-6 325 M HIDR 0 SEFA CHMCE -1 N SE?AHIDR0
( CA MISS ZME?A AL"JSTMENT -59 M SMEPA
( ................
ALAIA:tA CE0RCIA CULF t!!SS SYSTEM LCAD -5 7919 19701 135J 1484 20243 g ................ ....... ....... ....... ....... .......
NUCLEAR -u S37 1542 9 9 2349
( FC131L -W I 9.9J 5497 19.89 9791 9.if 1484 6.23 1987 9.06 18679 2 67.41 69.17 94.64 92.84 72.24
( FEAKING:
C0?P TUTd -n 87 974 31 62 1154 I 1.97 4.88 1.98 3.32 4.45
( HTLR0 -S I
1163 14.33 EJi 5.65 J.f3 9
0.33 9 1948 7.59 SE:A HT M0 -MW 313 932 33 61 1349 3.El
( T0iAL * -MW I
1565 4.58 2726 2.42 69 3.36 131 5.29 4471 1 19.2J 19.12 4.46 6.33 17.24 OT;iER:
( INTERUP LD -d 211 9 3 9 211 AEC -d G J 9 9 9,
( SME?A TVA
-W
-N 9
72 9
117 i
15 G
16 9
223 SAV N AH -N G 9 9 3 9
-W
( SCELC FFC -N 9
G 9
9 9
9 9
9 0
9 PiU -N 9 3 9 9 9
-D
( CRiiP CTI Ml?C -d G
G 9
9 9
9 9
9 9
9 TOTAL -d 283 117 15 16 431 1 3.47 f.83 9.16 9.78 1.66 b TOTAL CAFAB -n 8152 14156 1568 2f54 25939
( RESERVES -N 2
till 14.14 3455 12.29 218 16.15 453 46.30 5682 23.06
( 19/18/79
(.
C iA75 142 C
ykk&}- '
liOV 27 1979 i (Pasr / er f)
( . O
b CE'iERAT!C?i E1FA'iS10:1 PLAN 79R1(REV3)
F10P0$ED ICCEI CD FORECAST PLA'i (1983-1189)
(1917-li!4 CO?.TIiCENCY PLA'l) b PEAK HOUR CA:ASILITY, REiERVES A'O COM?0SliiON CF CAPA3!LITT (IELUDING SE?A FFEFERECE CUSTCHER LOAD)
MW AND 1 CF LOAD p
1981CA?AllllifCHA'CES:
A'.A TVA DHERCHANGE ADJUSTMENT -25P.W TVA E CA CA;4Sillii M JUSTMENT If] MW FOSSIL CA TVA INTERCHACE JJUSTMENT -42 F.W TVA ALA FARLET 2 807 MW NUCLEAR b A: A EX1. DIN DAM
. 232 r4 HTCR0 ALA FARLEY 1 INCREASE 37 MW NUCLEAR ALA TVA ::GETJ5 ACE ADJUSTMENT -25 MW TVA k CA SEFA CHAGE -1 rd SEFA HYDRO CA TVA l'.iERCHAEE ADJUSTMENT -42NW TNA
,r CUtf DANIEL 142 (5dI) 5f6 PW FOSSIL
' CUlf TVA INTERCFACE ADJUSTMENT TVA
_-6 MW MISS CANIEL 1 (Sil) -254 MW FOSSIL
( MISS CANIEL 2 (531)
MISS CAFAlillif AI:JU$iMEli 151 MW 24 MJ F05SIL FOSSIL MISS TVA INTERCHANGE ADJUSTMENT -7 MW TVA b ALA2M4 CEORCIA CULF MISS S1 STEM
-EJ p LOAD 72S3 11131 1354 1459 Zi9J2
( 'iUCLEAR -rJ I
1651 17.94 1542 10.35 f.fi i
G.f]
f 3193 11.59 FOSSIL -EJ 5497 9891 1993 1923 193J6 g I 59.73 69.59 96.23 93.23 79.37 CCS TURB -rJ 87 974 31 62 1154 I 1.95 6.35 1.50 3.53 4.19 k HYIR0 -rJ 146J Sd6 8 0 2283 1 15.21 5.63 f.if f.fi 7.93 SEF; HYDR 0 -rJ 318 931 33 69 1343 b 1 3.37 6.55 1.34 3.34 4.89 TOTAL -rJ 1797 2705 69 131 4702
( OTHER:
1 19.53 19.03 3.34 6.33 17.37 .
