Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment To Byproduct Materials License No. 06-30667-02, for Termination of the License and Unrestricted Release of Curagen Corporation's Facility In Branford, Connecticut, 71974-71976 [E7-24600]

Download as PDF mstockstill on PROD1PC66 with NOTICES 71974 Federal Register / Vol. 72, No. 243 / Wednesday, December 19, 2007 / Notices to: Chief, Rulemaking, Directives and Editing Branch, Division of Administrative Services, Office of Administration, Mailstop T–6D59, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. Comments may be hand-delivered to the NRC at 11545 Rockville Pike, Room T–6D59, Rockville, Maryland, between 7:30 a.m. and 4:15 p.m. on Federal workdays. Electronic comments may be submitted to the NRC by e-mail at ShearonHarrisEIS@nrc.gov. All comments received by the Commission, including those made by Federal, State, local agencies, Native American Tribes, or other interested persons, will be made available electronically at the Commission’s PDR in Rockville, Maryland, and through ADAMS. The NRC staff will hold a public meeting to present an overview of the draft plant-specific supplement to the GEIS and to accept public comments on the document. The public meeting will be held on January 30, 2008, at the New Horizons Fellowship, 820 East Williams Street, Apex, North Carolina 27502. There will be two identical meetings to accommodate interested parties. The first meeting will convene at 1:30 p.m. and will continue until 4:30 p.m., as necessary. The second meeting will convene at 7 p.m. and will continue until 10 p.m., as necessary. Both meetings will be transcribed and will include: (1) A presentation of the contents of the draft plant-specific supplement to the GEIS, and (2) the opportunity for interested government agencies, organizations, and individuals to provide comments on the draft report. Additionally, the NRC staff will host informal discussions one hour prior to the start of each meeting at the same location. No comments on the draft supplement to the GEIS will be accepted during the informal discussions. To be considered, comments must be provided either at the transcribed public meetings or in writing. Persons may pre-register to attend or present oral comments at the meeting by contacting Mr. Samuel Hernandez, the NRC Environmental Project Manager at 1–800–368–5642, extension 4049, or by e-mail at ShearonHarrisEIS@nrc.gov no later than January 23, 2008. Members of the public may also register to provide oral comments within 15 minutes of the start of each session. Individual, oral comments may be limited by the time available, depending on the number of persons who register. If special equipment or accommodations are needed to attend or present information at the public meeting, the need should be brought to Mr. Hernandez’s attention no later than January 23, 2008, to VerDate Aug<31>2005 21:40 Dec 18, 2007 Jkt 214001 provide the NRC staff adequate notice to determine whether the request can be accommodated. FOR FURTHER INFORMATION CONTACT: Mr. Hernandez, Reactor Projects Branch 1, Division of License Renewal, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Mail Stop O–11F1, Washington, DC 20555– 0001. Mr. Hernandez may be contacted at the aforementioned telephone number or e-mail address. Dated at Rockville, Maryland, this 10th day of December 2007. For the Nuclear Regulatory Commission. Louise Lund, Branch Chief, Reactor Projects Branch 1, Division of License Renewal, Office of Nuclear Reactor Regulation. [FR Doc. E7–24648 Filed 12–18–07; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 030–36257] Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment To Byproduct Materials License No. 06–30667–02, for Termination of the License and Unrestricted Release of Curagen Corporation’s Facility In Branford, Connecticut Nuclear Regulatory Commission. ACTION: Issuance of Environmental Assessment and Finding of No Significant Impact for License Amendment. AGENCY: FOR FURTHER INFORMATION CONTACT: Dennis Lawyer, Health Physicist, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I, 475 Allendale Road, King of Prussia, Pennsylvania; telephone 610–337–5366; fax number 610–337–5393; or by e-mail: drl1@nrc.gov. SUPPLEMENTARY INFORMATION: I.Introduction The U.S. Nuclear Regulatory Commission (NRC) is considering the issuance of a license amendment to Byproduct Materials License No. 06– 30667–02. This license is held by CuraGen Corporation (the Licensee), for its facility located at 322 East Main Street, in Branford, Connecticut (the Facility). Issuance of the amendment would authorize release of the Facility for unrestricted use and termination of the NRC license. The Licensee requested this action in a letter dated July 31, PO 00000 Frm 00104 Fmt 4703 Sfmt 4703 2007. The NRC has prepared an Environmental Assessment (EA) in support of this proposed action in accordance with the requirements of Title 10, Code of Federal Regulations (CFR), Part 51 (10 CFR Part 51). Based on the EA, the NRC has concluded that a Finding of No Significant Impact (FONSI) is appropriate with respect to the proposed action. The amendment will be issued to the Licensee following the publication of this FONSI and EA in the Federal Register. II. Environmental Assessment