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| | issue date = 03/08/2018 | | | issue date = 03/08/2018 |
| | title = Exemption - Vogtle Electric Generating Plant Unit 4 LAR-17-025 | | | title = Exemption - Vogtle Electric Generating Plant Unit 4 LAR-17-025 |
| | author name = Gleaves W C | | | author name = Gleaves W |
| | author affiliation = NRC/NRO/DNRL/LB4 | | | author affiliation = NRC/NRO/DNRL/LB4 |
| | addressee name = Whitley B H | | | addressee name = Whitley B |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05200025, 05200026 | | | docket = 05200025, 05200026 |
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| =Text= | | =Text= |
| {{#Wiki_filter:SOUTHERN NUCLEAR OPERATING COMPANY, INC. GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SPVJ, LLC MEAG POWER SPVP, LLC CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 DOCKET NO. 52-026 EXEMPTION FROM REGULATIONS SET FORTH IN APPENDIX D OF 10 CFR PART 52 Exemption License No. NPF-92 | | {{#Wiki_filter:SOUTHERN NUCLEAR OPERATING COMPANY, INC. |
| : 1. In a letter dated July 28, 2017, Southern Nuclear Operating Company requested from the Nuclear Regulatory Commission (NRC or Commission) an exemption to allow departures from Tier 1 information in the certified Design Control Document (DCD) incorporated by reference in Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Appendix D, "Design Certification Rule for the AP1000 Design," as part of license amendment request (LAR) 17-025, "Reactor Vessel Head Vent Capacity." | | GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SPVJ, LLC MEAG POWER SPVP, LLC CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 DOCKET NO. 52-026 EXEMPTION FROM REGULATIONS SET FORTH IN APPENDIX D OF 10 CFR PART 52 Exemption License No. NPF-92 |
| For the reasons set forth in Section 3.1 of the NRC staff's safety evaluation, which can be found at Agencywide Documents Access and Management System (ADAMS) Accession Number ML18045A190, the Commission finds that: | | : 1. In a letter dated July 28, 2017, Southern Nuclear Operating Company requested from the Nuclear Regulatory Commission (NRC or Commission) an exemption to allow departures from Tier 1 information in the certified Design Control Document (DCD) incorporated by reference in Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Appendix D, Design Certification Rule for the AP1000 Design, as part of license amendment request (LAR) 17-025, Reactor Vessel Head Vent Capacity. |
| A. the exemption is authorized by law; B. the exemption presents no undue risk to public health and safety; C. the exemption is consistent with the common defense and security; D. special circumstances are present in that the application of the rule in this circumstance is not necessary to serve the underlying purpose of the rule; E. the special circumstances outweigh any decrease in safety that may result from the reduction in standardization caused by the exemption; and F. the exemption will not result in a significant decrease in the level of safety otherwise provided by the design. | | For the reasons set forth in Section 3.1 of the NRC staffs safety evaluation, which can be found at Agencywide Documents Access and Management System (ADAMS) |
| : 2. Accordingly, the licensee is granted an exemption from the certified AP1000 DCD Tier 1 information, allowing changes to the plant-specific DCD Tier 1 information with corresponding changes to Appendix C of the Facility Combined License as described in the request dated July 28, 2017. This exemption is related to, and necessary for, the granting of License Amendment No. 113, which is being issued concurrently. | | Accession Number ML18045A190, the Commission finds that: |
| : 3. As explained in Section 6.0 of the NRC staff's Safety Evaluation (ADAMS Accession Number ML18045A190), this exemption meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the exemption. | | A. the exemption is authorized by law; B. the exemption presents no undue risk to public health and safety; C. the exemption is consistent with the common defense and security; D. special circumstances are present in that the application of the rule in this circumstance is not necessary to serve the underlying purpose of the rule; |
| | |
