Edwin I. Hatch Nuclear Plant, Unit No. 2; Southern Nuclear Operating Company, Inc.; Operating License No. NPF-5; Environmental Assessment and Finding of No Significant Impact, 65415-65416 [E8-26133]

Download as PDF Federal Register / Vol. 73, No. 213 / Monday, November 3, 2008 / Notices Response to Request sroberts on PROD1PC70 with NOTICES The request for an extension to the comment period is approved until December 31, 2008. We agree that Addendum A is a needed improvement to the ASME/ANS standard RA-S–2008 and would result in a more effective and efficient implementation of both the standard and RG 1.200. Consequently, we are extending the public review and comment period to December 31, 2008, and the final publication of Revision 2 to RG 1.200 to March 31, 2009. ASME and ANS have cooperated worked to develop this PRA standard in support of NRC’s PRA quality initiative/ plan in support of risk-informed regulation (SECY–04–0118, ‘‘Plan for the Implementation of the Commission’s Phased Approach to Probabilistic Risk Assessment Quality,’’ dated July 13, 2004). This plan identified the various technical guidance documents (e.g. , standards) needed to support the various risk-informed activities. Requests for technical information about DG–1200 may be directed to the NRC contact, Mary Drouin at (301) 415– 6675 or e-mail to Mary.Drouin@nrc.gov. Electronic copies of DG–1200 are available through the NRC’s public Web site under Draft Regulatory Guides in the ‘‘Regulatory Guides’’ collection of the NRC’s Electronic Reading Room at http://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also available in ADAMS (http:// www.nrc.gov/reading-rm/adams.html), under Accession No. ML081200566. In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR), which is located at 11555 Rockville Pike, Rockville, Maryland. The PDR’s mailing address is USNRC PDR, Washington, DC 20555–0001. The PDR can also be reached by telephone at (301) 415–4737 or (800) 397–4205, by fax at (301) 415– 3548, and by e-mail to pdr.resource@nrc.gov. Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them. Dated at Rockville, Maryland, this 29 day of October, 2008. For the Nuclear Regulatory Commission. Andrea D. Valentin, Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E8–26214 Filed 10–31–08; 8:45 am] BILLING CODE 7590–01–P VerDate Aug<31>2005 16:58 Oct 31, 2008 Jkt 217001 NUCLEAR REGULATORY COMMISSION [Docket No. 50–366] Edwin I. Hatch Nuclear Plant, Unit No. 2; Southern Nuclear Operating Company, Inc.; Operating License No. NPF–5; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 46, and Appendix K to Part 50, for Facility Operating License No. NPF–5, issued to Southern Nuclear Operating Company (the licensee), for operation of the Edwin I. Hatch Nuclear Plant, Unit 2 located in Appling County, Georgia. Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessment and finding of no significant impact. Environmental Assessment Identification of the Proposed Action The proposed action would allow the use of Ziron fuel cladding. The proposed action is in accordance with the licensee’s application dated March 21, 2008, as supplemented May 2, August 8, and September 22, 2008. The Need for the Proposed Action The proposed action would allow a small number of lead test assemblies (LTAs) that will include some fuel rods manufactured with a cladding material, called GNF-Ziron, which is similar in composition to Zircaloy-2, but contains a slightly higher iron content than specified in ASTM B350. Irradiation of LTAs with GNF-Ziron fuel rods will enable SNC to acquire in-reactor operating experience with this material. Pursuant to 10 CFR 50.12, ‘‘Specific Exemptions,’’ the licensee has requested an exemption to 10 CFR 50.46, ‘‘acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,’’ that requires, among other items, that ‘‘each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical zircaloy or ZIRLO cladding, must be provided with an emergency core cooling system (ECCS) that must be designed so that its calculated cooling performance following postulated loss-of-coolant accidents conforms to the criteria set forth in paragraph (b) of this section.’’ Appendix K to 10 CFR Part 50, ‘‘ECCS Evaluation Models,’’ requires, among other items, that the rate of energy release, hydrogen generation, and cladding oxidation from the metal/water PO 00000 Frm 00132 Fmt 4703 Sfmt 4703 65415 reaction shall be calculated using the Baker-Just equation. The regulations at 10 CFR 50.46 and 10 CFR Part 50, Appendix K, make no provisions for use of fuel rods clad in a material other than zircaloy or ZIRLO. The proposed action would allow the licensee to irradiate a small number of LTAs using fuel rods clad with Ziron alloy in Hatch, Unit 2. Since the material specifications of the Ziron alloy differ from the specification for zircaloy or ZIRLO, a plant-specific exemption is required to support the use of the eight assemblies. Environmental Impacts of the Proposed Action The NRC has completed its safety evaluation of the proposed action and concludes that application of 10 CFR 50.46, and Appendix K to 10 CFR Part 50, is not necessary for the licensee to achieve its underlying purposes. The details of the NRC staff safety evaluation will be provided in the exemption that will be issued as part of the letter to the licensee approving the exemption to the regulation. The staff has concluded that such a change would not adversely affect plant safety, and would have no adverse effect on the probability of any accident. For accidents that involve damage or melting of the fuel in the reactor core, the fuel rod integrity of GNF-Ziron cladded fuel has been shown to be similar to zircaloy cladded fuel; therefore, the