Identification of Proposed Action The proposed action would approve the Licensee’s July 31, 2007, license amendment request, resulting in release of the Facility for unrestricted use and the termination of its NRC materials license. License No. 06–30667–02 was issued on April 8, 2003, pursuant to 10 CFR Part 30, and has been amended periodically since that time. This license authorized the Licensee to use unsealed byproduct material at the Facility for purposes of conducting research and development activities on laboratory bench tops, incubators, and in hoods. The Facility is comprised of a 52,000 square foot building on 3.5 acres of land and consists of general office space and laboratories. Use of licensed materials was confined to 300 square feet of the building known as Area 311B. The Facility is located in a mixed residential/commercial area. Within the Facility, the radionuclides of concern were hydrogen-3 and carbon-14 because their half-lives are greater than 120 days. In October 2004, the Licensee ceased licensed activities at the Facility and initiated survey and decontamination actions there. Based on the Licensee’s historical knowledge of the site and the conditions of the Facility, the Licensee determined that only routine decontamination activities, in accordance with their NRC-approved, operating radiation safety procedures, were required. The Licensee was not required to submit a decommissioning plan to the NRC because worker cleanup activities and procedures are consistent with those approved for routine operations. The Licensee conducted surveys of the Facility and provided information to the NRC to demonstrate that it meets the criteria in Subpart E of 10 CFR Part 20 for unrestricted release and for license termination. Need for the Proposed Action The Licensee has ceased conducting licensed activities at the Facility, and E:\FR\FM\19DEN1.SGM 19DEN1 Federal Register / Vol. 72, No. 243 / Wednesday, December 19, 2007 / Notices mstockstill on PROD1PC66 with NOTICES seeks the unrestricted use of its Facility and the termination of its NRC materials license. Termination of its license would end the Licensee’s obligation to pay annual license fees to the NRC. Environmental Impacts of the Proposed Action The historical review of licensed activities conducted at the Facility shows that such activities involved use of the following radionuclides with halflives greater than 120 days: hydrogen-3 and carbon-14. Prior to performing the final status survey, the Licensee conducted decontamination activities, as necessary, in the areas of the Facility affected by these radionuclides. The Licensee conducted final status surveys on July 2–3, 2007. The final status survey report was attached to the Licensee’s amendment request letter dated July 31, 2007. The Licensee elected to demonstrate compliance with the radiological criteria for unrestricted release as specified in 10 CFR 20.1402 by using the screening approach described in NUREG–1757, ‘‘Consolidated NMSS Decommissioning Guidance,’’ Volume 2. The Licensee used the radionuclide-specific derived concentration guideline levels (DCGLs), developed there by the NRC, which comply with the dose criterion in 10 CFR 20.1402. These DCGLs define the maximum amount of residual radioactivity on building surfaces, equipment, and materials, that will satisfy the NRC requirements in Subpart E of 10 CFR Part 20 for unrestricted release. The Licensee’s final status survey results were below these DCGLs and are in compliance with the As Low As Reasonably Achievable (ALARA) requirement of 10 CFR 20.1402. The NRC thus finds that the Licensee’s final status survey results are acceptable. Based on its review, the staff has determined that the affected environment and any environmental impacts associated with the proposed action are bounded by the impacts evaluated by the ‘‘Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRCLicensed Nuclear Facilities’’ (NUREG– 1496) Volumes 1–3 (ML042310492, ML042320379, and ML042330385). The staff finds there were no significant environmental impacts from the use of radioactive material at the Facility. The NRC staff reviewed the docket file records and the final status survey report to identify any non-radiological hazards that may have impacted the environment surrounding the Facility. No such hazards or impacts to the environment were identified. The NRC VerDate Aug<31>2005 21:40 Dec 18, 2007 Jkt 214001 has identified no other radiological or non-radiological activities in the area that could result in cumulative environmental impacts. The NRC staff finds that the proposed release of the Facility for unrestricted use and the termination of the NRC materials license is in compliance with 10 CFR 20.1402. Based on its review, the staff considered the impact of the residual radioactivity at the Facility and concluded that the proposed action will not have a significant effect on the quality of the human environment. Environmental Impacts of the Alternatives to the Proposed Action Due to the largely administrative nature of the proposed action, its environmental impacts are small. Therefore, the only alternative the staff considered is the no-action alternative, under which the staff would leave things as they are by simply denying the