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| | number = ML081080189 | | | number = ML081080189 |
| | issue date = 04/28/2008 | | | issue date = 04/28/2008 |
| | title = Vogtle, Units 1 & 2, Request for Additional Information, Review of License Renewal Application, Sections 3.3, 4.3 & 4.7.1 | | | title = Request for Additional Information, Review of License Renewal Application, Sections 3.3, 4.3 & 4.7.1 |
| | author name = Ashley D J | | | author name = Ashley D J |
| | author affiliation = NRC/NRR/ADRO/DLR | | | author affiliation = NRC/NRR/ADRO/DLR |
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Category:Letter
MONTHYEARML24032A0252024-02-0505 February 2024 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200026-2023009 ML24010A0712024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports and Recordkeeping and Suspicious Activity Reporting) ML24031A6102024-01-31031 January 2024 Cyber Security Inspection Report 05200026/2024401 - Public ML24029A0592024-01-30030 January 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report Enclosure 2, GAE-NRCD-RF-LR-000002 P-Attachment, Rev. 0 ML24016A1132024-01-30030 January 2024 Correction of Unit 1 Amendment Nos. 96 and 190 and Unit 2 Amendment Nos. 74 and 173 Adoption of Standard Technical Specifications Westinghouse Plants NL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 IR 05000424/20244032024-01-26026 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000424/2024403; 05000425/2024403 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report ML23347A2092024-01-17017 January 2024 Voluntary Requests for Data, Information, And/Or Observation ML23279A0042024-01-17017 January 2024 Amendment No. 194 to Remove Combined License Appendix C NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23317A2072023-12-22022 December 2023 Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448 ML23335A1222023-12-19019 December 2023 Safety Evaluation Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 (EPID L-2023-LRQ-0002) - Letter ML23353A1702023-12-19019 December 2023 LAR-22-002, TS 3.8.3 Inverters Operating Completion Time Extension Letter ML23310A2922023-12-0707 December 2023 Issuance of Amendment for Exception to Regulatory Guide 1.163, LAR 23 007 ML23339A1812023-12-0707 December 2023 Correction Letter Regarding License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 ML23338A2182023-12-0606 December 2023 Project Manager Reassignment NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23289A1632023-11-28028 November 2023 Letter and Amendment 195 and 192 LAR-23-006R1 TS 3.1.9 More Restrictive Action NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 ML23318A4582023-11-14014 November 2023 Integrated Inspection Report 05200025/2023003 ML23312A3502023-11-14014 November 2023 Integrated Inspection Report 05200026/2023003 ML23306A3552023-11-0808 November 2023 NRC Initial Test Program and Operational Programs Integrated Inspection Report 052000/262023008 ML23268A0572023-11-0707 November 2023 Issuance of Amendments 194 & 191 Request for License Amendment Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) IR 05000424/20234022023-11-0606 November 2023 Security Baseline Inspection Report 05000424/2023402 and 05000425/2023402 IR 05000424/20230032023-10-27027 October 2023 Integrated Inspection Report 05000424/2023003 and 05000425/2023003 ML23291A1512023-10-18018 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 0520026/2024401 ML23263A9852023-10-12012 October 2023 Issuance of Amendments Nos. 221 and 204, Regarding Technical Specification 5.5.11.C, Acceptance Criteria for Charcoal Filter Testing ML23283A0472023-10-0808 October 2023 Neop Letter Dated October 8, 2023 - Vogtle 3 & 4 - TS 3.7.6 License Amendment Request NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report ML23254A2032023-09-13013 September 2023 Initial Test Program and Operational Programs Inspection Report 05200025/2023013 ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report ML23234A2352023-09-0808 September 2023 Request for Withholding Information from Public Disclosure Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events