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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
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{{#Wiki_filter:a jpl Nb-{2 /d5- 04/95 4- TROUTMAN SANDERS _ -
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NAf80NS8ANK PLAZA 600 PEACHTREE STREET, N E. - suite S200 ATLANTA. GEORGIA 30308 @ 8 TELE PHONE 404-885 3000 *95 W -7 P 1 :57 FACSIMILE 404 886 3900 moMAS L PENLANQ JR. . . I CT 404 885-3471 April 6,1995 00CKEilNG : . ! k '<' i C E BRcmCii Administrative Judge Peter B. Bloch, Chairman Administrative Judge James H. Carpenter Administrative Judge Thomas D. Murphy Atomic Safety and Licensing Board (Georgia Power)
U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Rc: Vogtle Electric Generating Plant, Units 1 and 2 License Amendment (Transfer to Southern Nuclear) ASLBP No. 93-671-01-OLA-3.
Dear Sirs:
Please find enclosed a copy of an April 6,1995, letter from Mr. H. Allen Franklin of Georgia Power Company to the Commissioners. Mr. Franklin's letter requests issuance of the license amendments for Plant Vogtle - Units 1 and 2 and Plant Hatch - Units 1 and 2, granting operating authority to Southern Nuclear Operating Company, at this time.
Very truly yours, 1'
Thomas L. Penland, Jr.
TLP:pcw Enclosure cc: Service List 9504170254 950406
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April 6, 1995
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s Ivan Selin, Chairman Kenneth C. Rogers, Commissioner Gail de Planque, Commissioner One White Flint North 11555 Rockville Pike Rockville, Maryland.20852 RE: Vogtle Electric Generating Plant, Units 1 and 2; Edwin 4
I. Hatch Nuclear Plant, Units 1 and 2 -- Request for Commission Action on Transfer of Operational Authority to Southern Nuclear Ooeratina Company
Dear Chairman Selin and Commissioners Rogers and de Planque:
The purpose of this letter is to request'that the Commission authorize the NRC Staff to take the necessary actions at this time to issue license amendments approving Southern Nuclear.
Operating Company's (" Southern Nuclear") becoming the exclusive operating licensee for the Vogtle Electric Generating Plant and the Edwin I. Hatch Nuclear Plant. 'The NRC Staff has made the requisite factual findings to take such actions at this time.
Issuance of the amendments is permitted under NRC's rules even though there has been a request for a hearAng and intervention has been allowed.
This matter has been pending-before the NRC since September, 1992, and it is time to resolve it. We request the NRC Staff be directed to finalize its significant hazards determination and issue the amendments with the consent of the Commission, with the i
i pending Atomic Safety and Licensing Board hearing on the amendments to continue after the amendments have been issued.
Backaround.
'As early as May 1988, Georgia Power Company (" Georgia Power") and Alabama Power Company ("APC") began discussions with the NRC Staff concerning a proposal to consolidate the operations of the three nuclear plants (six units) within The Southern Company system (Plants Hatch, Vogtle and Farley) into a single
.-_ _ _ _ ___ ____ ~. _ . . _ _ _ . _
i l
. . l GeorgiaPower d April 6, 1995 ;
Page 2 j operating subsidiary of the Southern company.F Similar consolidations had taken place, or were underway, in other utility systems with operating nuclear power plants. The Southern company and its licensees envisioned the combination of
- the personnel and other resources dedicated to nuclear operations within a single corporate team. An environment would be created to enhance the potential for continued improvement in the overall l safety, reliability and cost-effectiveness of these facilities. i A single purpose organization dedicated to excellence in nuclear power plant operations and less distracted by other electric
, utilityfoperations, it was believed, would realize substantial
- benefits for the facilities' owners and the public.
On May 6, 1991, APC submitted an application to amend the Plant Farley license amendments to allow Southern Nuclear to operate those units. No one requested a hearing regarding that license amendment application. On November 22, 1991, the NRC Staff issued the Plant Farley license amendments authorizing Southern Nuclear to become the exclusive operating licensee of 3
that plant.