INTERUP LD -T'J 211 8 9 9 211 AEC -FJ f G 6 8 i b $PEPA -MW G 9 3 f f TVA -MW 47 75 9 9 148 SAV M A1 -MW 3 9 0 9 9 f- SCElG -FJ f 6 i i i FPC PJ G 9 9 3 i
-NJ b MSU CRI:!P CTT -MW G
f B i G i 143 MISC -MW G 6
i 8
9 G
9 9
8 1475 TOTAL -MJ 253 75 9 9 351 bg I 2.E9 9.53 3.44 f.44 1.27 522 TOT 4. CAPAD -rJ 9283 14213 2f68 2063 27552
( c~c REEERVES -M'J 1920 3152 714 681 6653 pg&g-f ~2-
- " 26.36 1 28.85 52.73 41.74 31.32 b
S ................ ....... ....... ....... ....... ....... [NW
CENERATIG4 EIFANSIC:t FLAN 79R1(REV3) r FR U O5Et EUE0ET AND FCEECf.3T FLAN (1983-1989)
(1910-ZN4 CCtTIMECT PLAN)
PEAK HOUR CAFABIL!if e RESERVES, AND CO?f0SITICN CF CAPABILITT
!D.0LGIC SEFA F5EFERENCE CU310?.ER LOAD)
- I N AN3 I (F LOAD 1922 CAFA?lLITT CHANGES:
I CA SCFERER 1 323 N FOS $1L ALAEA14 CEORCIA CULF MISS SISTEM
[ ................ ....... ....... ....... ....... .......
LCAD -d 7622 11715 1397 1514 21679 NUCLEAR -d 1651 1542 9 6 3193 1 17.94 10.27 9.f3 d.fJ 11.26 I FOSSIL -d 5497 19699 1993 1923 20114 1 59.73 71.23 96.23 93.23 70.92
( PEAXINC:
CC?3 TURB -d 87 974 31 62 1154 1 3.95 4.48 1.53 3.53 4.07 f HIERO -N 14!J 833 6 3 22f3
- 15.21 5.33 0.00 1 0.83 7.76 SE?A H CR0 -MW 310 931 38 69 1348 I 3.37 6.28 1.24 3.34 4.75 I -d TOTAL 1797 27f5 69 131 4732 1 19.5J 18.01 3.34 4.33 16.53 OTHER:
U INTERUPLD-d 211 8 8 3 til AE; -d 9 0 0 0 i
( SMEPA -d G 8 6 i 8 TVA -d 47 75 9 9 142 SAVAN m -d 9 0 f 9 3 SCE% -d f f f i
( FPC -d 0 8 8 3
9 9 MSU -d 0 9 9 0 i CRISP CTT d 9 8 9 J J I- MISC -d G 9 9 0 i TOTAL -M'J 293 75 9 9 351 1 2.83 f.53 9.44 9.44 1.24 I
TOTAL CAFA3 -d 9233 15321 2063 2263 28349 RESER','ES -d 1601 3626 671 552 4631 k I 21.25 31.32 48.03 36.41 33.82
( 1H18/79 L
C
\415 \hh c
L +rme/xed ~2 LOV 27 1979 (P M E' 3 d' '
s CENERATICM EIF4.510ii PLAN 79R1(REV3)
FRCF0?ED PUICET AND FORECAST FlM (1980-1939)
(19101N4(CitilN;ENCYPLAN)
{ PE E HOUR C F45:llife REiERVEi, AND CCP.F051T10N CF CAFABILITT (INCL')DILC SE?A H.EFERENCE CUSTOMER LOAD) p MW AND 1 CF LOAD 1983CA?ABILITYCHA1CES:
ALA HF.RISCAM162 117 MW HYDR 0 C ALA MILLER 2 654MW FOSSIL ALAZAMA CEORCIA MISS SYSTE1 b ................ ....... .......
CULF LOAD -W 7934 12123 1449 1576 22838 g ................ ....... ....... ....... ....... .......
