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| | number = ML16204A042 | | | number = ML16204A042 |
| | issue date = 07/26/2016 | | | issue date = 07/26/2016 |
| | title = Acceptance Letter, Unacceptable, with Opportunity to Supplement (CAC Nos. MF8061, MF8062, and MF8070) | | | title = Acceptance Letter, Unacceptable, with Opportunity to Supplement |
| | author name = Williams S A | | | author name = Williams S |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Pierce C R | | | addressee name = Pierce C |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000348, 05000424, 05000425 | | | docket = 05000348, 05000424, 05000425 |
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Line 14: |
| | page count = 4 | | | page count = 4 |
| | project = CAC:MF8061, CAC:MF8062, CAC:MF8070 | | | project = CAC:MF8061, CAC:MF8062, CAC:MF8070 |
| | stage = Supplement | | | stage = Acceptance Review |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 26, 2016 Mr. Charles R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. P.O. Box 1295 I Bin 038 Birmingham, AL 35201-1295 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 26, 2016 Mr. Charles R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. |
| | P.O. Box 1295 I Bin 038 Birmingham, AL 35201-1295 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, AND JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 -ACCEPTANCE LETTER, UNACCEPTABLE, WITH OPPORTUNITY TO SUPPLEMENT (CAC NOS. MF8061, MF8062, AND MF8070} | | VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, AND JOSEPH M. |
| | FARLEY NUCLEAR PLANT, UNIT 1 -ACCEPTANCE LETTER, UNACCEPTABLE, WITH OPPORTUNITY TO SUPPLEMENT (CAC NOS. MF8061, MF8062, AND MF8070} |
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| ==Dear Mr. Pierce:== | | ==Dear Mr. Pierce:== |
| By letters dated June 28, 2016, and June 30, 2016 (Agencywide Documents Access and Management System Accession Nos. ML 16180A046 and ML 16182A475, respectively}, Southern Nuclear Operating Company, Inc. (SNC) submitted a request for relief for the Vogtle Electric Generating Plant, Units 1 and 2 (VEGP) and Joseph M. Farley, Unit 1 (FNP). SNC requests relief to eliminate the reactor pressure vessel threads in flange examination requirement for the remainder of the inservice inspection intervals. | | |
| The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of these two relief requests. | | By letters dated June 28, 2016, and June 30, 2016 (Agencywide Documents Access and Management System Accession Nos. ML16180A046 and ML16182A475, respectively}, |
| The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (1 O CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty, without a compensating increase in the level of quality or safety. The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. | | Southern Nuclear Operating Company, Inc. (SNC) submitted a request for relief for the Vogtle Electric Generating Plant, Units 1 and 2 (VEGP) and Joseph M. Farley, Unit 1 (FNP). SNC requests relief to eliminate the reactor pressure vessel threads in flange examination requirement for the remainder of the inservice inspection intervals. |
| In order to make the application complete, the NRC staff requests that SNC supplement the application to address the information requested within 20 days of the date of this letter. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 1 O CFR 2.101, and the NRC will cease its review activities associated with the application. | | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of these two relief requests. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. |
| If the application is subsequently accepted for review, you will be advised C. Pierce of any further information needed to support the staff's detailed technical review by separate correspondence. | | Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (1 O CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty, without a compensating increase in the level of quality or safety. |
| The information requested and associated timeframe in this letter were discussed with your staff on July 25, 2016. If you have any questions, please contact me at (301) 415-1009 or by e-mail at Shawn.Williams@nrc.gov. | | The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. |
| Docket Nos. 50-424, 50-425, 50-348 | | In order to make the application complete, the NRC staff requests that SNC supplement the application to address the information requested within 20 days of the date of this letter. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised |
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| | C. Pierce of any further information needed to support the staff's detailed technical review by separate correspondence. |
| | The information requested and associated timeframe in this letter were discussed with your staff on July 25, 2016. |
| | If you have any questions, please contact me at (301) 415-1009 or by e-mail at Shawn.Williams@nrc.gov. |
| | Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424, 50-425, 50-348 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Supplemental Information Needed cc: Distribution via Listserv Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SUPPLEMENTAL INFORMATION NEEDED RELIEF REQUEST SOUTHERN NUCLEAR OPERATING COMPANY. INC. VOGTLE ELECTRIC GENERATING PLANT, UNITS 1AND2 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 DOCKET NOS. 50-424, 50-425, AND 50-348 By letters dated June 28, 2016, and June 30, 2016 (Agencywide Documents Access and Management System Accession Nos. ML 16180A046 and ML 16182A475, respectively), Southern Nuclear Operating Company, Inc. (SNC or the licensee) submitted a request for relief for the Vogtle Electric Generating Plant, Units 1 and 2 (VEGP) and Joseph M. Farley, Unit 1 (FNP). SNC requested to eliminate the reactor pressure vessel (RPV) threads in flange examination requirement (ASME Code, Section XI, Examination Category B-G-1, Item Number 86.40) for the remainder of the inservice inspection intervals for VEGP and FNP. The following information is needed to continue U.S. Nuclear Regulatory Commission (NRC) staff acceptance review. 1. The VEGP and FNP application states that the technical basis for elimination of the RPV threads in flange examination requirement is contained in Electric Power Research Institute (EPRI) Technical Report 3002007626, March 2016. This referenced EPRI report is not approved by the NRC. For the licensee to use the information in this report as a technical basis, the pertinent information in the EPRI report specific to each application must be provided on the docket. Enclosure C. Pierce of any further information needed to support the staff's detailed technical review by separate correspondence. | | Supplemental Information Needed cc: Distribution via Listserv |
| The information requested and associated timeframe in this letter were discussed with your staff on July 25, 2016. If you have any questions, please contact me at (301) 415-1009 or by e-mail at Shawn.Williams@nrc.gov.