probability of an accident will not be affected. For accidents in which the core remains intact, the use of GNF-Ziron cladding will not have a significant effect on the mix of fission products that could be released in the event of a serious accident; thus, the previously analyzed accident dose consequences remain bounding. Regulatory limits on radiological effluent releases are independent of the type of fuel cladding used. The requirements of 10 CFR 50.36a, Appendix I to 10 CFR Part 50, and 40 CFR Part 190, as well as the plant’s Technical Specifications ensure that the release of radioactive gaseous, liquid, and solid waste to unrestricted areas are kept to ‘‘as low as reasonably achievable’’ (ALARA) levels. The licensee’s radioactive waste processing system will collect, control, process to reduce the amount of radioactivity, and discharge the waste in accordance with regulatory limits. Therefore, the staff concluded that during routine operations, there will be no significant increase of radiological effluents released into the environment as a result of the proposed exemption request. No significant increase in the allowable individual occupational radiation E:\FR\FM\03NON1.SGM 03NON1 65416 Federal Register / Vol. 73, No. 213 / Monday, November 3, 2008 / Notices exposure will occur. The impact to workers is not expected to change because radiation exposure will be controlled in accordance with the licensee’s radiation protection program, the ALARA program, in-plant shielding, the use of temporary shielding, and engineering controls. The use of GNFZiron fuel rods will not change the potential environmental impacts of incident-free transportation of spent nuclear fuel provided the shipping casks are maintained and transported within the Department of Transportation and NRC regulations. Therefore, there are no significant radiological environmental impacts associated with the proposed action. With regard to potential nonradiological impacts, the proposed action does not have a potential to affect any historic sites. It does not affect nonradiological plant effluents and has no other environmental impact. Therefore, there are no significant non-radiological environmental impacts associated with the proposed action. Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action. 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. Alternative Use of Resources The action does not involve the use of any different resources than those previously considered in NUREG–1437, Supplement 4, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants,’’ Supplement 4, Regarding the Edwin I. Hatch Nuclear Plant, Units 1 and 2,’’ dated May 31, 2001. sroberts on PROD1PC70 with NOTICES Agencies and Persons Consulted In accordance with its stated policy, on September 18, 2008, the NRC staff consulted with the Georgia State official, Mr. Jim Hardeman, of the Department of Natural Resources, 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 VerDate Aug<31>2005 16:58 Oct 31, 2008 Jkt 217001 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 letters dated March 21, 2008, as supplemented May 2, August 8, and September 22, 2008. 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 O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, 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. Dated at Rockville, Maryland, this 27th day of October, 2008. For the Nuclear Regulatory Commission. Robert E. Martin, Senior Project Manager, Plant Licensing Branch II–1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E8–26133 Filed 10–31–08; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Sunshine Federal Register Notice AGENCY HOLDING THE MEETINGS: Nuclear Regulatory Commission. DATE: Week of November 3, 2008. PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. (Tentative). This meeting will be webcast live at the Web address—http://www.nrc.gov. * The schedule for Commission meetings is subject to change on short notice. To verify the status of meetings, call (recording)—(301) 415–1292. Contact person for more information: Michelle Schroll, (301) 415–1662. The NRC Commission Meeting Schedule can be found on the Internet at: http://www.nrc.gov/about-nrc/policymaking/schedule.html. The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a reasonable accommodation to participate in these public meetings, or need this meeting notice or the transcript or other information from the public meetings in another format (e.g. braille, large print), please notify the NRC’s Disability Program Coordinator, Rohn Brown, at 301–492–2279, TDD: 301–415–2100, or by e-mail at REB3@nrc.gov. Determinations on requests for reasonable accommodation will be made on a case-by-case basis. This notice is distributed by mail to several hundred subscribers; if you no longer wish to receive it, or would like to be added to the distribution, please contact the Office of the Secretary, Washington, DC 20555 (301–415–1969). In addition, distribution of this meeting notice over the Internet system is available. If you are interested in receiving this Commission meeting schedule electronically, please send an electronic message to dkw@nrc.gov. Dated: October 29, 2008. R. Michelle Schroll, Office of the Secretary. [FR Doc. E8–26215 Filed 10–30–08; 11:15 am] BILLING CODE 7590–01–P Additional Items To Be Considered Week of November 3, 2008 Thursday, November 6, 2008 9:30 a.m. Executive Branch Briefing (Closed— Ex. 1 & 9) (Tentative). 1:25 p.m. Affirmation Session (Public Meeting) (Tentative). b. AmerGen Energy Company, LLC (License Renewal for Oyster Creek Nuclear Generating Station), Docket No. 50–219–LR, Citizens’ Petition for Review of LBP–08–12 PO 00000 Frm 00133 Fmt 4703 Sfmt 4703 E:\FR\FM\03NON1.SGM 03NON1