amendment request. This no-action alternative is not feasible because it conflicts with 10 CFR 30.36(d), requiring that decommissioning of byproduct material facilities be completed and approved by the NRC after licensed activities cease. The NRC’s analysis of the Licensee’s final status survey data confirmed that the Facility meets the requirements of 10 CFR 20.1402 for unrestricted release and for license termination. Additionally, denying the amendment request would result in no change in current environmental impacts. The environmental impacts of the proposed action and the no-action alternative are therefore similar, and the no-action alternative is accordingly not further considered. Conclusion The NRC staff has concluded that the proposed action is consistent with the NRC’s unrestricted release criteria specified in 10 CFR 20.1402. Because the proposed action will not significantly impact the quality of the human environment, the NRC staff concludes that the proposed action is the preferred alternative. Agencies and Persons Consulted NRC provided a draft of this Environmental Assessment to Connecticut Department of Environmental Protection for review on November 6, 2007. On November 30, 2007,the State of Connecticut, Department of Environmental Protection responded by electronic mail. The State agreed with the conclusions of the EA, and otherwise had no comments. The NRC staff has determined that the proposed action is of a procedural PO 00000 Frm 00105 Fmt 4703 Sfmt 4703 71975 nature, and will not affect listed species or critical habitat. Therefore, no further consultation is required under Section 7 of the Endangered Species Act. The NRC staff has also determined that the proposed action is not the type of activity that has the potential to cause effects on historic properties. Therefore, no further consultation is required under Section 106 of the National Historic Preservation Act. III. Finding of No Significant Impact The NRC staff has prepared this EA in support of the proposed action. On the basis of this EA, the NRC finds that there are no significant environmental impacts from the proposed action, and that preparation of an environmental impact statement is not warranted. Accordingly, the NRC has determined that a Finding of No Significant Impact is appropriate. IV. Further Information Documents related to this action, including the application for license amendment and supporting documentation, are available electronically at the NRC’s Electronic Reading Room at http://www.nrc.gov/ reading-rm/adams.html. From this site, you can access the NRC’s Agencywide Document Access and Management System (ADAMS), which provides text and image files of NRC’s public documents. The documents related to this action are listed below, along with their ADAMS accession numbers. 1. NUREG–1757, ‘‘Consolidated NMSS Decommissioning Guidance;’’ 2. Title 10 Code of Federal Regulations, Part 20, Subpart E, ‘‘Radiological Criteria for License Termination;’’ 3. Title 10, Code of Federal Regulations, Part 51, ‘‘Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions;’’ 4. NUREG–1496, ‘‘Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRCLicensed Nuclear Facilities;’’ and 5. CurGen Corporation’s Termination Request dated July 31, 2007 [ML072280511]. If you do not have access to ADAMS, or if there are problems in accessing the documents located in ADAMS, contact the NRC Public Document Room (PDR) Reference staff at 1–800–397–4209, 301– 415–4737, or by e-mail to pdr@nrc.gov. These documents may also be viewed electronically on the public computers located at the NRC’s PDR, O 1 F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR E:\FR\FM\19DEN1.SGM 19DEN1 71976 Federal Register / Vol. 72, No. 243 / Wednesday, December 19, 2007 / Notices II. Environmental Assessment reproduction contractor will copy documents for a fee. Dated at 475 Allendale Road, King of Prussia this 11th day of December. For the Nuclear Regulatory Commission. James P. Dwyer, Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I. [FR Doc. E7–24600 Filed 12–18–07; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 030–14680] Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Byproduct Materials License No. 29–00117–06, for Unrestricted Release of Merck & Co., Inc.’s Facility In Branchburg Township, NJ Nuclear Regulatory Commission. ACTION: Issuance of Environmental Assessment and Finding of No Significant Impact for License Amendment. AGENCY: FOR FURTHER INFORMATION CONTACT: mstockstill on PROD1PC66 with NOTICES Dennis Lawyer, Health Physicist, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I, 475 Allendale Road, King of Prussia, Pennsylvania; telephone 610–337–5366; fax number 610–337–5393; or by e-mail: drl1@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is considering the issuance of a license amendment to Byproduct Materials License No. 29– 00117–06. This license is held by Merck & Co., Inc. (the Licensee), for its Branchburg Farm, located at 203 River Road in Branchburg Township, New Jersey (the Facility). Issuance of the amendment would authorize release of the Facility for unrestricted use. The Licensee requested this action in a letter dated August 24, 2007. The NRC has prepared an Environmental Assessment (EA) in support of this