Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Byproduct Materials License No. 21-00182-03, for Unrestricted Release of the Pharmacia & Upjohn Company's Facilities in Kalamazoo, MI, 67609-67611 [E7-23159]

Download as PDF Federal Register / Vol. 72, No. 229 / Thursday, November 29, 2007 / Notices • Update on S&E Indicators ‘‘Digest.’’ • Science and Engineering Indicators 2008 Companion Piece. • Science and Engineering Indicators 2008 Rollout. • Science and Engineering Indicators 2010. • Presentation on Electronic ‘‘Digest.’’ • Subcommittee Chairman’s Summary. NUCLEAR REGULATORY COMMISSION [Docket No. 030–04781] Committee on Strategy and Budget (CSB) Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Byproduct Materials License No. 21–00182–03, for Unrestricted Release of the Pharmacia & Upjohn Company’s Facilities in Kalamazoo, MI Open Session: 10 a.m.–10:45 a.m. AGENCY: • Approval of CSB Minutes, October 3, 2007. • Committee Chairman’s Remarks. • Recommendations on NSF Average Award Size, Duration, and Proposal Success Rate. • Discussion of the Number of Proposal Submissions by a Single Institution or Principal Investigator. • Status Report: CSB Task Force on Cost Sharing. Closed Session: 10:45 a.m.–11a.m. • Status of NSF FY 2009 Budget Request. Committee on Education and Human Resources (EHR) Open Session: 11a.m.–12 p.m. • Approval of October 2007 Minutes. • Committee Chairman’s Remarks. • Update on NSF Implementation of Board STEM Education Guidance. • Status of Subcommittee on Science and Engineering Indicators. • Discussion: Preparing the Next Generation of STEM Innovators. • Board Executive Officer’s Report. Plenary Executive Closed Closed Session: 1 p.m.–1:05 p.m. • Approval of October 2007 Minutes. Plenary Closed Closed Session: 1:05 p.m.–1:30 p.m. • Approval of October 2007 Minutes. • Awards and Agreements. • Closed Committee Reports. Plenary Open rmajette on PROD1PC64 with NOTICES Open Session: 1:30 p.m.–2:30 p.m. • Approval of October 2007 Minutes. • Resolution to Close February 2008 Meeting. • Chairman’s Report. • Director’s Report. • Open Committee Reports. Michael P. Crosby, Executive Officer and Board Office Director. [FR Doc. E7–23174 Filed 11–28–07; 8:45 am] BILLING CODE 7555–01–P VerDate Aug<31>2005 14:52 Nov 28, 2007 Jkt 211001 Nuclear Regulatory Commission. ACTION: Issuance of Environmental Assessment and Finding of No Significant Impact for License Amendment. FOR FURTHER INFORMATION CONTACT: William Snell, Senior Health Physicist, Decommissioning Branch, Division of Nuclear Materials Safety, Region III, U.S. Nuclear Regulatory Commission, 2443 Warrenville Road, Lisle, Illinois 60532; telephone: (630) 829–9871; fax number: (630) 515–1259; or by e-mail at wgs@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. 21– 00182–03. This license is held by Pharmacia & Upjohn Company, LLC (the Licensee), a subsidiary of Pfizer, Inc., and governs licensed activities at its 7000 Portage Road, Kalamazoo, Michigan site. Issuance of the amendment would authorize release of Building 172 and the adjoining North Tank Farm (the Facilities) for unrestricted use. Licensed activities will continue at other site locations. The Licensee requested this action in a letter dated August 22, 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 August 22, 2007, license amendment request, resulting in release PO 00000 Frm 00017 Fmt 4703 Sfmt 4703 67609 of the Facilities for unrestricted use. License No. 21–00182–03 was issued on April 24,1958, pursuant to 10 CFR part 30, and has been amended periodically since that time. This license authorizes the Licensee to use byproduct materials for activities involving research and development. Amendment 21 issued on July 31, 1984, authorized the incineration of licensed materials in Building 172. The principal types of waste burned in the incinerator in Building 172 included pathologic wastes, trash, returned pharmaceuticals, organic process residues, waste solvents and laboratory chemicals. Some of this incinerated waste was contaminated with low levels of radioactive materials. The Facilities are situated on a 1728 acre pharmaceutical complex consisting of multiple chemical and compound manufacturing structures including offices and pharmaceutical manufacturing facilities. Building 172 is a one story building of about 8500 square feet that is 24 feet in height which contains the incinerator, operating controls, emissions controls, office areas, and waste receipt, transfer and shipping areas. The incinerator is a rotary kiln that is 12 feet long and 51⁄2 feet in diameter with a secondary combustion chamber that is 19 feet long