81316 Federal Register / Vol. 75, No. 247 / Monday, December 27, 2010 / Notices 

Dated at Rockville, Maryland, this 20th day 

of December, 2010. 

Tremaine Donnell, 

NRC Clearance Officer, Office of Information 

Services. 

[FR Doc. 2010–32423 Filed 12–23–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–341] 

Detroit Edison Company; FERMI 2; 

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, appendix E, Section 

IV.F.2.b, for conducting a biennial 

emergency preparedness exercise for 

Facility Operating License No. NFP–43, 

issued to Detroit Edison Company (the 

licensee), for operation of Fermi 2, 

located in Monroe County, Michigan. 

Therefore, as required by 10 CFR 51.21, 

the NRC performed an environmental 

assessment. Based on the results of the 

environmental assessment, the NRC is 

issuing a finding of no significant 

impact. 

Environmental Assessment 

Identification of the Proposed Action 

The proposed action is in accordance 

with the licensee’s application dated 

August 3, 2010, as supplemented by 

letters dated October 22, 2010, and 

November 15, 2010. Following a 

telephone conference with the NRC staff 

on September 17, 2010, the licensee 

determined the postponement of the 

exercise into calendar year 2011 to be an 

acceptable option to the licensee’s 

original request for crediting the 

response to a tornado event on June 6, 

2010, in place of the 2010 exercise. 

The Need for the Proposed Action 

Detroit Edison’s Fermi 2 biennial 

evaluated exercise was scheduled to be 

conducted on June 8, 2010. However, on 

June 6, 2010 at 0217 hours, a tornado 

warning was issued for Monroe County 

due to a storm front moving through 

southeast Michigan. At 0238 hours, a 

tornado swept across the Fermi 2 

property. At 0253 hours, the Shift 

Manager declared an Unusual Event 

based on reports of storm damage 

within the protected area, including loss 

of both 345kV lines for Division 2 of 

offsite power supply, and the loss of two 

out of three 120kV lines for Division 1 

of offsite power supply. 

Review of the actions that occurred 

during the June 6, 2010 actual event 

supplemented by the drills, exercises, 

and other training activities conducted 

since the previous biennial exercise, 

provides evidence that Fermi 2 has 

regularly exercised its emergency 

response strategies and personnel in 

coordination with the offsite authorities 

as required by regulations. In addition, 

due to a refueling outage during the 

fourth quarter of 2010, an alternative to 

schedule and conduct a biennial 

exercise in 2010 was ruled out by the 

licensee. 

The proposed action would exempt 

Fermi 2 from the requirements of 

conducting a biennial emergency 

preparedness exercise in the calendar 

year 2010 and postpone it into the 

calendar year 2011. Granting an 

exemption from the requirement of 

conducting the biennial exercise will 

not pose an undue risk to public health 

and safety and will ensure that focus is 

maintained on plant safety and security. 

Environmental Impacts of the Proposed 

Action 

The NRC staff has completed its 

evaluation of the proposed action and 

concludes that the proposed action is an 

exemption from the requirements of 

conducting a biennial emergency 

preparedness exercise. Whether or not 

the exercise is conducted would have 

no effect on the environment since any 

outdoor activity during an exercise is 

limited to minimal use of roads and 

highways. The staff has concluded that 

the changes would not significantly 

affect plant safety. The proposed action 

would not result in an increased 

radiological hazard beyond those 

previously analyzed in the Updated 

Safety Analysis Report. There will be no 

change to radioactive effluents that 

affect radiation exposures to plant 

workers and members of the public. No 

changes will be made to plant buildings 

or the site property. Therefore, no 

changes or different types of 

radiological impacts are expected as a 

result of the proposed changes. 

There are no federal permits, licenses, 

approvals and other entitlements which 

must be obtained in connection with the 

proposed action. The proposed action is 

not subject to any environmental quality 

standards or requirements imposed by 

Federal, State, regional, or local 

agencies having responsibility for 

environmental protection. 

The details of the staff’s safety 

evaluation will be provided in the 

exemption issued as part of the letter to 

the licensee approving the exemption to 

the regulation, if granted. 