proposed action in accordance with the requirements of Title 10, Code of Federal Regulations (CFR), Part 51 (10 CFR Part 51). Based on the EA, the NRC has concluded that a Finding of No Significant Impact (FONSI) is appropriate with respect to the proposed action. The amendment will be issued to the Licensee following the publication of this FONSI and EA in the Federal Register. VerDate Aug<31>2005 21:40 Dec 18, 2007 Jkt 214001 Identification of Proposed Action The proposed action would approve the Licensee’s August 24, 2007, license amendment request, resulting in release of the Facility for unrestricted use. License No. 29–00117–06 was issued on January 22, 1990, pursuant to 10 CFR Part 30, and has been amended periodically since that time. This license authorized the Licensee to use unsealed byproduct material at the Facility for purposes of conducting research and development activities on laboratory bench tops and in hoods, animal studies and instrument calibration. The proposed action pertains only to the cessation of licensed activities at the Facility. The license authorizes use of licensed material at other locations that will not be affected by this action and the license will thus not be terminated if the proposal is approved. The Facility is situated on 223 acres, and consists of office, laboratory, and animal areas. Within the Facility, use of licensed materials was confined to Building 71 and Building 91. The area of use totaled 29,000 square feet. The Facility is located in a residential area. Within the Facility, the radionuclides of concern were hydrogen-3 and carbon-14 because the half-life of these isotopes is greater than 120 days. In January 2007, the Licensee ceased licensed activities at the Facility and initiated survey and decontamination actions there. Based on the Licensee’s historical knowledge of the site and the conditions of the Facility, the Licensee determined that only routine decontamination activities, in accordance with their NRC-approved operating radiation safety procedures, were required. The Licensee was not required to submit a decommissioning plan to the NRC because worker cleanup activities and procedures are consistent with those approved for routine operations. The Licensee conducted surveys of the Facility and provided information to the NRC to demonstrate that it meets the criteria in Subpart E of 10 CFR Part 20 for unrestricted release. Need for the Proposed Action The Licensee has ceased conducting licensed activities at the Facility, and seeks the unrestricted use of its Facility. Environmental Impacts of the Proposed Action The historical review of licensed activities conducted at the Facility shows that such activities involved use of the following radionuclides with halflives greater than 120 days: hydrogen-3 PO 00000 Frm 00106 Fmt 4703 Sfmt 4703 and carbon-14. Prior to performing the final status survey, the Licensee conducted decontamination activities, as necessary, in the areas of the Facility affected by these radionuclides. The Licensee conducted final status surveys on April 9–11, May 1, and May 22, 2007. This survey covered 13 laboratories and an incinerator used within Building 71 and 91. The final status survey report was attached to the Licensee’s amendment request dated August 24, 2007. The Licensee elected to demonstrate compliance with the radiological criteria for unrestricted release as specified in 10 CFR 20.1402 by using the screening approach described in NUREG–1757, ‘‘Consolidated NMSS Decommissioning Guidance,’’ Volume 2. The Licensee used the radionuclide-specific derived concentration guideline levels (DCGLs), developed there by the NRC, which comply with the dose criterion in 10 CFR 20.1402. These DCGLs define the maximum amount of residual radioactivity on building surfaces, equipment, and materials, that will satisfy the NRC requirements in Subpart E of 10 CFR Part 20 for unrestricted release. The Licensee’s final status survey results were below these DCGLs and are in compliance with the As Low As Reasonably Achievable (ALARA) requirement of 10 CFR 20.1402. The NRC thus finds that the Licensee’s final status survey results are acceptable. Based on its review, the staff has determined that the affected environment and any environmental impacts associated with the proposed action are bounded by the impacts evaluated by the ‘‘Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRCLicensed Nuclear Facilities’’ (NUREG– 1496) Volumes 1–3 (ML042310492, ML042320379, and ML042330385). The staff finds there were no significant environmental impacts from the use of radioactive material at the Facility. The NRC staff reviewed the docket file records and the final status survey report to identify any non-radiological hazards that may have impacted the environment surrounding the Facility. No such hazards or impacts to the environment were identified. The NRC has identified no other radiological or non-radiological activities in the area that could result in cumulative environmental impacts. The NRC staff finds that the proposed release of the Facility for unrestricted use and the termination of the NRC materials license is in compliance with 10 CFR 20.1402. Based on its review, the staff considered the impact of the E:\FR\FM\19DEN1.SGM 19DEN1