and about 8 feet in diameter. The adjoining North Farm Area consists of three 10,000 gallon steel and carbon tanks used to store liquids prior to incineration. The pharmaceutical complex is located in a mixed residential, agricultural and commercial area. The licensee ceased using the 10,000 gallon tanks to receive or store radioactive liquids in 1996 and ceased using the incinerator in Building 172 in December 2006. A facility historical site assessment and scoping surveys were performed in January 2007, while demolition and final status surveys of the Facilities were initiated in June 2007. Based on the Licensee’s historical knowledge of the site and the conditions of the Facilities, 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 Facilities in June and July 2007 and provided information to the NRC to demonstrate that they meet the criteria in Subpart E of 10 CFR part 20 for unrestricted release. E:\FR\FM\29NON1.SGM 29NON1 67610 Federal Register / Vol. 72, No. 229 / Thursday, November 29, 2007 / Notices Need for the Proposed Action The Licensee has ceased conducting licensed activities in the Facilities and seeks their unrestricted use. rmajette on PROD1PC64 with NOTICES Environmental Impacts of the Proposed Action The historical review of the relevant licensed activities shows that such activities involved use of the following radionuclides with half-lives greater than 120 days: Hydrogen-3 and carbon14. Prior to performing the final status survey, the Licensee conducted decontamination activities, as necessary, in the areas affected by these radionuclides. The Licensee completed final status surveys in July 2007 covering all areas of the Facilities. The final status survey report was attached to the Licensee’s amendment request dated August 22, 2007. The Licensee elected to demonstrate compliance with the radiological criteria for unrestricted release as specified in 10 CFR 20.1402 using the screening approach described in NUREG–1757, ‘‘Consolidated NMSS Decommissioning Guidance,’’ Volume 2. The Licensee used the radionuclidespecific derived concentration guideline levels (DCGLs), developed 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, and in soils, 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 in Building 172 and the adjoining North Farm Area. 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 Facilities. VerDate Aug<31>2005 14:52 Nov 28, 2007 Jkt 211001 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 Facilities for unrestricted use is in compliance with 10 CFR 20.1402, including the impact of residual radioactivity at previouslyreleased site locations of use. Based on its review, the staff considered the impact of the residual radioactivity from the Facilities 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 Building 172 and the adjoining North Farm Area meet the requirements of 10 CFR 20.1402 for unrestricted release. 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 the Michigan Department of Environmental Quality (DEQ) for review on October 31, 2007. On November 6, 2007, Mr. Bob Skowronek, Chief, Radioactive Materials Unit, with the Michigan DEQ, responded by e-mail. The State agreed PO 00000 Frm 00018 Fmt 4703 Sfmt 4703 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. Dee L. Clement, Pfizer, Inc., letter to William Snell, U.S. Nuclear Regulatory Commission, Region III, dated August 22, 2007 (ADAMS Accession No. ML072360479); 2. NRC Inspection Report No. 030– 04781/07–01(DNMS) (NRC Form 591M) dated June 29, 2007 (ADAMS Accession No. ML071840206); 3. Title 10 Code of Federal Regulations, Part 20, Subpart E, ‘‘Radiological Criteria for License Termination;’’ 4. Title 10 Code of Federal Regulations, Part 51, ‘‘Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions;’’ 5. NUREG–1496, ‘‘Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRCLicensed Nuclear Facilities;’’ 6. NUREG–1757, ‘‘Consolidated NMSS Decommissioning Guidance.’’ E:\FR\FM\29NON1.SGM 29NON1 Federal Register / Vol. 72, No. 229 / Thursday, November 29, 2007 / Notices 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 reproduction contractor will copy documents for a fee. Dated at Lisle, Illinois, this 16th day of November 2007. For the Nuclear Regulatory Commission. Patrick L. Louden, Chief, Decommissioning Branch, Division of Nuclear Materials Safety, Region III. [FR Doc. E7–23159 Filed 11–28–07; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 030–34325] Notice of Availability of Environmental Assessment and Finding of No Significant Impact for Amendment of a Materials Permit in Accordance With Byproduct Materials License No. 03– 23853–01va, for