NUCLEAR M 1651 1542 i i 3193
( F073IL -NW I 16.55 6151 13.27 if699 9.f3 1993 0.fJ 1928 19.96 20768 1 61.67 71.23 96.13 93.23 71.29
( FEAKINC:
COM3 IURB - d 87 974 31 62 1154 1 9.87 6.48 1.5J 3.fJ 3.96
( HYERO -lf.i
~
1517 C33 i G 2317 15.21 5.33 J.23 0.fi 7.95 SEFA HTIRO d 319 931 38 69 1348 I 3.11 6.2i 1.24 3.34 4.63
{ TOTAL -W 1914 27i5 69 131 4819 1 19.19 13.01 3.34 6.33 16.54 GTHER:
b INTE?.U? LD -N 211 8 8 8 211 AEC -d G f f 2 3
( SMEPA TVA
-M
-N 8
47 f
75 f
9 J
9 g
14,1 SA'.'MNAH -d G $ i i g e SCE!C -d 9 9 6 3 0
' FFC -W 0 9 8 i 3 MSU -W 8 8 9 i 8
( Ci!3P CIT -d MISC -u G
0 8
0 9
9 9
i 9
J TOTAL -d 253 75 9 9 351 1 2.59 9.59 8.44 6.44 1.29
( TOTU. CAFAB W 9?74 15J21 2168 2f68 29131
( RE! EWES -N 1
2B3 25.69 1991 23.94 619 42.72 498 31.72 6293 27.55 16/18/79
(
C 1475 145 C
C ,, p c .a
(!Lol27 197 9 (re" # e' d
CENERATIONEIPAMIGNPLAN79R1(REV3)
FROP0iEL li.U ET AND FORECAST PLAN (1963-1989) c (1910-L184CONiltiCENCYPLAi)
' FEAK H0'.!R CAFA5ILITie REiERVES, AN3 COM?0 SIT 10N CF CAPABILITI (ILCi.CINC SEPA FREFERE? ICE CUSTOMER LCAD)
N AND I 0F LOAD 1931CAPABILITTCHANCES:
r CA ATKINiON 1 (RETIRE) -55 N FOS 3!L 8-CA SCHERER 2 825 s F0ti!L ALAEANA CEOR0IA CULF NISS S1 STEM f ................ ....... ....... ....... ....... .......
LOAD -N 8269 12847 1502 1623 242]I g
NUCLEAR -u 1451 1542 9 9 3193
,r 1 16.55 9.78 6.fi 6.03 10.68
' F091L
-W 6151 11452 1973 1923 21521 1 61.67 72.63 96.23 93.23 72.92 FEAXING:
I CCr3 TGB -u 87 974 31 62
' 1154 I 9.87 4.17 1.58 3.fi 3.36 HYERO -W 1517 839 8 8 2317 I I' 15.21 5.07 3.03 8.fJ 7.75 EEFA HTI M -N 319 931 33 69 1348 1 3.11 5.13 1.84 3.34 4.51 I TOTAL -N 1914 2705 69 131 4319 2 19.19 17.15 3.34 4.33 16.13 OTHER:
I INTERP LD -u 211 0 3 8 211 AEC -d 6 0 9 9 i i
( S?i?A TVA
-d
-5 G
47 9
75 9 8 9 9 143 SAVAKiAH -G 9 i G f 9 c SCE00 -N G i 8 9 6 A FFC -W f i 9 f i MSU -rJ f 3 i i f CRI5? CTY -d I
( MISC -d 6
G 8
i 0
8 i
9 i TOTAL -M 253 75 9 9 351 I
( TOTAL CA?AB -W 2.59 9974 f.43 15774 0.44 2268 9.44 2263 1.17 29634 RESERVE 3 -n 1705 2927 566 441 5834
(- I 28.62 22.78 37.68 27.03 24.52 C.
1475 146
(.
( prrsc/kW D _
(w r.u)
( ROV 27 1979
E t CE!;ERATIBt EIFAi!!0:1 PLAN 79R1(REV3) -WRL Vog (c.5,Jc.
