Federal Register / Vol. 74, No. 187 / Tuesday, September 29, 2009 / Notices 49899 

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] Letter dated July 29, 2009 with the 

‘‘Decommissioning Survey for Ligand 

Pharmaceuticals’’ ML092170692; 

[2] NUREG–1757, ‘‘Consolidated 

NMSS Decommissioning Guidance;’’ 

[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;’’ and 

[5] NUREG–1496, ‘‘Generic 

Environmental Impact Statement in 

Support of Rulemaking on Radiological 

Criteria for License Termination of 

NRC–Licensed Nuclear Facilities.’’ 

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 Region I, 475 Allendale Road, 

King of Prussia, PA this 23rd day of 

September 2009. 

For the Nuclear Regulatory Commission. 

James Dwyer, 

Chief, Commercial and R&D Branch, Division 

of Nuclear Materials Safety, Region I. 

[FR Doc. E9–23459 Filed 9–28–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0429; Docket No. 030–05249] 

Notice of Availability of Environmental 

Assessment and Finding of No 

Significant Impact for License 

Amendment to Byproduct Materials 

License No. 29–01035–01, for 

Unrestricted Release of the FMC 

Corporation Facility Located In 

Princeton, NJ 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Issuance of Environmental 

Assessment and Finding of No 

Significant Impact for license 

amendment. 

FOR FURTHER INFORMATION CONTACT: 

Betsy Ullrich, Senior Health Physicist, 

Commercial and R&D Branch, Division 

of Nuclear Materials Safety, Region I, 

475 Allendale Road, King of Prussia, 

Pennsylvania 19406; telephone (610) 

337–5040; fax number (610) 337–5268; 

or by e-mail: Elizabeth.ullrich@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– 

01035–01. This license is held by FMC 

Corporation (the Licensee), for its FMC 

Corporation Princeton Chemical 

Research and Development Center (the 

Facility), located at U. S. Route 1 and 

Plainsboro Road in Princeton, New 

Jersey. Issuance of the amendment 

would authorize release of the Facility 

for unrestricted use. The Licensee 

requested this action in a letter dated 

August 5, 2009. 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 5, 2009, license 

amendment request, resulting in release 

of the Facility for unrestricted use. 

License No. 29–01035–01 was issued on 

August 24, 1956, pursuant to 10 CFR 

part 30, and has been amended 

periodically since that time. This 

license authorized the Licensee to use 

unsealed byproduct material for 

purposes of conducting research and 

development activities on laboratory 

bench tops and in hoods. 

The Facility is situated on 114 acres 

and consists of multiple buildings 

housing office space and laboratories. 

The Facility is located in a mixed 

industrial/commercial area. Within the 

Facility, use of licensed materials was 

confined to Building 2 and Building 22. 

In 2008, the Licensee ceased licensed 

activities at the Facility and initiated a 

survey and decontamination of the 

Facility. 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, 

carbon-14, and chlorine-36. 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 a final status 

survey on June 15–17, and August 6, 

2009. This survey covered Building 2, 

Laboratories 2–1130, 2–1135, 2–1140, 

2–1150, 2–1155, 2–1160, 2–1162, 2– 

1165, 2–1175, 2–1205, 2–1210, 2–1230, 

2–1245, 2–1250, 2–1255, 2–14742–2135, 


jlentini on DSKJ8SOYB1PROD with NOTICES
49900 Federal Register / Vol. 74, No. 187 / Tuesday, September 29, 2009 / Notices 

2–2240, 2–2260, and 2–2265; Growth 

Chambers 8, 10, 15, and 19; Greenhouse 

#5; 2–1465 waste storage area; and the 

2–Basement. The survey also covered 

Building 22, a small storage shed used 

for temporary storage of containers of 

low-level radioactive waste prior to 

disposal. The final status survey report 

for Building 2 was submitted July 31, 

2009, and for Building 22 on August 7, 

2009. 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, 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 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. 