Agencies

[Federal Register Volume 73, Number 213 (Monday, November 3, 2008)]
[Notices]
[Pages 65415-65416]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-26133]


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NUCLEAR REGULATORY COMMISSION

 [Docket No. 50-366]


Edwin I. Hatch Nuclear Plant, Unit No. 2; Southern Nuclear 
Operating Company, Inc.; Operating License No. NPF-5; Environmental 
Assessment and Finding of No Significant Impact

    The U.S. Nuclear Regulatory Commission (NRC) is considering 
issuance of an exemption from Title 10 of the Code of Federal 
Regulations (10 CFR) Part 50, Section 46, and Appendix K to Part 50, 
for Facility Operating License No. NPF-5, issued to Southern Nuclear 
Operating Company (the licensee), for operation of the Edwin I. Hatch 
Nuclear Plant, Unit 2 located in Appling County, Georgia. Therefore, as 
required by 10 CFR 51.21, the NRC is issuing this environmental 
assessment and finding of no significant impact.

Environmental Assessment

Identification of the Proposed Action

    The proposed action would allow the use of Ziron fuel cladding. The 
proposed action is in accordance with the licensee's application dated 
March 21, 2008, as supplemented May 2, August 8, and September 22, 
2008.

The Need for the Proposed Action

    The proposed action would allow a small number of lead test 
assemblies (LTAs) that will include some fuel rods manufactured with a 
cladding material, called GNF-Ziron, which is similar in composition to 
Zircaloy-2, but contains a slightly higher iron content than specified 
in ASTM B350. Irradiation of LTAs with GNF-Ziron fuel rods will enable 
SNC to acquire in-reactor operating experience with this material. 
Pursuant to 10 CFR 50.12, ``Specific Exemptions,'' the licensee has 
requested an exemption to 10 CFR 50.46, ``acceptance criteria for 
emergency core cooling systems for light-water nuclear power 
reactors,'' that requires, among other items, that ``each boiling or 
pressurized light-water nuclear power reactor fueled with uranium oxide 
pellets within cylindrical zircaloy or ZIRLO cladding, must be provided 
with an emergency core cooling system (ECCS) that must be designed so 
that its calculated cooling performance following postulated loss-of-
coolant accidents conforms to the criteria set forth in paragraph (b) 
of this section.'' Appendix K to 10 CFR Part 50, ``ECCS Evaluation 
Models,'' requires, among other items, that the rate of energy release, 
hydrogen generation, and cladding oxidation from the metal/water 
reaction shall be calculated using the Baker-Just equation. The 
regulations at 10 CFR 50.46 and 10 CFR Part 50, Appendix K, make no 
provisions for use of fuel rods clad in a material other than zircaloy 
or ZIRLO. The proposed action would allow the licensee to irradiate a 
small number of LTAs using fuel rods clad with Ziron alloy in Hatch, 
Unit 2. Since the material specifications of the Ziron alloy differ 
from the specification for zircaloy or ZIRLO, a plant-specific 
exemption is required to support the use of the eight assemblies.