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| Sincerely, /RAJ Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424, 50-425, 50-348
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| ==Enclosure:==
| | SUPPLEMENTAL INFORMATION NEEDED RELIEF REQUEST SOUTHERN NUCLEAR OPERATING COMPANY. INC. |
| | VOGTLE ELECTRIC GENERATING PLANT, UNITS 1AND2 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 DOCKET NOS. 50-424, 50-425, AND 50-348 By letters dated June 28, 2016, and June 30, 2016 (Agencywide Documents Access and Management System Accession Nos. ML16180A046 and ML16182A475, respectively), |
| | Southern Nuclear Operating Company, Inc. (SNC or the licensee) submitted a request for relief for the Vogtle Electric Generating Plant, Units 1 and 2 (VEGP) and Joseph M. Farley, Unit 1 (FNP). SNC requested to eliminate the reactor pressure vessel (RPV) threads in flange examination requirement (ASME Code, Section XI, Examination Category B-G-1, Item Number 86.40) for the remainder of the inservice inspection intervals for VEGP and FNP. |
| | The following information is needed to continue U.S. Nuclear Regulatory Commission (NRC) staff acceptance review. |
| | : 1. The VEGP and FNP application states that the technical basis for elimination of the RPV threads in flange examination requirement is contained in Electric Power Research Institute (EPRI) Technical Report 3002007626, March 2016. This referenced EPRI report is not approved by the NRC. For the licensee to use the information in this report as a technical basis, the pertinent information in the EPRI report specific to each application must be provided on the docket. |
| | Enclosure |
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| Supplemental Information Needed cc: Distribution via Listserv DISTRIBUTION:
| | ML16204A042 OFFICE DORL/LPL2-1 /PM DORL/LPL2-1/PM DORL/LPL2-1 /LA DE/EVIB/BC NAME SWilliams RMartin LRonewicz JMcHale DATE 7/25/16 7/25/16 7/25/16 7/25/16 OFFICE DORL/LPL2-1/BC DORL/LPL2-1/PM NAME MMarkley SWilliams DATE 7/25/16 7/26/16}} |
| PUBLIC LPL2-1 R/F RidsACRS_MailCTR Resource RidsNrrDorl Resource RidsNrrDorlDpr Resource RidsNrrDorllpl2-1 Resource RidsNrrLALRonewicz Resource RidsNrrPMFarleyResource RidsNrrPMVogtle Resource RidsRgn2MailCenter Resource RidsNrrDeEvib Resource RidsNrrDraApla Resource ADAMS Accession No.: ML 16204A042 OFFICE DORL/LPL2-1
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| /PM DORL/LPL2-1/PM NAME SWilliams RMartin DATE 7/25/16 7/25/16 OFFICE DORL/LPL2-1/BC DORL/LPL2-1/PM NAME MMarkley SWilliams DATE 7/25/16 7/26/16 DORL/LPL2-1 | |
| /LA LRonewicz 7/25/16 OFFICIAL RECORD COPY DE/EVIB/BC JMcHale 7/25/16}}
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Letter Sequence Acceptance Review |
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MONTHYEARNL-16-0724, Proposed Lnservice Inspection Alternative VEGP-ISI-ALT-11, Version 1.02016-06-28028 June 2016
Proposed Lnservice Inspection Alternative VEGP-ISI-ALT-11, Version 1.0
Project stage: Request
NL-16-0723, Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 1.02016-06-30030 June 2016
Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 1.0
Project stage: Request
ML16204A0422016-07-26026 July 2016
Acceptance Letter, Unacceptable, with Opportunity to Supplement
Project stage: Acceptance Review
NL-16-1329, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.02016-08-0404 August 2016
Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.0
Project stage: Request
ML16224A1432016-08-23023 August 2016
Acceptance Review Regarding Reactor Vessel Threads in Flange Examination
Project stage: Acceptance Review
ML16256A2212016-09-15015 September 2016
Request for Additional Information
Project stage: RAI
ML16308A4012016-11-16016 November 2016
Followup Request for Additional Information
Project stage: RAI
NL-16-2513, Response to Follow-up Request for Information Regarding Reactor Pressure Vessel Threads-in-Flange Examination Requirement2016-11-23023 November 2016
Response to Follow-up Request for Information Regarding Reactor Pressure Vessel Threads-in-Flange Examination Requirement