Unrestricted Release of a Department of Veterans Affairs’ Facility in Coatesville, PA Nuclear Regulatory Commission. ACTION: Issuance of Environmental Assessment and Finding of No Significant Impact for License Amendment. AGENCY: FOR FURTHER INFORMATION CONTACT: rmajette on PROD1PC64 with NOTICES William Snell, Senior Health Physicist, Decommissioning Branch, Division of Nuclear Materials Safety, Region III, U.S. Nuclear Regulatory Commission, 2443 Warrenville Road, Lisle, Illinois 60532; telephone: (630) 829–9871; fax number: (630) 515–1259; or by e-mail at wgs@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is considering the amendment of a materials permit held under Master Byproduct Materials License No. 03–23853–01VA. The license is held by the Department of Veterans Affairs (the Licensee). The permit pertains to its VA Medical Center facility located at 1400 Black Horse Hill Road, Coatesville, Pennsylvania (the Facility). Issuance of the amendment would authorize release of the Facility’s Building 11 for unrestricted use and VerDate Aug<31>2005 14:52 Nov 28, 2007 Jkt 211001 termination of the permit. The Licensee requested this action in a letter dated June 28, 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 June 28, 2007, materials permit amendment request, resulting in release of Building 11 for unrestricted use. License No. 03–23853–01VA was issued on March 17, 2003, pursuant to 10 CFR Parts 30 and 35, and has been amended periodically since that time. This license authorizes the Licensee to use byproduct materials at Licensee facilities, as authorized by permits issued by the Licensee’s National Radiation Safety Committee for: Medical use defined in 10 CFR part 35; research and development as defined in 10 CFR part 30; portable gauge use; and veterinary use. Building 11 is a three-story brick building containing 65 rooms, is approximately 40 by 200 feet in size, and was used for research. The site is located in a semi-rural area of mixed residential and commercial land use. Between 1964 and 1996, the VA Medical Center in Coatesville possessed numerous Atomic Energy Commission and NRC licenses. Use of licensed materials at the Medical Center ceased in 1995, and the last of the licenses was terminated in 1996 and the site was released for unrestricted use. Following that action, 28 radioactive-labeled vials were found in Building 11. Accordingly, in February 2006, the Licensee issued a new permit authorizing the Facility to store these vials pending their disposal. Based on the Licensee’s historical knowledge of the site and the conditions of Building 11, the Licensee determined that only routine decontamination activities in accordance with NRC guidance were required to search for any other radioactive materials and conduct radiological surveys of Building 11. 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 PO 00000 Frm 00019 Fmt 4703 Sfmt 4703 67611 Building 11 on February 2, April 6, September 28, and October 4, 2006, and on March 9, 2007, and provided information to the NRC to demonstrate that the proposed action will meet 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 in Building 11, and seeks the unrestricted use of Building 11. Environmental Impacts of the Proposed Action The historical review of licensed activities conducted in Building 11 shows that such activities involved use of the following radionuclides with halflives greater than 120 days: hydrogen-3 (H–3) and carbon-14 (C–14). Prior to performing the final status survey, the Licensee conducted decontamination activities, as necessary, in the areas of Building 11 affected by these radionuclides. The Licensee completed final status surveys on Building 11 on March 9, 2007. The surveys covered all areas of Building 11. The final status survey report was attached to the Licensee’s amendment request dated June 28, 2007. The Licensee elected to demonstrate compliance with the 10 CFR 20.1402 criteria for unrestricted release by using release criteria for building surfaces based on NRC Regulatory Guide 1.86, ‘‘Termination of Operating Licenses for Reactors.’’ The criterion used is 5 × 103 disintegrations per minute per 100 square centimeters (dpm/100 cm2) for H–3 and C–14. These values are much more restrictive than the radionuclidespecific dose-based release criteria described in NUREG–1757, ‘‘Consolidated NMSS Decommissioning Guidance,’’ Volume 2, which are 1.2 × 108 dpm/100 cm2 for H–3 and 3.7 × 106 dpm/100 cm2 for C–14. These values 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 values 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 E:\FR\FM\29NON1.SGM 29NON1

