Federal Register / Vol. 76, No. 162 / Monday, August 22, 2011 / Notices 52355 

directed by the Antarctic Conservation 

Act of 1978 (Pub. L. 95–541), as 

amended by the Antarctic Science, 

Tourism and Conservation Act of 1996, 

has developed regulations for the 

establishment of a permit system for 

various activities in Antarctica and 

designation of certain animals and 

certain geographic areas a requiring 

special protection. The regulations 

establish such a permit system to 

designate Antarctic Specially Protected 

Areas. 

The applications received are as 

follows: 

Permit Application: 2012–006 

1. Applicant: Jeff Bowman, University 

of Washington, Box 357940, Seattle, WA 

98105–7940. 

Activity for Which Permit Is Requested 

Enter an Antarctic Specially Protected 

Area. The applicant plans to enter the 

Antarctic Specially Protect Area at Cape 

Royds, Ross Island (ASPA 121) to 

collect sea ice and seawater for 

microbial analysis. 

Location 

ASPA 121—Cape Royds, Ross island. 

Dates 

August 27, 2011 to November 2, 2011. 

Nadene G. Kennedy, 

Permit Officer, Office of Polar Programs. 

[FR Doc. 2011–21296 Filed 8–19–11; 8:45 am] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2010–0278] 

NUREG–1482, Revision 2, ‘‘Guidelines 

for Inservice Testing at Nuclear Power 

Plants, Draft Report for Comment’’ 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Announcement of issuance for 

public comment, availability. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) has issued for public 

comment a document entitled: NUREG– 

1482, Revision 2, ‘‘Guidelines for 

Inservice Testing at Nuclear Power 

Plants, Draft Report for Comment,’’ and 

subtitled ‘‘Inservice Testing of Pumps 

and Valves, and Inservice Examination 

and Testing of Dynamic Restraints 

(Snubbers) at Nuclear Power Plants’’. 

(Note that this document was 

submitted previously for public 

comments as draft NUREG–1946. Based 

on public comments, draft NUREG– 

1482 is being updated as Revision 2 and 

is being issued to incorporate all 

comments received for draft report 

NUREG–1946). 

DATES: Please submit comments by 

December 20, 2011. Comments received 

after this date will be considered if it is 

practical to do so, but the NRC staff is 

able to ensure consideration only for 

comments received on or before this 

date. 

ADDRESSES: Please include Docket ID 

NRC–2010–0278 in the subject line of 

your comments. For additional 

instructions on submitting comments 

and instructions on accessing 

documents related to this action, see 

‘‘Submitting Comments and Accessing 

Information’’ in the SUPPLEMENTARY

INFORMATION section of this document. 

You may submit comments by any one 

of the following methods: 

• Federal Rulemaking Web Site: Go to 

http://www.regulations.gov and search 

for documents filed under Docket ID 

NRC–2010–0278. Address questions 

about NRC dockets to Carol Gallagher, 

telephone: 301–492–3668; e-mail: 

Carol.Gallagher@nrc.gov. 

• Mail comments to: Cindy Bladey, 

Chief, Rules, Announcements, and 

Directives Branch (RADB), Office of 

Administration, Mail Stop: TWB–05– 

B01M, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001. 

• Fax comments to: RADB at 301– 

492–3446. 

SUPPLEMENTARY INFORMATION: 

Submitting Comments and Accessing 

Information 

Comments submitted in writing or in 

electronic form will be posted on the 

NRC Web site and on the Federal 

rulemaking Web site, http:// 

www.regulations.gov. Because your 

comments will not be edited to remove 

any identifying or contact information, 

the NRC cautions you against including 

any information in your submission that 

you do not want to be publicly 

disclosed. 

The NRC requests that any party 

soliciting or aggregating comments 

received from other persons for 

submission to the NRC inform those 

persons that the NRC will not edit their 

comments to remove any identifying or 

contact information, and therefore, they 

should not include any information in 

their comments that they do not want 

publicly disclosed. 

You can access publicly available 

documents related to this document 

using the following methods: 

• NRC’s Public Document Room 

(PDR): The public may examine and 

have copied, for a fee, publicly available 

documents at the NRC’s PDR, O1–F21, 

One White Flint North, 11555 Rockville 

Pike, Rockville, Maryland 20852. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): Publicly available documents 

created or received at the NRC are 

available online in the NRC Library at 

http://www.nrc.gov/reading-rm/ 

adams.html. From this page, the public 

can gain entry into ADAMS, which 

provides text and image files of the 

NRC’s public documents. If you do not 

have access to ADAMS or if there are 

problems in accessing the documents 

located in ADAMS, contact the NRC’s 

PDR reference staff at 1–800–397–4209, 

301–415–4737, or by e-mail to 

pdr.resource@nrc.gov. The NUREG– 

1482, Revision 2, ‘‘Guidelines for 

Inservice Testing at Nuclear Power 

Plants, Draft Report for Comment,’’ and 

subtitled ‘‘Inservice Testing of Pumps 

and Valves, and Inservice Examination 

and Testing of Dynamic Restraints 

(Snubbers) at Nuclear Power Plants’’ is 

available electronically under ADAMS 

Accession Number ML112231412. 