Agencies

[Federal Register Volume 72, Number 243 (Wednesday, December 19, 2007)]
[Notices]
[Pages 71974-71976]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-24600]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[Docket No. 030-36257]


Notice of Availability of Environmental Assessment and Finding of 
No Significant Impact for License Amendment To Byproduct Materials 
License No. 06-30667-02, for Termination of the License and 
Unrestricted Release of Curagen Corporation's Facility In Branford, 
Connecticut

AGENCY: Nuclear Regulatory Commission.

ACTION: Issuance of Environmental Assessment and Finding of No 
Significant Impact for License Amendment.

-----------------------------------------------------------------------

FOR FURTHER INFORMATION CONTACT: Dennis Lawyer, Health Physicist, 
Commercial and R&D Branch, Division of Nuclear Materials Safety, Region 
I, 475 Allendale Road, King of Prussia, Pennsylvania; telephone 610-
337-5366; fax number 610-337-5393; or by e-mail: drl1@nrc.gov.

SUPPLEMENTARY INFORMATION:

I.Introduction

    The U.S. Nuclear Regulatory Commission (NRC) is considering the 
issuance of a license amendment to Byproduct Materials License No. 06-
30667-02. This license is held by CuraGen Corporation (the Licensee), 
for its facility located at 322 East Main Street, in Branford, 
Connecticut (the Facility). Issuance of the amendment would authorize 
release of the Facility for unrestricted use and termination of the NRC 
license. The Licensee requested this action in a letter dated July 31, 
2007. The NRC has prepared an Environmental Assessment (EA) in support 
of this proposed action in accordance with the requirements of Title 
10, Code of Federal Regulations (CFR), Part 51 (10 CFR Part 51). Based 
on the EA, the NRC has concluded that a Finding of No Significant 
Impact (FONSI) is appropriate with respect to the proposed action. The 
amendment will be issued to the Licensee following the publication of 
this FONSI and EA in the Federal Register.