PR0?OSED EULGET CiD FORECA5i FLAN (1989-1939) c (1913-2i.4 CCitTICENCY PLAN)
' PEAK HER CAFAEILITY, REiERVE3, Ah3 (CMP 051 TION OF CAFABILIT1 IINCL'J:ING 5EFA FF.EFERENCE CUSTCMER LOAD)
MW AND I CF LOAD p
1985 CA~ ASILITY CHANCES:
c ALA MITCHELL DAM INCREASE 97 MW HTERO
'- ALA MILLER 3 654 MW F0istL ALA FARLET 2 INCREA?E 37 MW NUCLEAR ALA *Eh0?0L151*.2
- (KETIRE) -34MW COMB TURB b CA RICHARD B. RUSSELL 153 MW SEFAHTLR0 CA V0 GILE 1 1150 MW hUCLEAR GA Vo9% ALAEANA L SedeCECRCIA ~350 MLV
, LOAD -MW 8607 13133 1557 1579 24903
-r) 4383 - 3 5 0
( NUCLEAR I
1633 15.73 2692 .150 15.77 9.23 8
0.83 9
13.71 FOSSIL -rJ 6225 11452 1193 1928 22175 g I 63.43 67.37 96.23 93.23 69.43 COM3 TUR3 WJ 53 174 31 62 !!Z8
( HYDRO -r4 1 0.41 1614 5.73 Sid 1.50 8
3.93 3
3.51 2414 2 15.04 4.49 0.03 G.fi 7.56
,- SEPA HIERO -FJ 310 1931 33 69 1493 L I 2.?? 6.33 1.84 3.34 4.69 TOTAL fJ 1977 2855 69 131 Si32 16,72
( I 18.43 3.34 4.33 15.76 ICERUPLD-NW 211 8 9 0 211
( AEC SMEPA
-rJ
-MW G
8 i
9 9
9 9
9 6
i TVA -MW 47 75 9 9 ill SAVAE'.4H f) G 8 9 9 9 k SCE;G -MW 9 9 i e i FPC -MW 6 9 0 0 6
-N
( MSU CRISP CIT -MW G
9 9
6 8
0 0 3 . 3 8
MISC fJ G 6 0 9 3 TOTAL -MJ 253 75 9 9 351
( I 2.49 0.44 9.44 f.44 1.13 TOTAL Cf4AE fJ 18723 17074 2063 2f63 31933 g-REEERVES TJ 2121 3666 511 489 7033 1 24.64 27.34 32.82 3J.97 28.27
( 10/12/79 Sc le. of asos.ma) us*124 3:585 c o v. sans c6rs !475 i4/
o .fy4 em 24.~l3 % 26.% %
( _
Q clA A 4 d- 3 C M_0V 2 7 1979
^
mu/ a )
d.
e GE'.EFATIO" EIFANSION PLAN 79R1(REV3) - U.)in. Vogtk ,$mle.
PRO ~0iED IU0CEi CD FORECAST FLAN (1928-1989)
(1956-1034 CONiiNCENCfPLAN) b PEA':r HOUR GFASIllib REiERVES, AND CCP.?GSITION OF CAFA31LITT (ICLWi!.G SE?A F;EFERE::CE CUSTOMER LOAD)
M AND I 0F LCAD p
1926C:PAE!LITYCHA!.GES:
- r. ALA CA310N A (RETIRE) (50%) -8 W COMB TURB l GA CAS70N A (RETIRE) (Sil) -8 N COPB TURB GA DRILETTS FERRY INC liJ N HTOR0 G7.F CRIli ! (REiiRE) -22 N FOSSIL I Ml!$ EAICN 1 (RETIRE) -24 N FOSSIL MISS '4ATSON A (RETIRE) -31 W C0FB TURB k ALAEAMA GEORCIA GULF MISS SYSTEM
-d
( LCAD 8939 13958 1614 1524 25749 g TJCLEAR -d 1681 2692-J50 8 6 4333 -J'SC 1 15.75 15.48 f.fJ J.21 13.71 FOSSIL -0 6535 11452 1968 1994 22!29 g I 63.48 66.71 96.19 94.59 69.27 -
00?3 TGS -N 45 966 31 31 1J73 I f.42 5.63 1.52 1.54 3.36 I
Hf*G0 -N 1614 9J3 0 0 2514 1 15.25 5.24 0.93 3.23 7.87 SEFA MtLR0 -N I I 313 2.39 1981 6.33 38 1.86 69 3.43 1498 4.69 TOTAL -N 1961 2947 69 170 MS5 2 18.37 17.17 3.37 4.97 15.12
{
INTER'J? LD -u 211 8 i 9 211 g-AEC -W 0 8 0 0 i SMEPA -d G 9 8 i 3 .