• Federal Rulemaking Web Site: 

Public comments and supporting 

materials related to this notice can be 

found at http://www.regulations.gov by 

searching on Docket ID NRC–2010– 

0278. 

FOR FURTHER INFORMATION CONTACT: 

Gurjendra S. Bedi, Division of 

Component Integrity, Office of Nuclear 

Reactor Regulation, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001, telephone: 301–415– 

1393, e-mail: Gurjendra.Bedi@nrc.gov. 

NUREG–1482, Revision 2, 

‘‘Guidelines for Inservice Testing at 

Nuclear Power Plants, Draft Report for 

Comment’’ provides updated 

information on applicable regulations 

for testing of pumps and valves, and 

inservice examination and testing of 

snubbers. The information in NUREG– 

1482, ‘‘Guidelines for Inservice Testing 

at Nuclear Plants,’’ Revision 0, issued 

April 1995, and Revision 1, issued 

January 2005, has described these topics 

in the past. 

This NUREG report replaces Revision 

0 and Revision 1 of NUREG–1482, and 

is applicable, unless stated otherwise, to 

all editions and addenda of the 

American Society of Mechanical 

Engineers (ASME) Code of Operation 

and Maintenance of Nuclear Power 

Plants (OM Code), which Title 10 of the 

Code of Federal Regulations (10 CFR) 

50.55a(b) incorporates by reference (76 

FR 36232–36279), dated June 21, 2011. 

Note that the draft NUREG–1482, 

Revision 2, is a substantial re-write from 

issuance of draft NUREG–1946 (ADAMS 


jlentini on DSK4TPTVN1PROD with NOTICES
52356 Federal Register / Vol. 76, No. 162 / Monday, August 22, 2011 / Notices 

Accession Number: ML102100236). 

This draft NUREG–1482, Revision 2, 

incorporates all the public comments 

received for draft NUREG–1946, because 

based on public comments, NUREG– 

1482, Revision 1, is revised and updated 

instead of issuing the new NUREG– 

1946. The NRC staff evaluation and 

resolution of public comments for draft 

NUREG–1946, including Inservice 

Testing Owner Group comments, are 

documented in ADAMS Accession 

Number: ML112092872. Most of the 

draft NUREG–1946 included in the 

main text of draft NUREG–1482, 

Revision 2, Appendix A, to this 

NUREG–1482, Revision 2, contains 

guidance provided in Revision 1 to 

NUREG–1482 for pumps and valves that 

has been updated for the development 

of inservice testing programs at nuclear 

power plants. Appendix B to this 

NUREG contains guidance related to 

inservice examination and testing of 

dynamic restraints (snubbers), which is 

included for the first time in the draft 

NUREG–1482, Revision 2. 

The guidelines and recommendations 

provided in this NUREG and its 

Appendices A and B do not supersede 

the regulatory requirements specified in 

10 CFR 50.55a. Further, this NUREG 

does not authorize the use of 

alternatives to, or grant relief from, the 

ASME Code requirements for inservice 

testing of pumps and valves, or 

inservice examination and testing of 

dynamic restraints (snubbers), 

incorporated by reference in 10 CFR 

50.55a. In addition, the NUREG 

discusses other inservice test program 

topics such as the NRC process for 

review of the OM Code, conditions on 

the use of the OM Code, and 

interpretations of the OM Code. 

Dated at Rockville, Maryland, this 11th day 

of August 2011. 

For the Nuclear Regulatory Commission. 

Anthony C. McMurtray, 

Chief, Component Performance and Testing 

Branch, Division of Component Integrity, 

Office of Nuclear Reactor Regulation. 

[FR Doc. 2011–21357 Filed 8–19–11; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2011–0188; Docket No. 50–315] 

Indiana Michigan Power Company, 

Donald C. Cook Nuclear Plant, Unit 1; 

Environmental Assessment and 

Finding of No Significant Impact 

The U.S. Nuclear Regulatory 

Commission (NRC or the Commission) 

is considering issuance of an exemption 

and an amendment to Renewed Facility 

Operating License No. NPF–58 issued to 

Indiana Michigan Power Company (the 

licensee), for operation of Donald C. 