Project stage: Request
ML17006A1092017-01-26026 January 2017
Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads Inflange Inspection
Project stage: Other
2016-07-26
[Table View] |
|
|---|
Category:Acceptance Review Letter
MONTHYEARML24276A1132024-10-0202 October 2024
Acceptance Review - License Amendment Request to Revise TS SR 3.4.14.3 and Correct Administrative Oversight
ML24205A2142024-07-23023 July 2024
Acceptance Review - License Amendment Request to Change TS 3.6.5, Containment Air Temperature
ML24178A3762024-07-0101 July 2024
Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations
ML23150A0802023-05-30030 May 2023
Acceptance Review - Vogtle Units 1 and 2 - Proposed LAR and Relief Request to Revise TS 3.4.14.1 and IST ALT-VR-02 (EPIDs L-2023-LLA-0061 and L-2023-LLR-0023)
ML20290A2842022-08-0303 August 2022
Licensee Letter Subject: Finding That All Acceptance Criteria Are Met for Vogtle Electric Generating Plant, Unit 3 Combined License
ML21095A0872021-04-19019 April 2021
Non-Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values
ML20258A1462020-09-0909 September 2020
E-Mail - Acceptance Review - Vogtle GSI-191 Exemption
ML19319A0112019-09-11011 September 2019
Acceptance Letter - Vogtle Electric Generating Plant Units 3 and 4 LAR 19-014, Tornado Missile Protection for Main Steam Vent Stacks and Wall
ML19220A9542019-08-0808 August 2019
LAR 19-013, Pressurizer Surge Line Stratification Evaluation
ML19182A0142019-07-0303 July 2019
Acceptance Letter Vogtle 3 and 4 LAR 19-012
ML19135A1132019-05-15015 May 2019
Acceptance Letter for Vogtle Units 3 and 4, LAR 19-006, Crediting ADS Blowdown First Three Plant Test
ML18156A4432018-06-0707 June 2018
Acceptance Letter for LAR 18-011 ESF Safeguard Actuation TS Applicability Changes
ML18082B0942018-03-27027 March 2018
Acceptance Letter (LAR-17-043) Containment Pressure Analysis
ML18052B0642018-02-26026 February 2018
Acceptance Letter for LAR 18-003
ML18025A7862018-01-31031 January 2018
Acceptance Letter for LAR 17-042
ML18019A3622018-01-25025 January 2018
(LAR 17-037) Acceptance Letter
ML18022B1142018-01-22022 January 2018
Acceptance Letter (LAR 17-044)
ML17319A8472017-11-21021 November 2017
Acceptance Review Letter, License Amendment Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis
ML17166A4332017-06-26026 June 2017
Supplemental Information Needed for Acceptance of Systematic Risk-Informed Assessment of Debris Technical Report
ML17033A0232017-02-14014 February 2017
Request for One-Time Exception to Nuclear Reactor Regulation Office Instructions LIC-109, LIC-101, and LIC-500 Acceptance Review Criteria
ML16245A9142016-09-0101 September 2016
Acceptance Review - NSCW Transfer Pump Vogtle Unit 2
ML16224A1432016-08-23023 August 2016
Acceptance Review Regarding Reactor Vessel Threads in Flange Examination
ML16204A0422016-07-26026 July 2016
Acceptance Letter, Unacceptable, with Opportunity to Supplement
ML15259A3292015-10-0101 October 2015
Acceptance Review
ML15141A0562015-06-0404 June 2015
Acceptance Review
ML15117A4762015-04-30030 April 2015
Acceptance Review Regarding License Amendment to Adopt TSTF-432-A, Rev. 1
ML14343A7812015-01-0808 January 2015
Acceptance Review
ML14288A4472014-11-0404 November 2014
Acceptance Review Regarding Proposed Inservice Inspection Alternative (FNP-ISI-ALT-17, Version 1)
ML14265A2272014-10-24024 October 2014
Acceptance Review Regarding License Amendment to Revise Surveillance Requirement 3.3.2 and Technical Specification 5.6.5
ML13086A0852013-04-26026 April 2013
Acceptance Review Results Regarding Implementation of Risk-Informed Technical Specifications
ML13022A1582013-01-24024 January 2013
Acceptance Review Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742) (N-1-2-1893)
ML12297A2632012-11-0707 November 2012
Acceptance Review
ML12257A0982012-09-25025 September 2012
Acceptance Review - Unacceptable with Opportunity to Supplement (TAC ME9293 & ME9294)
ML12115A0742012-04-20020 April 2012
NRR E-mail Capture - Acceptance Review for VEGP VEGP-ISI-ALT-07 ASME Code Case N-729-1, NL-12-0663