With respect to Plants Hatch and Vogtle, Georgia Power and its co-owners submitted applications to amend the licenses of 1
those plants on September 18, 1992, to transfer operational authority to Southern Nuclear. These requests are still pending.
- The proposed amendments would have no effect on the ownership of ,
4 the plants. Southern' Nuclear would, through contractual !
arrangements with Georgia Power, become the exclusive operator of j q the facility. On-site personnel would be transferred from i
Georgia Power to Southern Nuclear. Georgia Power officers- j responsible for licensed activities would become solely Southern j Nuclear officers. For example, the current Georgia Power !
Executive Vice President would no longer be an officer of Georgia Power reporting directly to the Georgia Power Chief Executive
. Officer, but would, as President of Southern Nuclear, report to )
the Southern Nuclear Board of Directors relative to licensed ,
activities.F "
FP lant Farley is wholly owned by APC; Plants Hatch and !
Vogtle are each co-owned by GPC, Oglethorpe Power-Corporation, the Municipal Electric Authority of Georgia and the City of Dalton, Georgia.
F Southern Nuclear currently provides nuclear support '
services to Georgia Power for Plants Hatch and Vogtle, pursuant to-a services agreement. Operations personnel and officers responsible for the plants are employees of Georgia Power. These officers also are officers of Southern Nuclear. ;
i i
~
i mn i
GeorglaPowerd April o, 1995 Page 3 Notice of the Application and proposed finding of no significant hazards considerations for each Plant's application was published in the Federal Register on October 14, 1992. 57 Fed. Reg. 47127, 47131 and 47135.F On November 3, 1992, the NRC Staff noticed the issuance of an " Environmental Assessment and Finding of No Significant Impact" in connection with each of the proposed license amendments. 57 Fed. Reg. 49724. In those Environmental Assessments, the Commission, through' authority delegated to the staff, concluded that the proposed license amendments would result in no radiological or nonradiological environmental impact.
The license amendment applications for Hatch and Vogtle are patterned on and similar to the Plant Farley application.
However, in the case of Plant Vogtle, an ex-employee filed a-request for a hearing.F By order dated February 18, 1993, the Atomic Safety and Licensing Board (" Licensing Board") granted standing to the petitioner and admitted one contention.F Georgia Power's appeal of that order was denied. CLI-93-16, 38 NRC 25 (1993).
The Intervenor has asserted two factual bases in support of his contention. The first basis is an allegation that Georgia Power illegally transferred the Vogtle licenses to Southern Nuclear in the 1988-90 time frame. This allegation had been previously investigated by the NRC Staff in response to a September, 1990 Section 2.206 petition filed by the same individual. In a partial decision, the Director of the Office of Nuclear Reactor Regulation found that no unauthorized transfer of the Vogtle license occurred, that the Georgia Power nuclear F
The Staff also noted that the transfer of any right under the operating licenses is subject to NRC approval pursuant to 10 C.F.R. $ 50.80(a), and that such approval was proposed to be giv'en through an Order.
F Egg Georaia Power Company (Vogtle Electric Generating Plant, Units 1 and 2) Docket No. 50-424-OLA-3/50-425-OLA-3, ASLBP No. 93-671-01-OLA-3. No intervention was sought relative to the Hatch amendments.
F The contention admitted by the Board is:
The license to operate the Vogtle Electric Generating Plant, Units 1 and 2, should not be transferred to Southern Nuclear Operating Company, Inc., because it lacks the requisite character, competence and integrity, as well as the necessary candor, truthfulness and willingness to abide by regulatory requirements.
T
, GeorgiaPower d 3py11 ,, 1,33 Page 4 facilities are being operated in accordance with NRC regulations and do not endanger the health and safety of the public, and that none of the issues decided in his decision called into question
, the licensee's character, competence, fundamental trustworthiness, or commitment to safety.F The Commission subsequently vacated this Partial Director's Decision. The Commission observed that the issues raised in the 2.206 petition generally concern the integrity of Georgia Power and Southern Nuclear officers and the corporation organization responsible for operation of Plant Vogtle and Plant Hatch and instructed the Staff to defer determination:
l Under the peculiar circumstances of this case, rather than address the issues in the Section 2.206 petition
; in a piecemeal fashion, the Staff should reach a l determination of all issues in an integrated manner i
after consideration of the remaining matters raised in the Section 2.206 petition and the outcome of the I
transfer proceeding. CLI-93-15, 38 NRC 1, 3 (1993).