II. Environmental Assessment

Identification of Proposed Action

    The proposed action would approve the Licensee's July 31, 2007, 
license amendment request, resulting in release of the Facility for 
unrestricted use and the termination of its NRC materials license. 
License No. 06-30667-02 was issued on April 8, 2003, pursuant to 10 CFR 
Part 30, and has been amended periodically since that time. This 
license authorized the Licensee to use unsealed byproduct material at 
the Facility for purposes of conducting research and development 
activities on laboratory bench tops, incubators, and in hoods.
    The Facility is comprised of a 52,000 square foot building on 3.5 
acres of land and consists of general office space and laboratories. 
Use of licensed materials was confined to 300 square feet of the 
building known as Area 311B. The Facility is located in a mixed 
residential/commercial area. Within the Facility, the radionuclides of 
concern were hydrogen-3 and carbon-14 because their half-lives are 
greater than 120 days.
    In October 2004, the Licensee ceased licensed activities at the 
Facility and initiated survey and decontamination actions there. Based 
on the Licensee's historical knowledge of the site and the conditions 
of the Facility, the Licensee determined that only routine 
decontamination activities, in accordance with their NRC-approved, 
operating radiation safety procedures, were required. The Licensee was 
not required to submit a decommissioning plan to the NRC because worker 
cleanup activities and procedures are consistent with those approved 
for routine operations. The Licensee conducted surveys of the Facility 
and provided information to the NRC to demonstrate that it meets the 
criteria in Subpart E of 10 CFR Part 20 for unrestricted release and 
for license termination.

Need for the Proposed Action

    The Licensee has ceased conducting licensed activities at the 
Facility, and

[[Page 71975]]

seeks the unrestricted use of its Facility and the termination of its 
NRC materials license. Termination of its license would end the 
Licensee's obligation to pay annual license fees to the NRC.

Environmental Impacts of the Proposed Action

    The historical review of licensed activities conducted at the 
Facility shows that such activities involved use of the following 
radionuclides with half-lives greater than 120 days: hydrogen-3 and 
carbon-14. Prior to performing the final status survey, the Licensee 
conducted decontamination activities, as necessary, in the areas of the 
Facility affected by these radionuclides.
    The Licensee conducted final status surveys on July 2-3, 2007. The 
final status survey report was attached to the Licensee's amendment 
request letter dated July 31, 2007. The Licensee elected to demonstrate 
compliance with the radiological criteria for unrestricted release as 
specified in 10 CFR 20.1402 by using the screening approach described 
in NUREG-1757, ``Consolidated NMSS Decommissioning Guidance,'' Volume 
2. The Licensee used the radionuclide-specific derived concentration 
guideline levels (DCGLs), developed there by the NRC, which comply with 
the dose criterion in 10 CFR 20.1402. These DCGLs define the maximum 
amount of residual radioactivity on building surfaces, equipment, and 
materials, that will satisfy the NRC requirements in Subpart E of 10 
CFR Part 20 for unrestricted release. The Licensee's final status 
survey results were below these DCGLs and are in compliance with the As 
Low As Reasonably Achievable (ALARA) requirement of 10 CFR 20.1402. The 
NRC thus finds that the Licensee's final status survey results are 
acceptable.
    Based on its review, the staff has determined that the affected 
environment and any environmental impacts associated with the proposed 
action are bounded by the impacts evaluated by the ``Generic 
Environmental Impact Statement in Support of Rulemaking on Radiological 
Criteria for License Termination of NRC-Licensed Nuclear Facilities'' 
(NUREG-1496) Volumes 1-3 (ML042310492, ML042320379, and ML042330385). 
The staff finds there were no significant environmental impacts from 
the use of radioactive material at the Facility. The NRC staff reviewed 
the docket file records and the final status survey report to identify 
any non-radiological hazards that may have impacted the environment 
surrounding the Facility. No such hazards or impacts to the environment 
were identified. The NRC has identified no other radiological or non-
radiological activities in the area that could result in cumulative 
environmental impacts.
    The NRC staff finds that the proposed release of the Facility for 
unrestricted use and the termination of the NRC materials license is in 
compliance with 10 CFR 20.1402. Based on its review, the staff 
considered the impact of the residual radioactivity at the Facility and 
concluded that the proposed action will not have a significant effect 
on the quality of the human environment.

