ML120580101
| ML120580101 | |
| Person / Time | |
|---|---|
| Site: | Oconee  (DPR-038, DPR-048, DPR-055) |
| Issue date: | 03/30/2012 |
| From: | Stang J Plant Licensing Branch II |
| To: | Gillespie P Duke Energy Carolinas |
| Stang J, DORL/LPL2-1 415-1345 | |
| References | |
| TAC ME7000, TAC ME7001, TAC ME7002, TAC ME7003, TAC ME7005, tac ME7004 | |
| Download: ML120580101 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 30, 2012 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7BOO Rochester Highway Seneca, SC 29672
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1,2, AND 3 - ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT RELATED TO THE PROPOSED EXEMPTION FROM THE REQUIREMENTS OF TITLE 10 OF THE CODE OF FEDERAL REGULATIONS (10 CFR), PART 50.61 and 10 CFR PART 50, APPENDIX G (TAC NOS. ME7000, ME7001, ME7002, ME7003, ME7004, AND ME7005)
Dear Mr. Gillespie:
Enclosed is a copy of the Environmental Assessment and Finding of No Significant Impact related to your application for an exemption dated August 3,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11223A010), for the Oconee Nuclear Station, Units 1,2, and 3, respectively. The application requested an exemption from certain requirements of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," and 10 CFR 50 Appendix G, "Fracture Toughness Requirements." The exemption would allow use of alternate initial reference nil ductility temperature (RT NDT) as described in the Nuclear Regulatory Commission approved topical reports, BAW-230B, Revisions 1-A and 2-A, for determining the adjusted RT NDT of Linde BO weld materials present in the beltline region of the Oconee Nuclear Station, Units 1,2, and 3 reactor pressure vessels.
The assessment is being forwarded to the Office of the Federal Register for publication.
Sincerely, ~
~~g, senior~d Manager Plant Licensing Bra~-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-2B7
Enclosure:
Environmental Assessment cc w/encl: Distribution via Listserv
7590-01-P u.s. NUCLEAR REGULATORY COMMISSION
[NRC-2012-XXXXl DUKE ENERGY CAROLINAS, LLC DOCKET NOS. 50-269, 50-270, AND 50-287 OCONEE NUCLEAR STATION, UNITS 1,2, AND 3 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, issued to Duke Energy Carolinas, LLC (the licensee), for operation of the Oconee Nuclear Station, Units 1,2, and 3, located in Oconee County in South Carolina, in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.12. Therefore, as required by 10 CFR 51.21, the NRC performed an environmental assessment. Based on the results of the environmental assessment, the NRC is issuing a finding of no significant impact.
ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action:
Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix G requires that fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary of light-water nuclear power reactors provide adequate margins of safety during any condition of normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected over its service lifetime, Section 50.61 provides fracture toughness requirements for protection against pressurized thermal shock (PTS) events.
- 2 The proposed action would grant an exemption from certain requirements of 10 CFR, Part 50, Section 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," and 10 CFR 50 Appendix G, "Fracture Toughness Requirements." The exemption would allow use of alternate initial reference nil ductility temperature (RT NOT) as described in the NRC approved topical reports, SAW-2308, Revisions 1-A and 2-A, for determining the adjusted RT NOT of Linde 80 weld materials present in the beltline region of the Oconee Nuclear Station, (ONS) Units 1, 2, and 3 reactor pressure vessels.
The proposed action is in accordance with the licensee's application dated August 3, 2011 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML11223A010).
The Need for the Proposed Action:
The proposed action is needed to allow the licensee to use alternate initial RT NOT (reference nil ductility temperature), as described in the NRC-approved topical reports (TRs),
SAW-2308, "Initial RT NOT of Linde 80 Weld Materials," Revisions 1-A and 2-A, for determining the adjusted RT NOT of Linde 80 weld materials present in the beltline region of the ONS, Units 1, 2, and 3 reactor vessels (RVs)
Environmental Impacts of the Proposed Action:
The NRC has completed its environmental assessment of an exemption. The staff has concluded that the proposed action to allow the use of alternate initial reference nil ductility temperature (RT NOT) as described in the NRC approved topical reports SAW-2308, Revisions 1-A and 2-A for determining the adjusted RT NOT of Linde 80 weld materials present in the beltline region of the ONS, Units 1, 2, and 3 reactor pressure vessels, would not significantly affect plant safety and would not have a significant adverse effect on the probability of an accident occurring.
- 3 The proposed action would not result in an increased radiological hazard beyond those previously analyzed in the updated final safety analysis report for ONS, Units 1, 2, and 3. There will be no change to radioactive effluents that effect radiation exposures to plant workers and members of the public. No changes will be made to plant buildings or the site property. The proposed action does not involve a change to plant building or land areas on the ONS site.
Therefore, no changes or different types of radiological impacts are expected as a result of the proposed exemption.
The proposed action does not result in changes to land use or water use, or result in changes to the quality or quantity of non-radiological effluents. No changes to the National Pollution Discharge Elimination System permit are needed. No effects on the aquatic or terrestrial habitat in the vicinity or the plant, or to threatened, endangered, or protected species under the Endangered Species Act, or impacts to essential fish habitat covered by the Magnuson-Stevens Act are expected. There are no impacts to the air or ambient air quality.
There are no impacts to historical and cultural resources. There would be no noticeable effect on socioeconomic conditions in the region. Therefore, no changes to or different types of non-radiological environmental impacts are expected as a result of the proposed action.
Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action.
The details of the staff's safety evaluation will be provided as part of the letter to the licensee approving issuance of the license amendment.
Environmental Impacts of the Alternatives to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the "no-action" alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar.
-4 Alternative Use of Resources:
The action does not involve the use of any different resources than those previously considered in the Final Environmental Statement for the ONS, Units 1, 2, and 3, dated March 1972, and Final Supplemental Environmental Impact Statement (NUREG-1437, Supplement 2) dated December 1999 (ADAMS Accession No. ML003770518).
Agencies and Persons Consulted:
In accordance with its stated policy, on February 27, 2012, the staff consulted with the South Carolina State official, Mr. Mark Yeager of the South Carolina Department of Health and Environmental Control, regarding the environmental impact of the proposed action. The State official had no comments.
FINDING OF NO SIGNIFICANT IMPACT On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensee's letter dated August 3, 2011. Documents may be examined, and/or copied for a fee, at the NRC's Public Document Room (PDR), located at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available documents created or received at the NRC are accessible electronically through the Agencywide Documents Access and Management System (ADAMS) in the NRC Library at http://www.nrc.gov/reading rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR reference staff by telephone at 1-800-397-4209 or 301-415-4737, or send an e-mail to pdr.resource@nrc.gov.
- 5 Dated at Rockville, Maryland, this 30th day of March 2012.
FOR THE NUCLEAR REGULATORY COMMISSION
~, S~Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Leiter ML120580101 EA FRN ML120580102 OFFICE NRR/LPL2*1/PM NRRlLPL2-1/LA NRRlDLRlRERB/BC IOGC NLO NRRlLPL2-1-BC NRRlLPL2*1/PM I
NAME JStang SFigueroa Almboden i CKanatas
- wi comments NSalgado JStang DATE 03/02112 03/12/12 03/9112 l03/15/12 03/30/12 03/30/12