The proposed action will not 

significantly increase the probability or 

consequences of accidents. No changes 

are being made in the types of effluents 

that may be released offsite. There is no 

significant increase in the amount of 

any effluent released offsite. There is no 

significant increase in occupational or 

public radiation exposure. 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 any foreseeable 

impacts to land, air, or water resources, 

including impacts to biota. In addition, 

there are no known socioeconomic or 

environmental justice impacts 

associated with such proposed action. 

Therefore, there are no significant nonradiological 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 the Final 

Environmental Statement for the Enrico 

Fermi Atomic Power Plant, Unit 2, 

NUREG–0769, dated August 1981, as 

supplemented with Addendum No. 1 in 

March 1982. 

Agencies and Persons Consulted 

In accordance with its stated policy, 

on November 22, 2010, the staff 

consulted with the State official, Mr. 

Ken Yale, of the Michigan Department 

of Natural Resources and Environment 

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. 


erowe on DSK5CLS3C1PROD with NOTICES
Federal Register / Vol. 75, No. 247 / Monday, December 27, 2010 / Notices 81317 

For further details with respect to the 

proposed action, see the licensee’s letter 

dated August 3, 2010 (Agencywide 

Documents Access and Management 

System (ADAMS) Accession No. 

ML102230442), as supplemented by 

letters dated October 22, 2010 (ADAMS 

Accession No. ML102950490) and 

November 15, 2010 (ADAMS Accession 

No. ML103200126). 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 O1 F21, 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 14th day 

of December, 2010. 

For the Nuclear Regulatory Commission. 

Mahesh Chawla, 

Project Manager, Plant Licensing Branch III– 

1, Division of Operating Reactor Licensing, 

Office of Nuclear Reactor Regulation. 

[FR Doc. 2010–32425 Filed 12–23–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards; Notice of Meeting 

In accordance with the purposes of 

Sections 29 and 182b of the Atomic 

Energy Act (42 U.S.C. 2039, 2232b), the 

Advisory Committee on Reactor 

Safeguards (ACRS) will hold a meeting 

on January 13–15, 2011, 11545 

Rockville Pike, Rockville, Maryland. 

The date of this meeting was previously 

published in the Federal Register on 

Thursday, October 21, 2010 (74 FR 

65038–65039). 

Thursday, January 13, 2011, 

Conference Room T2–B1, Two White 

Flint North, Rockville, Maryland 

8:30 a.m.–8:35 a.m.: Opening 

Remarks by the ACRS Chairman 

(Open)—The ACRS Chairman will make 

opening remarks regarding the conduct 

of the meeting. 

8:35 a.m.–10 a.m.: Aircraft Impact 

Assessment for the Revised AP1000 

Design (Open/Closed)—The Committee 

will hear presentations by and hold 

discussions with representatives of the 

NRC staff and Westinghouse regarding 

the Aircraft Impact Assessment for the 

revised AP1000 Design. 

[Note: A portion of this session may be 

closed in order to protect unclassified 

safeguards information, pursuant to 5 U.S.C. 

552b(c)(3), and information designated as 

proprietary by Westinghouse, pursuant to 5 

U.S.C. 552b(c)(4).] 

10:15 a.m.–12 p.m.: Final Safety 

Evaluation Report Associated With the 

Vogtle Units 3 and 4 Combined License 

Application (Open/Closed)—The 

Committee will hear presentations by 

and hold discussions with 

representatives of the NRC staff, 

Southern Nuclear Company, and NuStar 

Energy regarding the Final Safety 

Evaluation Report associated with the 

Vogtle Units 3 and 4 Combined License 

Application. 

[Note: A portion of this session may be 

closed in order to protect information 

designated as proprietary by Westinghouse 

pursuant to 5 U.S.C. 552b(c)(4).] 