| | E. the special circumstances outweigh any decrease in safety that may result from the reduction in standardization caused by the exemption; and F. the exemption will not result in a significant decrease in the level of safety otherwise provided by the design. |
| | : 2. Accordingly, the licensee is granted an exemption from the certified AP1000 DCD Tier 1 information, allowing changes to the plant-specific DCD Tier 1 information with corresponding changes to Appendix C of the Facility Combined License as described in the request dated July 28, 2017. This exemption is related to, and necessary for, the granting of License Amendment No. 113, which is being issued concurrently. |
| | : 3. As explained in Section 6.0 of the NRC staffs Safety Evaluation (ADAMS Accession Number ML18045A190), this exemption meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the exemption. |
| : 4. This exemption is effective as of the date of its issuance. | | : 4. This exemption is effective as of the date of its issuance. |
| FOR THE NUCLEAR REGULATORY COMMISSION: | | FOR THE NUCLEAR REGULATORY COMMISSION: |
| /RA/ Anna H. Bradford, Deputy Director Division of New Reactor Licensing
| | /RA/ |
| | | Anna H. Bradford, Deputy Director Division of New Reactor Licensing Office of New Reactors Date of Issuance: March 8, 2018}} |
| Office of New Reactors | |
| | |
| Date of Issuance: March 8, 2018}} | |
Letter Sequence Other |
|---|
EPID:L-2017-LLA-0134, Issuance of Amendment Nos. 114 and 113 and Exemptions - Reactor Vessel Head Vent Capacity (LAR-17-025) (Approved, Closed) |
|
MONTHYEARML18051A6682018-03-0808 March 2018
Attachment - Vogte Electric Generating Plant Unit 3 Amendment 114 (LAR-17-025)
Project stage: Acceptance Review
ML18045A1902018-03-0808 March 2018
Safety Evaluation - Vogtle Electric Generating Plant, Units 3 and 4 LAR-17-025
Project stage: Approval
ML18045A1832018-03-0808 March 2018
Issuance of Amendment Nos. 114 and 113 and Exemptions - Reactor Vessel Head Vent Capacity (LAR-17-025)
Project stage: Request
ML18045A1892018-03-0808 March 2018
Exemption - Vogtle Electric Generating Plant Unit 4 LAR-17-025
Project stage: Other
ML18045A1872018-03-0808 March 2018
Amendment No. 113 - Vogtle Electric Generating Plant Unit 4 LAR-17-025
Project stage: Other
ML18045A1862018-03-0808 March 2018
Amendment No. 114 - Vogtle Electric Generating Plant Unit 3 LAR-17-025
Project stage: Other
ML18045A1852018-03-0808 March 2018
Cover Letter - Vogtle Electric Generating Plant, Units 3 and 4 - Reactor Vessel Head Vent Capacity LAR-17-025
Project stage: Other
2018-03-08
[Table View] |
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Category:Exemption from NRC Requirements
MONTHYEARML24102A2662024-09-11011 September 2024
– Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - FRN
ML24102A2642024-09-0909 September 2024
– Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter
ML24102A2652024-09-0909 September 2024
– Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Exemption
NL-24-0097, Exemption Request: Final Safety Analysis Report Update Schedule2024-03-22022 March 2024
Exemption Request: Final Safety Analysis Report Update Schedule
ML24044A0732024-02-28028 February 2024
Federal Register Notice - Issuance of Multiple Exemptions Regarding 10 CFR Part 73 - January 2024
ML24010A0712024-01-31031 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports and Recordkeeping and Suspicious Activity Reporting)
NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023
Request for Exemption from Security Event Notification Implementation
ML23093A1012023-08-0101 August 2023
Exemption from the Requirements of 10 CFR Part 50, Section 46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors (EPID L-2022-LLE-0020) - Letter
ML23093A1032023-08-0101 August 2023
Exemption from the Requirements of 10 CFR Part 50, Section 46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors (EPID L-2022-LLE-0020) - Exemption
ML23094A1142023-08-0101 August 2023
Exemption from the Requirements of 10 CFR Part 50, Section 68, Criticality Accident Requirements (EPID L-2022-LLE-0022)- Exemption
ML23094A1192023-08-0101 August 2023
Exemption from the Requirements of 10 CFR Part 50, Section 68, Criticality Accident Requirements (EPID L-2022-LLE-0022)- Letter
ML23096A1902023-08-0101 August 2023