IR 05000424/20230912023-09-0505 September 2023 Plan Units 1 and 2 - NRC Investigation Report 2-2022-006 and Notice of Violation - NRC Inspection Report 05000424/2023091 and 05000425/2023091 ML23234A3002023-09-0101 September 2023 NRC Integrated Inspection Report 05200026/2023003 ML23243A0092023-08-31031 August 2023 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 & 4 (Report 05200025 2023005 & 05200026 2023005) NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) ML23243B0252023-08-30030 August 2023 Exam Corporate Notification Letter (210 Day) IR 05000424/20230052023-08-29029 August 2023 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 & 2 - Report 05000424/2023005 and 05000425/2023005 NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) 2024-02-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARIR 05000424/20244032024-01-26026 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000424/2024403; 05000425/2024403 ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23342A0802023-12-0808 December 2023 NRR E-mail Capture - Request for Additional Information (RAI) - Vogtle, Unit 1 - Review of SG Tube Inspection Report for Refueling Outage 24 (L-2023-LRO-0067) ML23279A2082023-10-0505 October 2023 Issuance of Formal RAIs - Vogtle, Units 1 and 2 - Proposed LAR and Proposed Alternative Request to Revise TS 3.4.14.1 and IST ALT-VR-02 (EPIDs L-2023-LLA-0061 and L-2023-LLR-0023) ML23257A2092023-09-14014 September 2023 NRR E-mail Capture - Formal Issuance of 2nd Round RAIs for Surry Units 1&2 and North Anna Units 1&2 Emergency Plans LAR ML23248A3482023-09-0505 September 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) 6 - Vogtle - TSTF-339 LAR (L-2023-LLA-0053) ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23188A1512023-08-0909 August 2023 Round 2 RAIs for LAR 22-002 TS 3.8.3 Inverters-Operating, Completion Time Extension ML23200A0112023-07-18018 July 2023 Document Request for Vogtle Unit 3 RP Inspection ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23193A7832023-07-12012 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle - TSTF-339 LAR (L-2023-LLA-0053) ML23065A0612023-03-0303 March 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) 14 - Vogtle - AST, TSTF-51, TSTF-471, and TSTF-490 LAR (L-2022-LLA-0096) ML23006A0882023-01-0606 January 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle - Accident Source Term (Ast), TSTF-51, TSTF-471, and TSTF-490 LAR (L-2022-LLA-0096) ML22348A0332022-12-13013 December 2022 NRR E-mail Capture - for Your Action - RAI - Vogtle, Unit 2 - Steam Generator Tube Inspection Report (L-2022-LRO-0120) ML22192A1042022-08-0101 August 2022 Acceptance of Requested Licensing Action Amendment Request Application to Allow Use of Lead Test Assemblies for Accident Tolerant Fuel with Request for Additional Information ML22157A0902022-06-0606 June 2022 NRR E-mail Capture - RAIs - Vogtle, Unit 1 - Refueling Outage (RFO) 1R23 Steam Generator (SG) Tube Inspection Report ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML22026A3942022-01-26026 January 2022 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21350A1032021-12-16016 December 2021 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21321A3762021-11-15015 November 2021 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21033B1072021-02-0202 February 2021 NRR E-mail Capture - RAI - Vogtle Unit 1 - SG Report (L-2020-LRO-0059) ML20338A1512020-12-0303 December 2020 NRR E-mail Capture - RAIs for Vogtle GSI-191 LAR (L-2020-LLA-0182) ML20325A0432020-11-20020 November 2020 NRR E-mail Capture - for Your Review - Draft RAIs for Vogtle GSI-191 LAR (L-2020-LLA-0182) ML20297A3052020-10-22022 October 2020 NRR E-mail Capture - RAIs for Vogtle Relief Request - EPRI Report (L-2020-LLR-0109) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests ML19263A6432019-09-19019 September 2019 NRR E-mail Capture - RAI - Vogtle End State License Amendment Request (LAR) to Revise the Technical Specifications (Tss) for Vogtle, Units 1 and 2 (L-2019-LLA-0148) ML19156A1872019-06-0505 June 2019 NRR E-mail Capture - Request for Additional Information (RAI) for