Federal Register / Vol. 74, No. 180 / Friday, September 18, 2009 / Notices 47977 

of approximately 2,500 cubic meters of 

soil containing 15% concrete and metal 

debris contaminated with low 

concentrations of naturally occurring 

radium-226 and uranium-238, which 

will be generated during remediation 

and redevelopment of a property located 

in Toronto, Canada. In its March 19, 

2009, letter, USEI stated that this 

material meets the ‘‘unimportant 

quantity of source material’’ criteria 

founded in 10 CFR 40.13(a). As part of 

their request, USEI included a safety 

assessment of the shipment from the 

Toronto property to the USEI disposal 

facility in Idaho and the resulting 

potential doses to members of the public 

during transport and disposal. 

As a matter of policy, the U.S. Nuclear 

Regulatory Commission (NRC) reviews 

the safety implications of disposing of 

unimportant quantities of material at 

sites other than Atomic Energy Actlicensed disposal facilities. USEI is 

permitted by the Idaho Department of 

Environmental Quality (IDEQ) to 

operate a Resource Conservation and 

Recovery Act (RCRA) Subtitle C facility 

located near Grand View, Idaho and is 

not an NRC licensee. Consistent with 

Commission policy (Federal Register: 

August 28, 2002 [Volume 67, Number 

167], Proposed Rules, Pages 55175– 

55179) such a request for transfer would 

normally be approved if the dose to a 

member of the public is unlikely to 

exceed 0.25 mSv/yr (25 mrem/yr). 

3.0 Discussion 

USEI supplied information on the 

source term of the waste and a proposed 

scenario to evaluate different possible 

exposures for members of the public. 

These scenarios include dose to the 

transportation workers, USEI workers, 

and post-closure dose to the general 

public. The State of Idaho RCRA permit 

allows the disposal of exempted 

radioactive material including uranium 

as either naturally occurring radioactive 

material or unimportant quantities of 

source material provided they meet the 

requirements outlined in 10 CFR 

40.13(a) and can demonstrate that no 

individual would receive a dose in 

excess of 0.15 mSv/yr (15 mrem/yr) for 

a period of 100 years after closure of the 

facility. 

Based on sampling results provided, 

the NRC confirmed that this waste 

material qualifies as ‘‘unimportant 

quantities of source material’’ (i.e., 

containing less than 0.05 weight percent 

of source material) under 10 CFR 

40.13(a). As indicated in the Safety 

Evaluation Report (ML092380115), the 

staff verified that the expected dose to 

a member of the public due to transfer 

and disposal of the Toronto waste will 

be well below 25 mrem/yr. 

4.0 Conclusion 

Accordingly, the Commission has 

determined that, pursuant to 10 CFR 

110.10(a), an exemption from the 

requirements of 10 CFR 110.27 is 

authorized by law, will not present an 

undue risk to the public health and 

safety, and is consistent with the 

common defense and security. 

Therefore, the Commission hereby 

grants USEI an exemption from the 

requirement of 10 CFR 110.27 for a 

specific license to import the 

approximately 2,500 cubic meters of 

contaminated soil. 

This exemption is effective upon 

issuance. 

For The Nuclear Regulatory Commission. 

Dated this 9th day of September 2009 at 

Rockville, Maryland. 

Scott W. Moore, 

Deputy Director, Office of International 

Programs. 

[FR Doc. E9–22559 Filed 9–17–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0294] 

Notice of Issuance of Regulatory Guide 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of issuance and 

availability of Regulatory Guide 1.100, 

Revision 3. 

FOR FURTHER INFORMATION CONTACT: John 

Burke, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, telephone (301) 251–7628 or email to John.Burke@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The U.S. Nuclear Regulatory 

Commission (NRC) is issuing a revision 

to an existing guide in the agency’s 

‘‘Regulatory Guide’’ series. This series 

was developed to describe and make 

available to the public information such 

as methods that are acceptable to the 

NRC staff for implementing specific 

parts of the agency’s regulations, 

techniques that the staff uses in 

evaluating specific problems or 

postulated accidents, and data that the 

staff needs in its review of applications 

for permits and licenses. 

Revision 3 of Regulatory Guide 1.100, 

‘‘Seismic Qualification of Electrical and 

Active Mechanical Equipment and 

Functional Qualification of Active 

Mechanical Equipment for Nuclear 

Power Plants,’’ was issued with a 

temporary identification as Draft 

Regulatory Guide, DG–1175. This guide 

describes methods that the staff of the 

NRC considers acceptable for use in the 

seismic qualification of electrical and 

active mechanical equipment and the 

functional qualification of active 

mechanical equipment for nuclear 

power plants (NPPs). 