Exemption from the Requirements of 10 CFR 50, Appendix K, ECCS (Emergency Core Cooling Systems) Evaluation Models (EPID L-2022-LLE-0021) - Cover Letter
ML23096A1952023-08-0101 August 2023
Exemption from the Requirements of 10 CFR 50, Appendix K, ECCS (Emergency Core Cooling Systems) Evaluation Models (EPID L-2022-LLE-0021) - Exemption
ML22284A1322022-11-22022 November 2022
Exemption - Vogtle LAR-22-003 U4 Electrical ITAAC Consolidation Amendment
NL-22-0583, Request for Fee Exemption for NRC Review Fees for the Licensing Amendment and 10 CFR 50.68 Exemption Submitted for Lead Test Assemblies with Increased Enrichment2022-08-12012 August 2022
Request for Fee Exemption for NRC Review Fees for the Licensing Amendment and 10 CFR 50.68 Exemption Submitted for Lead Test Assemblies with Increased Enrichment
ML21279A1922021-11-23023 November 2021
Draft Federal Register Notice Regarding Exemption from Operator Written Examination and Operating Test for Unit 4 Licenses
ML21320A0442021-11-23023 November 2021
FRN Exemption from the Requirements of 73.55(a)(4) and 73.56(a)(3) (EPID L-2021-LLE-0049)_Rev.1
ML21306A0022021-11-0404 November 2021
Request for Exemption: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load - Draft
ML21299A0272021-10-31031 October 2021
Southern Nuclear Operating Company (SNC) Vogtle Electric Generating Plant (VEGP) Units 3 and 4 Draft Request for Exemption: Protected Area Declaration
ML21237A2382021-10-15015 October 2021
Exemption Unit 3 - Vogtle Electric Generating Plant LAR-21-001: Clarification of ITAAC Regarding Invessel Components
ML21237A2392021-10-15015 October 2021
Exemption Unit 4 - Vogtle Electric Generating Plant LAR-21-001: Clarification of ITAAC Regarding Invessel Components
ML21179A1762021-08-0505 August 2021
FRN for Issuance of Exemption - Farley and Vogtle FSAR Update Exemption - Rev 1
ML21179A1852021-08-0404 August 2021
Exemption - Farley and Vogtle - FSAR Update Exemption - Rev 1
ML21179A2042021-08-0404 August 2021
LTR - Farley and Vogtle - Exemption Transmittal Letter - FSAR Update Exemption - Rev 1. Exemptions from the Requirements of 10 CFR Part 50, Section 50.71(e)(4), Final Safety Analysis Report Update Schedule
ML21071A0532021-07-30030 July 2021
Exemption from the Requirements of 10 CFR Part 50, Section 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors (Exemption)
ML21189A1552021-07-0808 July 2021
Enclosure 1: Request for Exemption from Operator Written Examination and Operating Test for Unit 4 Licenses
ML21189A1562021-07-0808 July 2021
Enclosure 2: Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test
NL-21-0543, Units 1 and 2 and Vogtle Electric Generating Plant - Units 1 and 2, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2021-06-0909 June 2021
Units 1 and 2 and Vogtle Electric Generating Plant - Units 1 and 2, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule
ML20329A3922020-12-0404 December 2020
Exemption from Annual Force-On-Force Exercise Requirement of 10 Cfr Part 73, Appendix B, General Criteria for Security Personnel Subsection VI C.3(I)(1) (EPID L 2020 Lle 0216 (Covid 19))
ML20315A3742020-12-0404 December 2020
Exemption from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel Subsection VI C.3(I)(1) (EPID L-2020-LLE-0183 (COVID-19))
NL-20-1254, Request for One-Time Exemptions from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic2020-11-0606 November 2020
Request for One-Time Exemptions from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic
ML20132A0772020-08-0303 August 2020
Exemption - Vogtle Electric Generating Plant Unit 3 (LAR 20-001)
NL-20-0620, SNC Requests a Temporary Exemption from the Quarterly Fire Brigade Drills and Annual Live Fire Fighting Training Requirements of the Regulation2020-05-22022 May 2020
SNC Requests a Temporary Exemption from the Quarterly Fire Brigade Drills and Annual Live Fire Fighting Training Requirements of the Regulation
ML20126G2662020-05-14014 May 2020
Exemption Request from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI
ML20059N7872020-05-12012 May 2020
Exemption - LAR-19-010: Auxiliary Building Room Heatup
ML20059N7902020-05-12012 May 2020
Exemption - LAR-19-010: Auxiliary Building Room Heatup
ML20066G9042020-03-0606 March 2020
Request for Exemption from 10 CFR Part 50, Appendix E Exercise Requirements