Vogtle Unit 2 Core Operating Limits Report, Cycle 21 ML19105B1632019-04-15015 April 2019 NRR E-mail Capture - Request for Additional Information (RAI) for Voglte TSTF-412 Adoption LAR (L-2018-LLA-0731) ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18236A4452018-08-30030 August 2018 Review of Response to RAI License Amendment Request for Approval to Utilize the Tornado Missile Risk Evaluator to Analyze Tornado Missile Protection Non-Conformances ML18227A0222018-08-15015 August 2018 Notification of Inspection and Request for Information ML18225A3362018-08-13013 August 2018 NRR E-mail Capture - Request for Additional Information Regarding Relief Request VEGP-ISI-RR-03 ML18197A0602018-07-13013 July 2018 Us NRC Final RAI No. 1 for Vogtle 3 and 4 LAR-18-015, Fire Protection System Non-Safety Cable Spray Removal ML18197A1882018-07-13013 July 2018 Us NRC Final Request for Additional Information (Final RAI) No. 4 on Vogtle LAR-17-024, Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes ML18197A1052018-07-13013 July 2018 Us NRC Final Request for Additional Information (Final RAI) No. 1 on Vogtle 3 and 4 LAR-17-043, Containment Pressure Analysis ML18192C0782018-07-11011 July 2018 RAI (LAR 18-009) - Vogtle Electric Generating Plant, Unit 3 and 4 ML18192B7692018-07-11011 July 2018 Us NRC Draft Request for Additional Information (Draft RAI) No. 4 on Vogtle LAR-17-024, Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes ML18136A4972018-06-0101 June 2018 Request for Additional Information, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18109A1152018-05-0101 May 2018 Request for Additional Information ML18079A9572018-03-28028 March 2018 Request for Additional Information Incorporate Seismic Probabilistic Risk Assessment Into the 10 CFR 50.69 Categorization Process (CAC Nos. MF9861 and MF9862; EPID L-2017-LLA-0248) ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML18030B0622018-02-0808 February 2018 Request for Additional Information Reverse Technical Specification 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (CAC Nos. MG0240, MG0241; EPID L-2017-LLA-0295) ML17355A1012018-01-11011 January 2018 Request for Additional Information (CAC Nos. MF9685 and MF9686; EPID L-2017-TOP-0038) ML17354A7822018-01-0505 January 2018 Request for Additional Information Incorporate Seismic Probabilistic Risk Assessment Into the 10 CFR 50.69 Categorization Process (CAC Nos. MF9861 and MF9862; EPID L-2017-LLA-0248) ML17318A0352017-11-22022 November 2017 Request for Additional Information 2024-01-26
[Table view] |
Text
April 28, 2008 Mr. Tom E. Tynan Vice President - Vogtle Southern Nuclear Operating Company, Inc. 7821 River Road Waynesboro, GA 30830
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION, SECTIONS 3.3, 4.3 AND 4.7.1
Dear Mr. Tynan:
By letter dated June 28, 2007, Southern Nuclear Operating Company, Inc., submitted an application pursuant to 10 CFR Part 54, to renew the operating licenses for Vogtle Electric Generating Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information (RAIs) are based on responses that your staff had supplied to earlier questions and are submitted as a follow up to those earlier RAIs.
Items in the enclosure were discussed with members of your staff during a telephone call on April 14, 2008, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3191 or e-mail Donnie.Ashley@nrc.gov. Sincerely, /RA/ Donnie J. Ashley, Sr. Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation
Docket Nos. 50-424 and 50-425
Enclosure:
As stated cc w/encl: See next page
ML081080189 OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR NAME SFigueroa DAshley LLund DATE 4/22/08 04/22/08 04/28/08 ENCLOSURE VOGTLE ELECTRIC GENERATING PLANT UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION The staff has compared the information provided by the applicant related to the time limited aging analyses of reactor vessels of the Vogtle Nuclear Plant (Vogtle), Units 1 and 2, and the information provided in the licensee's response to previous RAIs. The staff has determined that some of the information provided requires clarification or additional information.