l However, the Commission specifically noted that it expressed "no I view on the soundness of the Staff's analysis" of the illegal transfer allegation. CLI-93-15, 38 NRC 1, 3 (1993). After extensive discovery, a hearing was held before the Licensing Board on this allegation in January, 1995. At the hearing the Staff adopted and affirmed the earlier Director's Decision. The Staff concluded that Georgia Power did not transfer control of operating licenses for Plant Vogtle, nor mislead the NRC in any material respect regarding control of the operation of the Vogtle facilities. NRC Staff Proposed Findings of Fact, Conclusions of Law, and Order in the Form of An Initial Decision at 60 (March 6, 1995).
The second factual basis for the contention admitted by the Licensing Board involves a group of allegations which now have been the subject of exhaustive review by the NRC's Office of Investigations and Office of Enforcement. The allegations are that Georgia Power intentionally made various false or incomplete statements to the NRC concerning the Vogtle emergency diesel generators ofter a March 20, 1990 Site Area Emergency at the plant. The Intervenor initially submitted these allegations to the NRC in 1990 and 1991, before the license amendment applications were filed by Georgia Power. As a result, the alleged false statements which Intervenor has identified to support his contention are the same as the NRC Staff has investigated and resolved in an enforcement action (EA 93-304).
F SAA Partial Director's Decision Pursuant To 10 CFR 2.206, DD-93-08, 37 NRC 314 (1993).
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4 GeorgiaPower A April 6, 1995
) Page 5 The Staff, in a letter date3 February 13, 1995, from Mr. l l James L. Milhoan, stated that, upon payment of a proposed civil i
penalty, resolved.?theGeorgia enforcement action would be considered fully j l Power has paid the penalty. Additionally, j i
the Staff concluded that, subject to commitments made by Georgia '
) Power and one involved individual, the Staff has "no present l concerns with the character and integrity" of the involved I individuals or Georgia Power Company arising out of the events
! which gave rise to the enforcement action. On April 3, 1995, 4
the NRC Staff profiled testimony with the Licensing Board which i presents the Staff's overall conclusion regarding the allegation
! of the intentional providing of inaccurate, incomplete or j misleading information:
! The NRC Staff concluded that inaccurate and incomplete
! information was provided to the NRC by GPC managers
] regarding the diesel generator testing after the SAE, 1
and to this extent, the allegation is partially 3 substantiated. These deficiencies resulted from'the performance failures by various GPC managers who were notified of problems but failed to take steps necessary to assurn that the requirements of 10 C.F.R. S 50.9 i were met. The NRC Staff did not conclude that GPC j
1 intentionally provided inaccurate, incomplete or misleading information. Therefore, the. allegation that i
senior GPC managers intentionally provided inaccurate i
; and incomplete information to the NRC was not substantiated.
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NRC's License Amendment Procedures l The NRC's well established practice on license amendments is
! to (1) consider any public comments, (2) review the licensee's
! safety evaluation (as it has in this case), and (3) make a j decision on the amendment request.F A formal " final j determination" of no significant hazards considerations is j F The Commission apparently reviewed the office of j
i' Investigations report and Office of Enforcement recommendation prior to making a decision on enforcement action. Egg, CLI-94-5, 39 NRC 190, 200 (...the Commission's decision on enforcement is
] imminent. . . ) , 202 (...the Commission's deliberations on possible i
enforcement action...) (1994)
FT here are some exceptions to this standard procedure, such as situations where notice and comment opportunities are j
l curtailed due to exigent circumstances (e.g., a change clearly more reliable and safe and with a limited window of opportunity
, for installation). 51 Fed. Reg. 7767 (March 6, 1986).