Agencies

[Federal Register Volume 72, Number 229 (Thursday, November 29, 2007)]
[Notices]
[Pages 67609-67611]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-23159]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 030-04781]


Notice of Availability of Environmental Assessment and Finding of 
No Significant Impact for License Amendment to Byproduct Materials 
License No. 21-00182-03, for Unrestricted Release of the Pharmacia & 
Upjohn Company's Facilities in Kalamazoo, MI

AGENCY: Nuclear Regulatory Commission.

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

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

FOR FURTHER INFORMATION CONTACT: William Snell, Senior Health 
Physicist, Decommissioning Branch, Division of Nuclear Materials 
Safety, Region III, U.S. Nuclear Regulatory Commission, 2443 
Warrenville Road, Lisle, Illinois 60532; telephone: (630) 829-9871; fax 
number: (630) 515-1259; or by e-mail at wgs@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. 21-
00182-03. This license is held by Pharmacia & Upjohn Company, LLC (the 
Licensee), a subsidiary of Pfizer, Inc., and governs licensed 
activities at its 7000 Portage Road, Kalamazoo, Michigan site. Issuance 
of the amendment would authorize release of Building 172 and the 
adjoining North Tank Farm (the Facilities) for unrestricted use. 
Licensed activities will continue at other site locations.
    The Licensee requested this action in a letter dated August 22, 
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 August 22, 2007, 
license amendment request, resulting in release of the Facilities for 
unrestricted use. License No. 21-00182-03 was issued on April 24,1958, 
pursuant to 10 CFR part 30, and has been amended periodically since 
that time. This license authorizes the Licensee to use byproduct 
materials for activities involving research and development. Amendment 
21 issued on July 31, 1984, authorized the incineration of licensed 
materials in Building 172. The principal types of waste burned in the 
incinerator in Building 172 included pathologic wastes, trash, returned 
pharmaceuticals, organic process residues, waste solvents and 
laboratory chemicals. Some of this incinerated waste was contaminated 
with low levels of radioactive materials.
    The Facilities are situated on a 1728 acre pharmaceutical complex 
consisting of multiple chemical and compound manufacturing structures 
including offices and pharmaceutical manufacturing facilities. Building 
172 is a one story building of about 8500 square feet that is 24 feet 
in height which contains the incinerator, operating controls, emissions 
controls, office areas, and waste receipt, transfer and shipping areas. 
The incinerator is a rotary kiln that is 12 feet long and 5\1/2\ feet 
in diameter with a secondary combustion chamber that is 19 feet long 
and about 8 feet in diameter. The adjoining North Farm Area consists of 
three 10,000 gallon steel and carbon tanks used to store liquids prior 
to incineration. The pharmaceutical complex is located in a mixed 
residential, agricultural and commercial area.
    The licensee ceased using the 10,000 gallon tanks to receive or 
store radioactive liquids in 1996 and ceased using the incinerator in 
Building 172 in December 2006. A facility historical site assessment 
and scoping surveys were performed in January 2007, while demolition 
and final status surveys of the Facilities were initiated in June 2007. 
Based on the Licensee's historical knowledge of the site and the 
conditions of the Facilities, 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 
Facilities in June and July 2007 and provided information to the NRC to 
demonstrate that they meet the criteria in Subpart E of 10 CFR part 20 
for unrestricted release.

[[Page 67610]]

Need for the Proposed Action

    The Licensee has ceased conducting licensed activities in the 
Facilities and seeks their unrestricted use.

Environmental Impacts of the Proposed Action

    The historical review of the relevant licensed activities 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 affected by 
these radionuclides.
    The Licensee completed final status surveys in July 2007 covering 
all areas of the Facilities. The final status survey report was 
attached to the Licensee's amendment request dated August 22, 2007. The 
Licensee elected to demonstrate compliance with the radiological 
criteria for unrestricted release as specified in 10 CFR 20.1402 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 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, and in 
soils, 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 in Building 172 and the adjoining North 
Farm Area. 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 Facilities. 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 Facilities for 
unrestricted use is in compliance with 10 CFR 20.1402, including the 
impact of residual radioactivity at previously-released site locations 
of use. Based on its review, the staff considered the impact of the 
residual radioactivity from the Facilities 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 Building 172 and the adjoining 
North Farm Area meet the requirements of 10 CFR 20.1402 for 
unrestricted release. 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 the 
Michigan Department of Environmental Quality (DEQ) for review on 
October 31, 2007. On November 6, 2007, Mr. Bob Skowronek, Chief, 
Radioactive Materials Unit, with the Michigan DEQ, responded by e-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. Dee L. Clement, Pfizer, Inc., letter to William Snell, U.S. 
Nuclear Regulatory Commission, Region III, dated August 22, 2007 (ADAMS 
Accession No. ML072360479);
    2. NRC Inspection Report No. 030-04781/07-01(DNMS) (NRC Form 591M) 
dated June 29, 2007 (ADAMS Accession No. ML071840206);
    3. Title 10 Code of Federal Regulations, Part 20, Subpart E, 
``Radiological Criteria for License Termination;''
    4. Title 10 Code of Federal Regulations, Part 51, ``Environmental 
Protection Regulations for Domestic Licensing and Related Regulatory 
Functions;''
    5. NUREG-1496, ``Generic Environmental Impact Statement in Support 
of Rulemaking on Radiological Criteria for License Termination of NRC-
Licensed Nuclear Facilities;''
    6. NUREG-1757, ``Consolidated NMSS Decommissioning Guidance.''

[[Page 67611]]

    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 reproduction contractor will copy documents for a fee.

    Dated at Lisle, Illinois, this 16th day of November 2007.

    For the Nuclear Regulatory Commission.
Patrick L. Louden,
Chief, Decommissioning Branch, Division of Nuclear Materials Safety, 
Region III.
[FR Doc. E7-23159 Filed 11-28-07; 8:45 am]
BILLING CODE 7590-01-P