RAI-4.3-04 In a letter dated February 21, 2008, the applicant submitted its response to RAI 4.3-4, regarding Table 4.3.1-3, Evaluation of Environmental Effects on Fatigue, of the LRA. The applicant provides the analysis results for cumulative usage factor (CUF) values of the charging nozzle and the surge line hot leg nozzle for different transients. Upon review of the response as well as Table 4.3.1-3 of the LRA, the staff identified several areas where additional information is needed for the staff to complete its review. Please note that questions a through i pertain to the letter response.
- a. Figure 1 and Figure 2, the temperature transient curves for the charging nozzle, are missing from the response. Please provide them.
- b. The locations for the charging nozzle and the surge line hot leg nozzle are at the safe-end region. Confirm the critical fatigue locations are at the safe-end region and provide supporting analysis results.
- c. Sections 4.5.4 and 5.5.4 state that "FatiguePro stress output for each transient was used as guidance to split the transient up into sub-transients." In addition, the FatiguePro stress output, Figure 9, shows that 1-D stress versus time was plotted. Explain how this graph was used in determining the stress intensity and explain why this graph was used instead of the temperature transient curve.
- d. The maximum range of linearized membrane plus bending stress from FatiguePro is taken as 2/3 times the peak stress range for the charging nozzle. What is the basis for the 2/3 factor? In addition, please explain the basis for using 17/20 factor to calculate maximum range of linearized membrane plus bending stress for surge line.
- e. For the charging nozzle, the location of high fatigue usage is protected by the thermal sleeve. Why is the alternating stress so high? Do both analyses use the same peak stress index at that location?
- f. The analyses are based on the 1986 Edition of the ASME Code. Does the FatiguePro analysis, which is based on NB-3600, exclude the linear thermal gradient when computing the strain concentration factor, K
- e. g. For the surge line hot leg nozzle, was a temperature variation in the circumferential direction used in the analysis? If so, how was it accounted for in FatiguePro?
- h. Section 4.5.1 states nominal stress components due to piping loads are multiplied by 1.8 to yield P+Q+F stress components. Describe the basis for using 1.8 factor in the ASME NB-3200 analysis.
- i. The February 21, 2008 response did not address the safety injection nozzle. Indicate whether the safety injection nozzle CUF calculated using FatiguePro would bound the CUF value calculated using the ASME-3200 methodology and provide the basis for the conclusion.
- j. Table 4.3.1-3 of the LRA indicates that the RHR line inlet transition nozzle had a design CUF of 0.95. Explain why the Unit 1 and Unit 2 60-year projected CUF is significantly lower than the design CUF.