Environmental Impacts of the Proposed Action

    The NRC has completed its safety evaluation of the proposed action 
and concludes that application of 10 CFR 50.46, and Appendix K to 10 
CFR Part 50, is not necessary for the licensee to achieve its 
underlying purposes.
    The details of the NRC staff safety evaluation will be provided in 
the exemption that will be issued as part of the letter to the licensee 
approving the exemption to the regulation.
    The staff has concluded that such a change would not adversely 
affect plant safety, and would have no adverse effect on the 
probability of any accident. For accidents that involve damage or 
melting of the fuel in the reactor core, the fuel rod integrity of GNF-
Ziron cladded fuel has been shown to be similar to zircaloy cladded 
fuel; therefore, the probability of an accident will not be affected. 
For accidents in which the core remains intact, the use of GNF-Ziron 
cladding will not have a significant effect on the mix of fission 
products that could be released in the event of a serious accident; 
thus, the previously analyzed accident dose consequences remain 
bounding. Regulatory limits on radiological effluent releases are 
independent of the type of fuel cladding used. The requirements of 10 
CFR 50.36a, Appendix I to 10 CFR Part 50, and 40 CFR Part 190, as well 
as the plant's Technical Specifications ensure that the release of 
radioactive gaseous, liquid, and solid waste to unrestricted areas are 
kept to ``as low as reasonably achievable'' (ALARA) levels. The 
licensee's radioactive waste processing system will collect, control, 
process to reduce the amount of radioactivity, and discharge the waste 
in accordance with regulatory limits. Therefore, the staff concluded 
that during routine operations, there will be no significant increase 
of radiological effluents released into the environment as a result of 
the proposed exemption request. No significant increase in the 
allowable individual occupational radiation

[[Page 65416]]

exposure will occur. The impact to workers is not expected to change 
because radiation exposure will be controlled in accordance with the 
licensee's radiation protection program, the ALARA program, in-plant 
shielding, the use of temporary shielding, and engineering controls. 
The use of GNF-Ziron fuel rods will not change the potential 
environmental impacts of incident-free transportation of spent nuclear 
fuel provided the shipping casks are maintained and transported within 
the Department of Transportation and NRC regulations. Therefore, there 
are no significant radiological environmental impacts associated with 
the proposed action.
    With regard to potential non-radiological impacts, the proposed 
action does not have a potential to affect any historic sites. It does 
not affect non-radiological plant effluents and has no other 
environmental impact. Therefore, there are no significant non-
radiological environmental impacts associated with the proposed action. 
Accordingly, the NRC concludes that there are no significant 
environmental impacts associated with the proposed action.

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.

Alternative Use of Resources

    The action does not involve the use of any different resources than 
those previously considered in NUREG-1437, Supplement 4, ``Generic 
Environmental Impact Statement for License Renewal of Nuclear Plants,'' 
Supplement 4, Regarding the Edwin I. Hatch Nuclear Plant, Units 1 and 
2,'' dated May 31, 2001.

Agencies and Persons Consulted

    In accordance with its stated policy, on September 18, 2008, the 
NRC staff consulted with the Georgia State official, Mr. Jim Hardeman, 
of the Department of Natural Resources, 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 letters dated March 21, 2008, as supplemented May 2, August 
8, and September 22, 2008. 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 O1F21, 11555 Rockville Pike (first 
floor), Rockville, Maryland. Publicly available records will be 
accessible electronically from the Agencywide Documents Access and 
Management System (ADAMS) Public Electronic Reading Room on the 
Internet at the NRC Web site, 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.

    Dated at Rockville, Maryland, this 27th day of October, 2008.

    For the Nuclear Regulatory Commission.
Robert E. Martin,
Senior Project Manager, Plant Licensing Branch II-1, Division of 
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
 [FR Doc. E8-26133 Filed 10-31-08; 8:45 am]
BILLING CODE 7590-01-P