The general requirements for the 

seismic qualification of electrical and 

active mechanical equipment appear in 

Title 10 of the Code of Federal 

Regulations (10 CFR) part 50, ‘‘Domestic 

Licensing of Production and Utilization 

Facilities,’’ and 10 CFR part 52, ‘‘Early 

Site Permits; Standard Design 

Certifications; and Combined Licenses 

for Nuclear Power Plants.’’ Particular 

sections include General Design 

Criterion (GDC) 1, ‘‘Quality Standards 

and Records’’; GDC 2, ‘‘Design Bases for 

Protection Against Natural 

Phenomena’’; and GDC 4, 

‘‘Environmental and Dynamic Effects 

Design Basis,’’ of Appendix A, ‘‘General 

Design Criteria for Nuclear Power 

Plants,’’ to 10 CFR part 50; Criterion III, 

‘‘Design Control’’; Criterion XI, ‘‘Test 

Control’’; and Criterion XVII, ‘‘Quality 

Assurance Records,’’ of Appendix B, 

‘‘Quality Assurance Criteria for Nuclear 

Power Plants and Fuel Reprocessing 

Plants,’’ to 10 CFR part 50; and 

Appendix S, ‘‘Earthquake Engineering 

Criteria for Nuclear Power Plants,’’ to 10 

CFR part 50. 

II. Further Information 

In May 2008, DG–1175 was published 

with a public comment period of 60 

days from the issuance of the guide. The 

public comment period closed on July 

11, 2008. The staff’s responses to the 

public comments are located in NRC’s 

Agencywide Documents Access and 

Management System under accession 

number ML091320489. Electronic 

copies of Regulatory Guide 1.100, 

Revision 3 are available through the 

NRC’s public Web site under 

‘‘Regulatory Guides’’ at http:// 

www.nrc.gov/reading-rm/doccollections/. 

In addition, regulatory guides are 

available for inspection at the NRC’s 

Public Document Room (PDR) located at 

Room O–1F21, One White Flint North, 

11555 Rockville Pike, Rockville, 

Maryland 20852–2738. The PDR’s 

mailing address is USNRC PDR, 

Washington, DC 20555–0001. The PDR 

can also be reached by telephone at 

(301) 415–4737 or (800) 397–4209, by 

fax at (301) 415–3548, and by e-mail to 

pdr.resource@nrc.gov. 


erowe on DSK5CLS3C1PROD with NOTICES
47978 Federal Register / Vol. 74, No. 180 / Friday, September 18, 2009 / Notices 

Regulatory guides are not 

copyrighted, and NRC approval is not 

required to reproduce them. 

Dated at Rockville, Maryland, this 25th day 

of August 2009. 

For the Nuclear Regulatory Commission. 

Andrea D. Valentin, 

Chief, Regulatory Guide Development Branch, 

Division of Engineering, Office of Nuclear 

Regulatory Research. 

[FR Doc. E9–22558 Filed 9–17–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0410] 

Proposed Standard Review Plan; 

Branch Technical Position 18–1 on 

Guidance for Evaluating Minimum 

Inventory of Alarms, Controls, and 

Displays for New Light-Water Reactor 

Plant Designs 

AGENCY: Nuclear Regulatory 

Commission (NRC). 

ACTION: Solicitation of public comment. 

SUMMARY: The NRC is requesting public 

comment on NUREG–0800, ‘‘Standard 

Review Plan for the Review of Safety 

Analysis Reports for Nuclear Power 

Plants,’’ Branch Technical Position 

(BTP) 18–1, on Guidance for Evaluating 

Minimum Inventory of Alarms, 

Controls, and Displays for New Light 

Water Reactor Plant Designs 

(Agencywide Documents Access and 

Management System (ADAMS) 

Accession No. ML092330826). This BTP 

is to be cited as the acceptance criteria 

for the minimum inventory of controls, 

displays, and alarms in the Standard 

Review Plan (SRP) Chapter 18, Section 

II.A.7, item 8 for those standard designs 

that have not been certified prior to the 

date of this BTP. When BTP 18–1 is 

issued as final, Chapter 18, Section 

II.A.7, item 8, which currently states, 

‘‘8. A minimum inventory of controls, 

displays, and alarms,’’ will be revised to 

read, ‘‘8. A minimum inventory of 

controls, displays, and alarms (See the 

guidance in BTP 18–1 for designs that 

the NRC has not previously certified).’’ 

(Material in parenthesis is added as a 

pointer to the BTP.) 