RAI 4.7.5-1
- In Southern Nuclear's Letter No. NL-08-0195, dated March 20, 2008 (ADAMS ML080810440), the applicant amended the LRA to provide its TLAA on underclad cracking of those reactor pressure vessel (RPV) components that are made from SA-508, Class 2 low alloy steel forgings with internal stainless steel or nickel alloy cladding. The supplemental LRA Section (LRA Section 4.7.5) states the flaw growth analysis in WCAP-15338 for Westinghouse-designed reactors is bounding for the 4-loop reactors at Vogtle and that this TLAA is acceptable in accordance with the provisions in 10 CFR 54.21(c)(1)(i). In Section 4.1 of the staff's safety evaluation on WCAP-15338, the staff identified two (2) renewal applicant action items on the use of this WCAP for a facility's licensing basis. In the first action item, the staff requested that, for 2-loop and 4-loop Westinghouse PWRs, the renewal applicant should demonstrate that the transients for normal, upset, emergency, faulted, and pressurized thermal shock (PTS) conditions used in WCAP-15338 report bound their plant-specific transients for these conditions; otherwise, the staff requested that the applicant perform similar Section XI flaw evaluations using their plant-specific transients to demonstrate that their Reactor Pressure Vessels (RPV) with underclad cracks are acceptable for 60 years of operation. In the second action item, the staff requested that the applicants referencing the WCAP-15338 report for the RPV components shall ensure that the evaluation of the TLAA is summarily described in the FSAR supplement. The staff has verified that the amendments of the LRA in Letter No. NL-08-0195 provided UFSAR Supplement for this TLAA that satisfies applicant action item No. 2 from the staff's SE on WCAP-15338. However, the staff has determined that the new TLAA section does not address how the transients for normal, upset, emergency, faulted, and PTS conditions used in WCAP-15338 bound their plant-specific transients for these conditions at Vogtle. The staff requests that SNOC provide clarification on how the normal, upset, emergency, faulted, and Pressurized Thermal Shock (PTS) conditions used in WCAP-15338 report bounds the plant-specific transients for these conditions at Vogtle reactor units.
RAI 3.3-1 and 3.4-1
Regarding the use of AMPs (e.g., the External Surfaces Monitoring Program) that credit visual examinations of external polymer (including elastomers, thermoplastics, thermoset, or rubber materials) surfaces, justify your basis for crediting the AMP for aging management of cracking and changes in material properties of the polymetric materials. Clarify how a visual examination alone is capable of detecting a crack or a change in a specific material property (such as a change in a hardness, strength, elasticity or fracture toughness property) in these type of materials.
Letter to T. Tynan from D. Ashley, dated April 28, 2008 DISTRIBUTION
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION, SECTIONS 3.3, 4.3 AND 4.7.1
HARD COPY: DLR RF E-MAIL: PUBLIC SSmith (srs3) SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDciCvib RidsNrrDciCpnb RidsNrrDraAfpb RidsNrrDeEmcb RidsNrrDeEeeb RidsNrrDssSrxb RidsNrrDssSbpb RidsNrrDssScvb RidsOgcMailCenter ------------- DAshley JPLeous SHernandez BSingal TChandler, RII CJulian, RII GMcCoy, RII Vogtle Electric Generating Plant, Units 1 and 2 cc:
Mr. Tom E. Tynan Vice President - Vogtle Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830 Mr. N. J. Stringfellow Manager, Licensing Southern Nuclear Operating Company, Inc. P.O. Box 1295 Birmingham, AL 35201-1295
Mr. Jeffrey T. Gasser Executive Vice President Southern Nuclear Operating Company, Inc. P.O. Box 1295 Birmingham, AL 35201-1295 Mr. Steven M. Jackson Senior Engineer - Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684 Mr. Reece McAlister Executive Secretary Georgia Public Service Commission 244 Washington Street, SW Atlanta, GA 30334 Mr. Harold Reheis, Director Department of Natural Resources 205 Butler Street, SE, Suite 1252 Atlanta, GA 30334 Attorney General Law Department 132 Judicial Building Atlanta, GA 30334
Mr. Laurence Bergen Oglethorpe Power Corporation 2100 East Exchange Place P.O. Box 1349 Tucker, GA 30085-1349 Arthur H. Domby, Esquire Troutman Sanders Nations Bank Plaza 600 Peachtree Street, NE Suite 5200 Atlanta, GA 30308-2216 Resident Inspector Vogtle Plant 8805 River Road Waynesboro, GA 30830 Office of the County Commissioner Burke County Commission Waynesboro, GA 30830 Mr. Stanford M. Blanton, Esq. Balch & Bingham, LLP P.O. Box 306 Birmingham, AL 35201 Ms. Monica M. Caston Vice President and General Counsel Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway P.O. Box 1295 Birmingham, AL 35201-1295 Chalmer R. Myer Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway P.O. Box 1295 Birmingham, AL 35201-1295