TVA -H 47 75 9 9 149
-G
( SAVAYiM SCE;G -5 9
f 9
a 9
8 9
8 3
9 FPC -W d 6 i i 9 MSU -d J 3 6 3 9 k CRISPCIT -N 3 8 9 9 9 MISC -d G 9 f 9 9 TOTAL -d 203 75 9 9 351 k I 2.41 f.44 9.44 f.45 1.13 TOTAL CAFA3 -d 1972al 17166 2046 2013 31945
( ................
RESERVES -N 1781 3216 432 459 6176 2 19.92 23.05 26.77 32.09 23.97 g ................ ....... ....... ....... ....... .......
10/18/79 Ifo8 Ila 38595
( 2%6 20.5 %
S826 )h]5 \4g 22.fo.t %
s rises %c a r .3 NOV o71979
s f CENERAT10ii E!PA'lSIC"i FLAN 79R1(REV3) -tdNl Voy(62 Sola.
FRG?0 SED S'.GEi A'?., FORECAST PLAN (19301989)
, (liif-22J4 CClill.CENCY FLAN)
' PEAi( HOUR CAFAIILITI, RE!ERVE3, AG CO?.P0Sli10N OF CAFA3ILIT7 (INCLUDIN;SE?APREFERENCECUSTCMERLOAD)
W AND I CF LOAD 1987 CAPASILITY CHANCES: -
ALA MILLER 4 654 N FOSSIL E ALA CCRCAS 5 (RETIRE) -58 H FOSSIL CA ROCKY MTN 1-3 675 W HTDR0 CA RICPARD B. RU35 ELL (PSH) 150 M SEPAHYCR0 I CA AE'J.*GHT 1 (RETIRE) -42 W FOSS!L CA AT.<!!.501 2 (RETIRE) -57 N F0531L CA SCHERER 3 (!al) 494 5 FOSSIL k CULF SCHERER 3 (251) 202 N FOSSIL MISS SCFERER 3 (251) 292 5 FCSSil p MISS S*dEAIT A (RETIRE) -31 S CC?.BTURB ALAEANA CECRCIA GULF MISS SISTEN
( ................
LOAD -fJ 93f6 14649 1674 1576 26943
( M.' CLEAR -W 1653 2692-J50 3 9 4383 -JSO I 14.92 14.71 0.fi 0.33 12.37 FOSSIL M 7481 11757 2170 21J6 23434 f- I 65.41 64.25 96.53 96.43 48.83 FEAKING:
,- C07.3 TURB -M 45 966 31 0 1942 L 1 3.4J 5.23 1.38 0.J 5 . 3.06 HY030 -d 1614 1575 3 0 3189
( SEFA HY B 0 - u 2 14.26 31J 8.41 1231 0.03 38 0.93 69 9.37 1643 1 2.74 6.73 1.69 3.16 4.24 TOTAL -5 1969 3772 69 69 5379 f I 17.40 22.62 3.07 3.16 17.27 OTHER:
INTERUP LD -W 211 9 6 9 211 b AEC d J 8 3 8 i SPEPA -d 0 $ i 8 3 TVA -h'.i 47 75 9 9 146 k SaVAWAH -d 0 0 3 i i SCE3C -W 0 0 f 9 i g FPC MSU
-W
-M'4 G 8 9 8 i 0 0 3 0 0 CR11P CT! -N 0 0 3 J 9 g-MISC W 8 9 9 9 i TOTAL W 2S3 75 9 9 351 I 2.23 f.41 3.40 0.41 1.63
( TOTAL CAPAB -d 11316 15296 2243 2184 34044 RESERVES -W 2010 3647 574 I 21.16 24.93 3?.29 603 38.59 7134 26.37 3 7 j4C)
( ................ ....... ....... ....... ....... .......