ML12011A0682011-11-23023 November 2011
NRR E-mail Capture - Acceptance Review of Farley IST Program - Relief Request Proposed Alternative RR-P-3, Version 2 (ME7512 and ME7513)
ML11102A0162011-04-12012 April 2011
E-Mail Acceptance Review for TSTF-361-A RHR Lop Testing (TAC ME5853/ME5854)
ML1108800402011-03-28028 March 2011
Email Acceptance Review for License Application NL-11-0280 Steam Generator Water Level Hi-Hi Setpoint Change
ML1102501572011-01-25025 January 2011
Acceptance of Farley Relief Request Dated January 5, 2011
ML1019302772010-07-19019 July 2010
Acceptance Review Regarding License Amendment Request for Technical Specification Table 3.3.1-1
ML1012000882010-04-30030 April 2010
Acceptance of Vogtle Relief Request (VEGP-ISI-ALT-03) Dated April 7, 2010
ML1001205962010-01-12012 January 2010
Email on Acceptance Review for Farley Relief Request
2024-07-23
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24290A1552024-10-16016 October 2024
NRR E-mail Capture - for Your Action - RAI - Farley, Hatch, and Vogtle 1 and 2 - Proposed Alternative Request for Code Case N-572
ML24290A1572024-10-16016 October 2024
NRR E-mail Capture - for Your Action - RAI - Farley and Vogtle 1 and 2 - Alternative Request for Pressurizer Welds (L-2024-LLR-0047)
ML24289A2002024-10-15015 October 2024
NRR E-mail Capture - for Your Action - RAI - Proposed License Amendment Request (LAR) for Vogtle Electric Generating Plant, Units 3 and 4 TS 3.7.6 Action E and SR 3.7.6.5 (L-2024-LLA-0083)
ML24271A0052024-09-26026 September 2024
NRR E-mail Capture - for Your Response - RAI - Farley and Vogtle 1 and 2 - Proposed Alternative Request for Steam Generator Welds (L-2024-LLR-0041)
ML24227A0512024-08-14014 August 2024
August 14, 2024 - Request for Additional Information - Farley, Units 1 and 2 - Proposed LAR to Revise TS SR 3.6.6.8 Frequency
ML24199A1592024-07-17017 July 2024
NRR E-mail Capture - Request for Additional Information - Vogtle 3 and 4 - Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Report
ML24179A1242024-06-27027 June 2024
ISFSI Request for Information (2024)
ML24143A0412024-05-28028 May 2024
Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions
ML24100A7842024-04-0909 April 2024
NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle, Units 3 and 4 - Alternative Request for Explosively Actuated Valves (L-2023-LLR-0016)
ML24072A3982024-03-12012 March 2024
NRR E-mail Capture - for Your Action - Second Round Request for Additional Information (RAI) - Vogtle, Unit 1 - SG Tube Inspection Report - 1R24 (L-2023-LRO-0067)
ML24037A1362024-02-0606 February 2024
RP DLR Feb. 2024
ML24037A1352024-02-0505 February 2024
E-mail
IR 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)
ML23243A9952023-08-31031 August 2023
Request for Baseline RP Inspection
ML23236A0022023-08-22022 August 2023
NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR
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)
ML23095A0832023-04-0505 April 2023
NRR E-mail Capture - for Your Action - RAI - Farley - Containment Isolation Valves, Surveillance Requirement 3.6.3.5 LAR (L-2022-LLA-0189)
ML23086A0232023-03-24024 March 2023
NRR E-mail Capture - for Your Action - Draft RAIs - Farley Surveillance Requirement (SR) 3.6.3.5 License Amendment Request (LAR) (L-2022-LLA-0189)
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)
ML23003A8092023-01-0303 January 2023
NRR E-mail Capture - for Your Action - RAI - Farley - ISI Alternative FNP-ISI-ALT-05-05 (L-2022-LLR-0068)
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)
ML22334A1482022-11-30030 November 2022
NRR E-mail Capture - for Your Action - RAI - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098)
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
ML22123A1782022-05-0303 May 2022
NRR E-mail Capture - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program
ML22123A1802022-05-0303 May 2022
NRR E-mail Capture - Correction - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program
ML22112A0892022-04-22022 April 2022