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 New 

Jersey Department of Environmental 

Protection (NJDEP) for review on August 

10, 2009. On September 4, 2009, NJDEP 

responded by letter. 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] ‘‘Multi-Agency Radiation Survey 

and Site Investigation Manual Final 

Status Survey, FMC Corporation, 

Building 2, Princeton, New Jersey, July 

2009’’ submitted July 31, 2009 

[ML092160141]; 

[2] Letter dated August 5, 2009 

[ML092190317]; 

[3] Survey results for Building 22 

dated August 7, 2009 [ML092230184] 

and letter dated August 11, 2009 

[ML092250111]; 

[4] NUREG–1757, ‘‘Consolidated 

NMSS Decommissioning Guidance;’’ 

[5] Title 10, Code of Federal 

Regulations, part 20, subpart E, 

‘‘Radiological Criteria for License 

Termination;’’ 

[6] Title 10, Code of Federal 

Regulations, part 51, ‘‘Environmental 

Protection Regulations for Domestic 

Licensing and Related Regulatory 

Functions;’’ and 

[7] NUREG–1496, ‘‘Generic 

Environmental Impact Statement in 

Support of Rulemaking on Radiological 

Criteria for License Termination of NRCLicensed Nuclear Facilities.’’ 

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. 


jlentini on DSKJ8SOYB1PROD with NOTICES
Federal Register / Vol. 74, No. 187 / Tuesday, September 29, 2009 / Notices 49901 

Dated at Region I, 475 Allendale Road, 

King of Prussia, PA this 23rd day of 

September 2009. 

For the Nuclear Regulatory Commission. 

James Dwyer, 

Chief, Commercial and R&D Branch, Division 

of Nuclear Materials Safety, Region I. 

[FR Doc. E9–23454 Filed 9–28–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0428; Docket No. 030–29879] 

Notice of Availability of Environmental 

Assessment and Finding of No 

Significant Impact for License 

Amendment to Byproduct Materials 

License No. 29–28005–01 Partial 

Unrestricted Release of the Sarnoff 

Corporation’s Facility in Princeton, NJ 

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 610–337–5269 or by e-mail: 

dennis.lawyer@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– 

28005–01. This license is held by The 

Sarnoff Corporation (the Licensee), for 

its facility located at 201 Washington 

Road in Princeton, New Jersey (the 

Facility). Issuance of the amendment 

would authorize release of Rooms EN– 

302, EN–307, and the Pond Building for 

unrestricted use. The amendment would 

also remove tritium from the materials 

authorized on the license as the licensee 

has provided surveys for the one 

laboratory which used tritium and will 

be used for other materials in the future. 

The Licensee requested this action in a 

letter dated April 14, 2009 and clarified 

its request in the additional information 

letter dated June 25, 2009. 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 April 14, 2009, license 

amendment request, resulting in release 

of Rooms EN–302, EN–307, and the 

Pond Building for unrestricted use and 

removal of tritium from the material 

authorization. License No. 29–28005–01 

was issued on June 16, 1987, pursuant 

to 10 CFR Part 30, and has been 

amended periodically since that time. 

This license authorized the Licensee to 

use unsealed byproduct material for 

purposes of conducting research and 

development activities on laboratory 

bench tops and in hoods. 

The Facility is situated on 254 acres 

in a 600,000 square foot building, and 

consists of office space and laboratories. 

The Facility is located in a residential 

area. The use of unsealed radioactive 

materials with a half life of greater than 

120 days was confined to 1,413 square 

feet within the Facility. 

The Licensee ceased licensed 

activities in Room EN–307 about July 1, 

1998; Room EN–302 on February 6, 

1996; and the Pond Building in 2001 

and initiated a survey and 

decontamination of the respective 

rooms. 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 Rooms EN–302, EN–307, and 

the Pond Building and provided 

information to the NRC to demonstrate 

that it meets the criteria in Subpart E of 

10 CFR Part 20 for unrestricted release. 

The licensee also conducted a survey on 

July 7, 2009, of the laboratory that had 

used hydrogen 3 and will be used for 

other materials in the future but the 

survey demonstrates that it could meet 

the criteria in Subpart E of 10 CFR Part 

20 for unrestricted release if it were 

being released at this time. 

Need for the Proposed Action 

The Licensee has ceased conducting 

licensed activities in Rooms EN–302, 

EN–307, and the Pond Building at the 

Facility, and seeks the unrestricted use 

of these areas. The licensee seeks the 

removal of hydrogen 3 material from 

their license. 

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. 

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 a final status survey 

on February 8, 1996, for Room EN–302; 

July 15, 1998, for EN–307; and April 16, 

2002, for the Pond Building. The final 

status survey report was attached to the 

Licensee’s additional information letter 

dated July 16, 2009. 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 


jlentini on DSKJ8SOYB1PROD with NOTICES