Cook Nuclear Plant, Unit 1 (DCCNP–1), 

located in Berrien County, Michigan, in 

accordance with Title 10 of the Code of 

Federal Regulations (10 CFR) part 50, 

§ 50.90. In accordance with 10 CFR 

51.21, the NRC performed an 

environmental assessment documenting 

its findings. The NRC concluded that 

the proposed actions would have no 

significant environmental impact. 

Environmental Assessment 

Identification of the Proposed Actions 

The proposed actions would issue an 

exemption from 10 CFR 50.46 regarding 

fuel cladding material, and revise the 

Technical Specifications document, 

which is part of the Renewed Facility 

Operating Licenses, to permit use of 

Optimized ZIRLOTM fuel to a peak road 

average burnup limit of 62 gigawattdays per metric ton uranium (GWD/ 

MTU). 

The proposed actions are in 

accordance with the licensee’s 

application dated December 16, 2010. 

The Need for the Proposed Actions 

The proposed actions to issue an 

exemption to the fuel cladding 

requirement of 10 CFR 50.46, and to 

amend the Technical Specifications to 

permit use of Optimized ZIRLOTM fuel 

to a peak rod average burnup limit of 62 

GWD/MTU would allow for more 

effective fuel management. If the 

exemption and amendment are not 

approved, the licensee will not be 

provided the opportunity to use 

Optimized ZIRLOTM fuel design with a 

peak rod average burnup as high as 62 

GWD/MTU; the licensee would thus 

lose fuel management flexibility. 

Environmental Impacts of the Proposed 

Actions 

In this environmental assessment 

regarding the impacts of the use of 

Optimized ZIRLOTM fuel with the 

possible burnup up to 62 GWD/MTU, 

the Commission is relying on the results 

of the updated study conducted for the 

NRC by the Pacific Northwest National 

Laboratory (PNNL), entitled 

‘‘Environmental Effects of Extending 

Fuel Burnup Above 60 GWD/MTU’’ 

(NUREG/CR–6703, PNNL–13257, 

January 2001). Environmental impacts 

of high burnup fuel up to 75 GWD/MTU 

were evaluated in the study, but some 

aspects of the review were limited to 

evaluating the impacts of the extended 

burnup up to 62 GWD/MTU, because of 

the need for additional data on the effect 

of extended burnup on gap release 

fractions. All the aspects of the fuelcycle were considered during the study, 

from mining, milling, conversion, 

enrichment and fabrication through 

normal reactor operation, 

transportation, waste management, and 

storage of spent fuel. 

The amendment and exemption 

would allow DCCNP–1 to use 

Optimized ZIRLOTM fuel up to a burnup 

limit of 62 GWD/MTU. The NRC staff 

has completed its evaluation of the 

proposed actions and concludes that 

such changes would not adversely affect 

plant safety, and would have no adverse 

effect on the probability of any accident. 

For the accidents that involve damage or 

melting of the fuel in the reactor core, 

fuel rod integrity has been shown to be 

unaffected by extended burnup under 

consideration; therefore, the probability 

of an accident will not be affected by 

fuel burnup to 62 GWD/MTU. For the 

accidents in which the reactor core 

remains intact, the increased burnup 

may slightly change the mix of fission 

products that could be released in the 

event of a serious accident, but because 

the radionuclides contributing most to 

the dose are short-lived, increased 

burnup would not have an effect on the 

consequences of a serious accident 

beyond the consequences of previously 

evaluated accident scenarios. Thus, 

there will be no significant increase in 

projected dose consequences of 

postulated accidents associated with 

fuel burnup up to 62 GWD/MTU, and 

doses will remain well below regulatory 

limits. 

Regulatory limits on radiological 

effluent releases are independent of 

burnup. The requirements of 10 CFR 

part 20, 10 CFR 50.36a, and Appendix 

I to 10 CFR part 50 ensure that routine 

releases of gaseous, liquid or solid 

radiological effluents to unrestricted 

areas is kept ‘‘As Low As is Reasonably 

Achievable.’’ Therefore, the NRC staff 

concludes that during routine 

operations, there would be no 

significant increase in the amount of 

gaseous radiological effluents released 

into the environment as a result of the 

proposed actions, nor will there be a 

significant increase in the amount of 

liquid radiological effluents or solid 

radiological effluents released into the 

environment. 

The proposed actions will not change 

normal plant operating conditions (i.e., 

no changes are expected in the fuel 

handling, operational, or storing 

processes). The fuel storage and 

handling, radioactive waste, and other 

systems which may contain 

radioactivity are designed to assure 

adequate safety under normal 


jlentini on DSK4TPTVN1PROD with NOTICES