I
( lTR4(o J297 Y4 6754 Afr/h# E 22Sl% 25.07 % (psu 3 "' '
40y27 1979
CENERATION EIPMSION PLAN 79R1(REV3) - u.)Lil Vqde $cm(.a.
FROF0iED ICCET A'.D FORECAST FLPi (1983-1989)
- (1993-2034 CGNTIN0ENCfFLAN)
PEAK HGUR CA?A:!Liif e REiERVES: AND C05:031TIONOFCAFA31LITT I N;LUDIN; SEPA FREFERENCE CU$iOMER LCAD)
,. N AND 1 0F LOAD 1983CAPAEILITYCHANCES:
y ALA EARRY AIB (RETIRE) -45 5 COMB iURB 6 CA V0GTLE 2 115J n NUCLEAR CA ARLRIGHT 2 (RETIRE) -43 N FCS$1L Flis EAT 0N 2 (RETIRE) -26 W FOSSIL b MISS STAfMD 0!L 102 (RETIRE)- -31 W FCSSIL GA %gHa 2. &de -Jso A.kx1-w ALABA:14 CEORCIA CULF MISS SYSTEM b ................ ....... ....... ....... ....... .......
LOAD u 9683 15215 1735 1624 27989 7
NL' CLEAR -d 1688 3342 'Ic o 6 3 5538 - 2 0 1 14.98 19.83 3.20 9.f3 15.78 I FOSSIL -d 7431 11714 2173 2349 23334 I 65.66 611.37 96.53 96.33 66.58 PEAKING:
b C0?3 TURB -d 0 946 31 i 997 ,
1 J.fi 4.98 1.33 6.fi 2.84 r HY'JO -u 1614 1575 i i 3189 1 14.72 8.12 8.23 8.fi 9.19 -
SEPA HTCR0 -N 31J 1231 23 69 1648
< 1 2.75 6.34 1.69 3.24 4.79
' TOTAL -N 1924 3772 69 69 5534 1 17.07 19.44 3.07 3.24 16.65 OTFER:
I INTERUP L3 -d 211 0 9 0 211 AEC -d G 6 9 i i
, S?.EFA -d 0 9 i 8 i L TV4 -d 47 75 9 9 143 SAVANNAM -W 8 3 9 9 0 g SCE0G -W G 0 i 9 9 FPC -d 0 9 9 8 i MSU -M'J 6 i i i 9
- CRISP CTI -W G 9 i 9 i L Ml?C -d i 3 8 i f TOTAL -W 153 75 9 9 351 g i 2.29 J.39 6.43 0.12 1.38 TOTAL CAFAB -d 11271 19433 2248 2127 35049 RESERVES -S 1591 4188 513 S3 7J69 4- I 38.97 25.26 16.44 27.53 29.57 13/18/79
(
S4
=
J5 otto I8703 z 3988 343H9 Gs9 -
\h]b \5 l ydem 2.2.92 % 2 2 ..*7 6 "Z.
C p acp ear 3 _
NOV o v 1979
s.
C CE.NEFATION E:PANSI3 FLAN 79R1(REV3) - (dif.WqO8cde PROFCIED EU]CET W. 20 RECAST PLAN (1983-1989)
(1992-230'C0'.i:N0iNCIFLAN) b PEAX F0t'3 CAPA!!LITYe REEEs.Eie AND CCMF051 TION CF CAPA21LITT (IL'LUE: M SE4 FREFEREC E CUSTOMER LOAD)
MJ M.D I 0F LCAD 1909 CAPA31Llif CHANCES:
,. CA AT24RIGHT 314 (RETIRE) -87 MW FOSSIL a (,0AT RCCX INC 67 N - HIDR 0 CA MITCEELL lt2 (RETIRE) -41 NW FOSSIL CA SCHERER 4 (!21) 404 MW FOSSIL E CULF SCHERER 4 (252) 2f2MJ FOSSIL alSS SCEEEER 4 (252) 262 W FOSSIL
( AlaIANA CEC 4GIA CULF MISS SISTEM g LCAD
- h.' 16954 15616 1799 1681 22868
{ NUCLEM fi 1633 3!42-7CC 9 2 5533- 7M 1 14.98 19.46 f.f# f.33 15.45 FOSSIL -MW 7401 11?96 2372 2251 21214 g I 65.66 62.72 96.82 96.65 67.39 CCM3 TURB -W 9 966 31 5 197 6.fi
( HIERO {J I i.BJ 1614 4.59 1642 1.27 f i 2.79 3256 2 14.22 8.32 3.53 J.il 9.16 SEFA HtDRO -d 3:0 1231 38 69 1683 I I 2.75 6.23 1.55 2.96 4.13 TOTAL 4J l'.24 0639 69 69 59!1 -
17.J7 19.44 2.82 2.96 15.49 p I INTERUP LD WJ 211 8 f i 211 k
AEC -W 9 9 8 8 i SM.E?A -W f f f i f TVA -d 47 75 9 9 143
, S A',' AB AH -MW f f 9 8 9 .