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'GeorgiaPower d April 6, 1995 i
Page 6 j
- j. normally not made, unless there is a request for a hearing. In that case, the NRC Staff prepares a " final determination" which j
considers the request and the public comments, makes the necessary findings, and concludes that the license amendment i either does or does not constitute a significant hazards '
j consideration. If a finding of no significant hazards consideration is made, any hearing required pursuant to a petition to intervene is then held after the amendment has been issued.F l
i J Reauest for License n=enenents Issuance and c-:--ission consent.
j j
Georgia Power requests that the Commission remove the ambiguity associated with the commission's observations in the
] 2.205 proceeding quoted above. 'The Commission's observations could be misconstrued as instructing the Staff to defer issuance
}
of a final "no significant i;azards" determination until after the
- Licensing Board issues its decision in the amendment' proceeding.
j The Commission's desire to defer Staff resolution on the 2.206 petition could not have been intended to preclude the Staff from exercising its separate and distinct responsibilities under Sections 50.92(c) and 2.105. Removal of.the ambiguity would {
I l enable the Staff to complete the actions'necessary to issue the Plant Hatch and Plant Vogtle license amendments at this time. ;
' The NRC Staff can and should now complete a final determination of no significant hazards considerations for the same reasons on j i
which the Staff based its decision to issue the Plant Farley j license amendments and on the basis of its review of the allegations proceeding.
which form the basis for the contention in the Vogtle i 1
The Staff's review' concludes that no basis exists i for concluding that the proposed transferee, Southern Nuclear, '
lacks the requisite character, competence, integrity, i
j truthfulness and candor to operate a nuclear facility. In the meantime, the deleterious impact of delay to the Company and its l employees might not be quantifiable, but it is real. As tho'
{ Licensing Board observed in November, 1993: ;
3
....further delay in the issuance of the license amendments I j
will delay the realization of the benefits of the consolidation, including; i !
F l
i A " transfer of control" of a license invokes only the j- .of hearing the AtomicrightsEnergy afforded Act.by the first sentence of Section 189a(1).
i The Act does not require the offer of a prior hearing on an application to transfer control before the i
transfer is made effective. Lona Island Liahtina Connany (Shoreham Nuclear Power Station, Unit 1) CLI-92-4,. 35 NRC 69, 77 l (1992).
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April 6, 1995 GeorbiaPower A Page 7 <
(a) _a single-purpose organization dedicated solely-toL excellence in nuclear power plant 1 operations, undistracted by the demands of other electric.
utility operations;.
(b) consistency in-personnel' policies resulting in cost savings and efficiencies; a
(c) the ability to attract and retain nuclear ~
professionals by offering them an opportunity to !
build a career within an_ operating organization I responsible for the operation and maintenance of multiple nuclear plants; (d) an increase in Southern Nuclear's effectiveness through recognition-by the nuclear community of its responsibility as.the exclusive _ operator of a three nuclear plants.... (LBP-93-22 at 14, quoting an affidavit of Mr. W. George Hairston, III,
-Georgia Power's-Executive Vice President-Nuclear)' l l
, Two and a half years have passed since the license- _
l
, amendments apnlications were filed. Virtually no change in the l personnel and management who will control the day-to-day operation of Plant Hatch and Plant Vogtle will result upon the issuance of the license amendments. The NRC Staff-has stated its views, which support amendment issuance.
In light of this substantial historic review byfthe NRC Staff and the Commission's deliberations on the now-resolved enforcement action, the Commission should now authorize the Staff to: complete its action and issue the license amendments allowing the transfer'from Georgia Power to Southern Nuclear.- Georgia Power Company respectfully requests this' action at this time.
Very truly yours, H. Allen Franklin HAL:jl 1
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N0*75
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GeorgiaPower d April 6, 1995 Page 8 l I
j .xc: Service List ASLBP No. 93-671-01-OLA-3 Georcia Power Comoany Mr. J. Beasley, Jr..
Mr. M. Shelbani NORMS
.; I U.S. Nuclear Reculatory Commission j Mr. James Taylor, Executive Director of Operations
~
; Mr. S.D. Ebneter, Regional Administrator j Mr. D.S. Hood, Licensing Project Manager, NRR J
Mr. B.R. Bonser, Senior Resident Inspector, Vogtle 4
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