NRR E-mail Capture - Draft RAIs for Farley LAR Re. TS 5.5.17
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
ML21321A3772021-11-16016 November 2021
NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal
ML21321A3762021-11-15015 November 2021
NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR
ML21321A3752021-11-10010 November 2021
NRR E-mail Capture - Draft RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal
ML21127A1132021-05-0606 May 2021
Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2021012 and 05000364/2021012
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)
ML21012A3242021-01-12012 January 2021
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 26, 2016 Mr. Charles R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
P.O. Box 1295 I Bin 038 Birmingham, AL 35201-1295
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2, AND JOSEPH M.
FARLEY NUCLEAR PLANT, UNIT 1 -ACCEPTANCE LETTER, UNACCEPTABLE, WITH OPPORTUNITY TO SUPPLEMENT (CAC NOS. MF8061, MF8062, AND MF8070}
Dear Mr. Pierce:
By letters dated June 28, 2016, and June 30, 2016 (Agencywide Documents Access and Management System Accession Nos. ML16180A046 and ML16182A475, respectively},
Southern Nuclear Operating Company, Inc. (SNC) submitted a request for relief for the Vogtle Electric Generating Plant, Units 1 and 2 (VEGP) and Joseph M. Farley, Unit 1 (FNP). SNC requests relief to eliminate the reactor pressure vessel threads in flange examination requirement for the remainder of the inservice inspection intervals.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of these two relief requests. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (1 O CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty, without a compensating increase in the level of quality or safety.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that SNC supplement the application to address the information requested within 20 days of the date of this letter. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised
C. Pierce of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated timeframe in this letter were discussed with your staff on July 25, 2016.
If you have any questions, please contact me at (301) 415-1009 or by e-mail at Shawn.Williams@nrc.gov.
Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424, 50-425, 50-348
Enclosure:
Supplemental Information Needed cc: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED RELIEF REQUEST SOUTHERN NUCLEAR OPERATING COMPANY. INC.
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1AND2 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 DOCKET NOS. 50-424, 50-425, AND 50-348 By letters dated June 28, 2016, and June 30, 2016 (Agencywide Documents Access and Management System Accession Nos. ML16180A046 and ML16182A475, respectively),
Southern Nuclear Operating Company, Inc. (SNC or the licensee) submitted a request for relief for the Vogtle Electric Generating Plant, Units 1 and 2 (VEGP) and Joseph M. Farley, Unit 1 (FNP). SNC requested to eliminate the reactor pressure vessel (RPV) threads in flange examination requirement (ASME Code,Section XI, Examination Category B-G-1, Item Number 86.40) for the remainder of the inservice inspection intervals for VEGP and FNP.
The following information is needed to continue U.S. Nuclear Regulatory Commission (NRC) staff acceptance review.
- 1. The VEGP and FNP application states that the technical basis for elimination of the RPV threads in flange examination requirement is contained in Electric Power Research Institute (EPRI) Technical Report 3002007626, March 2016. This referenced EPRI report is not approved by the NRC. For the licensee to use the information in this report as a technical basis, the pertinent information in the EPRI report specific to each application must be provided on the docket.
Enclosure
ML16204A042 OFFICE DORL/LPL2-1 /PM DORL/LPL2-1/PM DORL/LPL2-1 /LA DE/EVIB/BC NAME SWilliams RMartin LRonewicz JMcHale DATE 7/25/16 7/25/16 7/25/16 7/25/16 OFFICE DORL/LPL2-1/BC DORL/LPL2-1/PM NAME MMarkley SWilliams DATE 7/25/16 7/26/16