Environmental Impacts of the Alternatives to the Proposed Action

    Due to the largely administrative nature of the proposed action, 
its environmental impacts are small. Therefore, the only alternative 
the staff considered is the no-action alternative, under which the 
staff would leave things as they are by simply denying the amendment 
request. This no-action alternative is not feasible because it 
conflicts with 10 CFR 30.36(d), requiring that decommissioning of 
byproduct material facilities be completed and approved by the NRC 
after licensed activities cease. The NRC's analysis of the Licensee's 
final status survey data confirmed that the Facility meets the 
requirements of 10 CFR 20.1402 for unrestricted release and for license 
termination. Additionally, denying the amendment request would result 
in no change in current environmental impacts. The environmental 
impacts of the proposed action and the no-action alternative are 
therefore similar, and the no-action alternative is accordingly not 
further considered.

Conclusion

    The NRC staff has concluded that the proposed action is consistent 
with the NRC's unrestricted release criteria specified in 10 CFR 
20.1402. Because the proposed action will not significantly impact the 
quality of the human environment, the NRC staff concludes that the 
proposed action is the preferred alternative.

Agencies and Persons Consulted

    NRC provided a draft of this Environmental Assessment to 
Connecticut Department of Environmental Protection for review on 
November 6, 2007. On November 30, 2007,the State of Connecticut, 
Department of Environmental Protection responded by electronic mail. 
The State agreed with the conclusions of the EA, and otherwise had no 
comments.
    The NRC staff has determined that the proposed action is of a 
procedural nature, and will not affect listed species or critical 
habitat. Therefore, no further consultation is required under Section 7 
of the Endangered Species Act. The NRC staff has also determined that 
the proposed action is not the type of activity that has the potential 
to cause effects on historic properties. Therefore, no further 
consultation is required under Section 106 of the National Historic 
Preservation Act.

III. Finding of No Significant Impact

    The NRC staff has prepared this EA in support of the proposed 
action. On the basis of this EA, the NRC finds that there are no 
significant environmental impacts from the proposed action, and that 
preparation of an environmental impact statement is not warranted. 
Accordingly, the NRC has determined that a Finding of No Significant 
Impact is appropriate.

IV. Further Information

    Documents related to this action, including the application for 
license amendment and supporting documentation, are available 
electronically at the NRC's Electronic Reading Room at http://
www.nrc.gov/reading-rm/adams.html. From this site, you can access the 
NRC's Agencywide Document Access and Management System (ADAMS), which 
provides text and image files of NRC's public documents. The documents 
related to this action are listed below, along with their ADAMS 
accession numbers.
    1. NUREG-1757, ``Consolidated NMSS Decommissioning Guidance;''
    2. Title 10 Code of Federal Regulations, Part 20, Subpart E, 
``Radiological Criteria for License Termination;''
    3. Title 10, Code of Federal Regulations, Part 51, ``Environmental 
Protection Regulations for Domestic Licensing and Related Regulatory 
Functions;''
    4. NUREG-1496, ``Generic Environmental Impact Statement in Support 
of Rulemaking on Radiological Criteria for License Termination of NRC-
Licensed Nuclear Facilities;'' and
    5. CurGen Corporation's Termination Request dated July 31, 2007 
[ML072280511].
    If you do not have access to ADAMS, or if there are problems in 
accessing the documents located in ADAMS, contact the NRC Public 
Document Room (PDR) Reference staff at 1-800-397-4209, 301-415-4737, or 
by e-mail to pdr@nrc.gov. These documents may also be viewed 
electronically on the public computers located at the NRC's PDR, O 1 
F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. 
The PDR

[[Page 71976]]

reproduction contractor will copy documents for a fee.

    Dated at 475 Allendale Road, King of Prussia this 11th day of 
December.

    For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety, 
Region I.
[FR Doc. E7-24600 Filed 12-18-07; 8:45 am]
BILLING CODE 7590-01-P