O SCE3G fJ G 8 8 f f FFC -W i 9 8 3 5
-W f f f f
( MSU CRI5PCTY -d f G f 9
I f MISC -NW f f f f f TOTAL - M'.: 258 75 9 9 351 2 2.29 3.38 6.37 G.39 9.93 TOTAL CAPAB -MW 11271 19746 245f 2329 35796
( RESERNEE fJ 1217 4129 651 648 6928 1 12.!9 26.45 34.19 38.55 24.fi g-19CHG:,
lil18179 J50 #r4, \a5 )))
L. 3'i30 4228 '
21.'tfo*Z, .
2 I.5 7 <x , j c . t 4rrsc/%df 3 C
ROV 27 1979
.r-(96c.faf6)
i.
CE';ERATION EIPAMIC1 FLAN 79R1(REV3) -LOIR %O 8<le.
FRCf03ED IJCCEi A2 FCRECA3T FLAN (1920-1989)
(1997-IN4 CC'.T20ECT FLAN)
I PEAX H:JR CAFAIILITT, REiEME3, A'iD CO*?0SITION CF CAPABILITY (D.0L'.IIN0 5EFA PREFIREXE CUST07.ER LOAD) g M AG I 0F LOAD 1998 CA:aEILITT CHAEES:
,4.4 UV.0:ATED 41 783 MW FOSSIL b GA AR N IGHT SA M S (REi!RE) -26 N C07.3 TUR3 ClU CRIST 2 (RETIRE) -23 PW FOSSIL MISS EAIGN 3 (RETIRE) -24 n FOSSIL ALAEAMA CEORGIA CULF MISS SISTEM b Lhkh """"-55 f54h5 5((hh "5555 "5hkk 59955 b NUCLEAR -E 1688 3842-7c0 f 9 5533 - 7Co
% 18.f3 19.48 f.fi 8.fJ 15.15 FOSSIL -5 81S4 11998 2352 2227 24753 b : 67.89 60.83 96.79 96.62 67.83
CO?3 TURB -M'J G 94J 31 8 971 b 1 5.03 4.77 1.26 3.M 2.66 HY[i10 -M 1614 1642 8 9 3256
% 13.39 8.33 f.03 6.f3 8.12 b SEFA HYIRS -M 3rJ 1231~ 38 61 1648
~
2 2.57 6.24 1.56 2.99 4.51 -
-W I TOTAL I
1924 15.96 3313 19.34 69 2.84 2.M 69 5875 16.29 GTHER:
IhTER'JP LD -N 211 8 9 8 211 b AEC -M 9 9 f i f SEE?4 -N 9 8 f f f TVA -N 47 75 9 9 148 b SAVA'MH -N 9 9 9 8 i SCE0G d i 6 i 9 f FPC -W 9 8 9 9 8 b d MSU 9 8 8 8 f CEI!? Cii -G B 3 8 9 9 e MlSC -H 9 6 8 8 0
' TOTAL -n 253 75 9 9 351 I 2.14 f.38 f.37 0.39 9.96 T5TAL CAFAB - 5 12254 19723 2433 2325 34539 g
RE!ER'JES -W 1619 3537 564 563 6573 e 1 15.52 21.16 32.23 32.32 21.96 gg 19/18/79 L 2237 358D9
/7.53 % 58B )4]5 \5 g 19.6 2 %
L 4 rrae/MedT 3 e CW 6 '
,g .
-