2 p.m.–3:30 p.m.: Draft Final Revision 

2 to Regulatory Guide (RG) 1.174, ‘‘An 

Approach for Using Probabilistic Risk 

Assessment in Risk-Informed Decisions 

on Plant-Specific Changes to the 

Licensing Basis,’’ and Draft Final 

Revision 1 to RG 1.177, ‘‘An Approach 

for Plant-Specific, Risk-Informed 

Decisionmaking: Technical 

Specifications’’ (Open) The Committee 

will hear presentations by and hold 

discussions with representatives of the 

NRC staff regarding Draft Final Revision 

2 to RG 1.174, ‘‘An Approach for Using 

Probabilistic Risk Assessment in RiskInformed Decisions on Plant-Specific 

Changes to the Licensing Basis’’; Draft 

Final Revision 1 to RG 1.177, ‘‘An 

Approach for Plant-Specific, RiskInformed Decisionmaking: Technical 

Specifications’’; and the staff’s 

reconciliation of public comments. 

3:45 p.m.–7 p.m.: Preparation of 

ACRS Reports (Open/Closed)—The 

Committee will discuss proposed ACRS 

reports on matters discussed during this 

meeting. 

[Note: A portion of this session may be 

closed in order to protect unclassified 

safeguards information, pursuant to 5 U.S.C. 

552b(c)(3), and information designated as 

proprietary by Westinghouse, pursuant to 5 

U.S.C. 552b(c)(4).] 

Friday, January 14, 2011, Conference 

Room T2–B1, Two White Flint North, 

Rockville, Maryland 

8:30 a.m.–8:35 a.m.: Opening 

Remarks by the ACRS Chairman 

(Open)—The ACRS Chairman will make 

opening remarks regarding the conduct 

of the meeting. 

8:35 a.m.–10:30 a.m.: Draft Final Rule 

and Regulatory Guidance Regarding 

Enhancements to Emergency 

Preparedness Regulations (Open): The 

Committee will hear presentations by 

and hold discussions with 

representatives of the NRC staff 

regarding the draft final rule, 

‘‘Enhancements to Emergency 

Preparedness Regulations’’; Regulatory 

Guide 1.219, ‘‘Guidance on Making 

Changes to Emergency Plans for Nuclear 

Power Reactors’’; Interim Staff Guidance 

(ISG) NSIR/DPR–ISG–01,‘‘Emergency 

Planning for Nuclear Power Plants’’; and 

NUREG/CR–7002, ‘‘Criteria for 

Development of Evacuation Time 

Estimate Studies.’’ 

10:45 a.m.–12:15 p.m.: Staff 

Assessment of the RAMONA5–FA Code 

(Open/Closed): The Committee will hear 

presentations by and hold discussions 

with representatives of the NRC staff 

and AREVA regarding the staff’s 

assessment of the RAMONA5–FA code. 

[Note: A portion of this session may be 

closed in order to protect information 

designated as proprietary by AREVA 

pursuant to 5 U.S.C. 552b(c)(4).] 

1:15 p.m.–2:45 p.m.: Future ACRS 

Activities/Report of the Planning and 

Procedures Subcommittee (Open/ 

Closed)—The Committee will discuss 

the recommendations of the Planning 

and Procedures Subcommittee regarding 

items proposed for consideration by the 

Full Committee during future ACRS 

meetings, and matters related to the 

conduct of ACRS business, including 

anticipated workload and member 

assignments. 

[Note: A portion of this meeting may be 

closed pursuant to 5 U.S.C. 552b (c)(2) and 

(6) to discuss organizational and personnel 

matters that relate solely to internal 

personnel rules and practices of ACRS, and 

information the release of which would 

constitute a clearly unwarranted invasion of 

personal privacy.] 

2:45 p.m.–3 p.m.: Reconciliation of 

ACRS Comments and 

Recommendations (Open)—The 

Committee will discuss the responses 

from the NRC Executive Director for 

Operations to comments and 

recommendations included in recent 

ACRS reports and letters. 

3:15 p.m.–4:15 p.m.: Preparation of 

ACRS Reports (Open/Closed)—The 

Committee will continue its discussion 

of proposed ACRS reports. [Note: A 

portion of this session may be closed in 

order to protect unclassified safeguards 

information, pursuant to 5 U.S.C. 

552b(c)(3), and information designated 


erowe on DSK5CLS3C1PROD with NOTICES