The NRC staff issues SRPs and BTPs 

to facilitate timely implementation of 

current staff guidance and to facilitate 

activities associated with the review of 

applications for design certification (DC) 

and combined licenses (COLs) by the 

Office of New Reactors (NRO). The NRC 

staff will also incorporate the revised 

SRP section and BTP 18–1 into the next 

revisions of Regulatory Guide 1.206 and 

any related guidance documents. 

DATES: Comments must be filed no later 

than 60 days from the date of 

publication of this notice in the Federal 

Register. Comments received after this 

date will be considered, if it is practical 

to do so, but the Commission is able to 

ensure consideration only for comments 

received on or before this date. 

ADDRESSES: Comments may be 

submitted to: Mr. Michael T. Lesar, 

Chief, Rulemaking & Directives Branch, 

MS: TWB–05–B01M, Office of 

Administration, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001. 

The NRC maintains ADAMS, which 

provides text and image files of NRC’s 

public documents. These documents 

may be accessed through the NRC’s 

Public Electronic Reading Room on the 

Internet at http://www.nrc.gov/readingrm/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 Public Document Room 

reference staff at 1–800–397–4209, 301– 

415–4737, or by e-mail at 

PDR.Resource@nrc.gov. 

FOR FURTHER INFORMATION CONTACT: Mr. 

Michael A. Junge, Chief, Operator 

Licensing and Human Performance 

Branch, Division of Construction 

Inspection and Operational Programs, 

Office of New Reactors, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001; telephone 301–415– 

6855 or e-mail at 

Michael.Junge@nrc.gov. 

SUPPLEMENTARY INFORMATION: This SRP, 

NUREG–0800, has been prepared to 

establish criteria that the NRO staff use 

to evaluate if DC and COL applications 

meet the NRC’s regulations. The SRP is 

not a substitute for the NRC’s 

regulations, and compliance with it is 

not required. However, applicants are 

required to identify differences in 

design features, analytical techniques, 

and procedural measures proposed for a 

facility and corresponding SRP 

acceptance criteria, and evaluate how 

the proposed alternatives to the 

acceptance criteria provide an 

acceptable method of complying with 

the NRC’s regulations. 

The agency posts its issued staff 

guidance in the agency external web 

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

doc-collections/nuregs/staff/sr0800). 

The NRC staff is issuing this notice to 

solicit public comments on proposed 

BTP 18–1, which is being issued for the 

first time. After the NRC staff considers 

any public comments, it will make a 

determination regarding proposed BTP 

18–1. 

Dated at Rockville, Maryland, this 11th day 

of September 2009. 

For the Nuclear Regulatory Commission. 

William F. Burton, 

Chief, Rulemaking and Guidance 

Development Branch, Division of New Reactor 

Licensing, Office of New Reactors. 

[FR Doc. E9–22557 Filed 9–17–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0405] 

Request for a License To Export 

Radioactive Waste 

Pursuant to 10 CFR 110.70 (b) ‘‘Public 

Notice of Receipt of an Application,’’ 

please take notice that the U. S. Nuclear 

Regulatory Commission (NRC) has 

received the following request for an 

export license. Copies of the request are 

available electronically through ADAMS 

and can be accessed through the Public 

Electronic Reading Room (PERR) link 

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

the NRC Homepage. 

A request for a hearing or petition for 

leave to intervene may be filed within 

thirty days after publication of this 

notice in the Federal Register. Any 

request for hearing or petition for leave 

to intervene shall be served by the 

requestor or petitioner upon the 

applicant, the office of the General 

Counsel, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555; 

the Secretary, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555; 

and the Executive Secretary, U.S. 

Department of State, Washington, DC 

20520. 

A request for a hearing or petition for 

leave to intervene may be filed with the 

NRC electronically in accordance with 

NRC’s E–Filing rule promulgated in the 

August 28 2007 Federal Register, 72 FR 

49139. Information about filing 

electronically is available on the NRC’s 

public Web site at http://www.rnc.gov/ 

site-help/e-submittals.html. To ensure 

timely electronic filing, at least 5 (five) 

days prior to the filing deadline, the 

petitioner/requestor should contact the 

Office of the Secretary by e-mail at 

HEARINGDOCKET@NRC.GOV, or by 

calling (301) 415–1677, to request a 

digital ID certificate and allow for the 

creation of an electronic docket. 

In addition to a request for hearing or 

petition for leave to intervene, written 

comments, in accordance with 10 CFR 

110.81, should be submitted within 

thirty (30) days after publication of this 

notice in the Federal Register to Office 

of the Secretary, U.S. Nuclear 

Regulatory Commission, Washington, 


erowe on DSK5CLS3C1PROD with NOTICES