ND-20-0204, Enclosure 1 - Vogtle Electric Generating Plant (VEGP) Unit 4, Exemption Request 10 CFR Part 50, Appendix E Exercise Requirements2020-03-0606 March 2020
Enclosure 1 - Vogtle Electric Generating Plant (VEGP) Unit 4, Exemption Request 10 CFR Part 50, Appendix E Exercise Requirements
ML19350C6272020-01-28028 January 2020
Exemption - Vogtle Electric Generating Plant Unit 3 (LAR 19-015)
ML19350C6612020-01-28028 January 2020
Exemption - Vogtle Electric Generating Plant Unit 4 (LAR 19-015)
ML19361A1092020-01-13013 January 2020
Exemption - Vogtle Electric Generating Plant Unit 4 (LAR 19-003)
ML19361A1192020-01-13013 January 2020
Exemption - Vogtle Electric Generating Plant Unit 3 (LAR 19-003)
ML19337A7412019-12-27027 December 2019
Exemption - Vogtle Electric Generating Plant, Unit 3 (LAR 19-002) Exemption from Regulations Set Forth in Appendix D of 10CFR52
ML19337B1392019-12-27027 December 2019
Exemption - Vogtle Electric Generating Plant Unit 4 (LAR 19-002) Exemption from Regulations Set Forth in Appendix D of 10CFR52
ML19164A2652019-11-15015 November 2019
Exemption - Vogtle Electric Generating Plant, Unit 3 (LAR 19-005)
ML19164A2662019-11-15015 November 2019
Exemption - Vogtle Electric Generating Plant, Unit 4 (LAR 19-005)
NL-19-0801, Quality Assurance Topical Report Submittal, Request for Schedular Exemption - 10 CFR 50.54(a)(3)2019-10-31031 October 2019
Quality Assurance Topical Report Submittal, Request for Schedular Exemption - 10 CFR 50.54(a)(3)
ML19238A3512019-09-27027 September 2019
Exemption - Vogtle Electric Generating Plant, Unit 3 LAR 19-004
ML19239A0892019-09-27027 September 2019
Exemption - Vogtle Electric Generating Plant, Unit 4 LAR 19-004
ND-19-0782, Request for License Amendment and Exemption: Onsite Standby Diesel Generator Loading Changes (LAR-19-015)2019-08-0909 August 2019
Request for License Amendment and Exemption: Onsite Standby Diesel Generator Loading Changes (LAR-19-015)
2024-09-09
[Table view] |
Text
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SPVJ, LLC MEAG POWER SPVP, LLC CITY OF DALTON, GEORGIA VOGTLE ELECTRIC GENERATING PLANT, UNIT 4 DOCKET NO.52-026 EXEMPTION FROM REGULATIONS SET FORTH IN APPENDIX D OF 10 CFR PART 52 Exemption License No. NPF-92
- 1. In a letter dated July 28, 2017, Southern Nuclear Operating Company requested from the Nuclear Regulatory Commission (NRC or Commission) an exemption to allow departures from Tier 1 information in the certified Design Control Document (DCD) incorporated by reference in Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Appendix D, Design Certification Rule for the AP1000 Design, as part of license amendment request (LAR)17-025, Reactor Vessel Head Vent Capacity.
For the reasons set forth in Section 3.1 of the NRC staffs safety evaluation, which can be found at Agencywide Documents Access and Management System (ADAMS)
Accession Number ML18045A190, the Commission finds that:
A. the exemption is authorized by law; B. the exemption presents no undue risk to public health and safety; C. the exemption is consistent with the common defense and security; D. special circumstances are present in that the application of the rule in this circumstance is not necessary to serve the underlying purpose of the rule;
E. the special circumstances outweigh any decrease in safety that may result from the reduction in standardization caused by the exemption; and F. the exemption will not result in a significant decrease in the level of safety otherwise provided by the design.
- 2. Accordingly, the licensee is granted an exemption from the certified AP1000 DCD Tier 1 information, allowing changes to the plant-specific DCD Tier 1 information with corresponding changes to Appendix C of the Facility Combined License as described in the request dated July 28, 2017. This exemption is related to, and necessary for, the granting of License Amendment No. 113, which is being issued concurrently.
- 3. As explained in Section 6.0 of the NRC staffs Safety Evaluation (ADAMS Accession Number ML18045A190), this exemption meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the exemption.
- 4. This exemption is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION:
/RA/
Anna H. Bradford, Deputy Director Division of New Reactor Licensing Office of New Reactors Date of Issuance: March 8, 2018
