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{{#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. 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 staff's 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; | : 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 staff's 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. | : 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 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. | : 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. | ||
: 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 | : 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 | ||
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Revision as of 23:00, 4 April 2018
ML18045A189 | |
Person / Time | |
---|---|
Site: | Vogtle |
Issue date: | 03/08/2018 |
From: | Gleaves W C NRC/NRO/DNRL/LB4 |
To: | Whitley B H Southern Nuclear Operating Co |
gleaves b/415-5848 | |
Shared Package | |
ML18045A183 | List: |
References | |
EPID L-2017-LLA-0134, LAR 17-025 | |
Download: ML18045A189 (2) | |
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 staff's 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 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.
- 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