21928 Federal Register / Vol. 76, No. 75 / Tuesday, April 19, 2011 / Notices 

the Operating License and Technical 

Specifications. 

Date of initial notice in the Federal 

Register: February 1, 2011 (76 FR 

5623). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated April 6, 2011. 

No significant hazards consideration 

comments received: No. 

Dated at Rockville, Maryland, this 8th day 

of April 2011. 

For the Nuclear Regulatory Commission. 

Joseph G. Giitter, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2011–9177 Filed 4–18–11; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–027; NRC–2011–0083] 

Washington State University; Facility 

Operating License No. R–76; 

Washington State University Modified 

TRIGA Nuclear Radiation Center 

Reactor (NRCR); Environmental 

Assessment and Finding of No 

Significant Impact 

The U.S. Nuclear Regulatory 

Commission (NRC or the Commission) 

is considering the issuance of a renewed 

Facility Operating License No. R–76, to 

be held by Washington State University 

(WSU or the licensee), which would 

authorize continued operation of the 

Washington State University Modified 

TRIGA Nuclear Radiation Center 

Reactor (NRCR), located in the Dodgen 

Research Facility on Roundtop Drive in 

Pullman, Whitman County, Washington. 

Therefore, as required by Title 10 of the 

Code of Federal Regulations (10 CFR) 

§ 51.21, the NRC is issuing this 

Environmental Assessment and Finding 

of No Significant Impact. 

Environmental Assessment 

Identification of Proposed Action 

The proposed action would renew 

Facility Operating License No. R–76 for 

a period of twenty years from the date 

of issuance of the renewed license. The 

proposed action is in accordance with 

the licensee’s application dated June 24, 

2002, as supplemented by letters dated 

August 15, 2007, June 13, 2008, and 

April 7, 2010. In accordance with 10 

CFR 2.109, the existing license remains 

in effect until the NRC takes final action 

on the renewal application. 

Need for the Proposed Action 

The proposed action is needed to 

allow the continued operation of the 

NRCR to routinely provide teaching 

opportunities, services and research for 

numerous institutions for a period of 

twenty years. 

Environmental Impacts of the Proposed 

Action 

The NRC has completed its safety 

evaluation of the proposed action to 

issue a renewed Facility Operating 

License No. R–76 to allow continued 

operation of the NRCR for a period of 

twenty years and concludes there is 

reasonable assurance that the NRCR will 

continue to operate safely for the 

additional period of time. The details of 

the NRC staff’s safety evaluation will be 

provided with the renewed license that 

will be issued as part of the letter to the 

licensee approving its license renewal 

application. This document contains the 

environmental assessment of the 

proposed action. 

The NRCR is located 1.27 kilometers 

(0.79 miles) east of the French 

Administration Building on the main 

campus of WSU. The NRCR is located 

in the Dodgen Research Facility. The 

Dodgen Research Facility is a multipurpose building constructed primarily 

of concrete, brick, steel, and aluminum. 

The entrance to the Dodgen Research 

Facility is secured and an access code 

is required for entry. Emergency exit 

doors in the Dodgen Research Facility 

are key-locked from the outside and 

only a few individuals are issued the 

key. Entry into the NRCR from the 

Dodgen Research Facility requires a 

special key or confirmation of identity 

through closed-circuit television and 

verbal contact with the reactor 

operators. There are three outside 

entrances allowing direct access to the 

NRCR. These entrances are secured and 

the area around each one is surrounded 

by a fence and jersey barriers. The 

exclusion zone is considered to be the 

perimeter of the reactor building. A road 

and unused land is located west of the 

site. Until late 2008, the site was 

surrounded for a distance of 400 meters 

(1300 feet) in all directions by grazing 

land for livestock which was owned by 

WSU. The land has since been 

converted into a golf course which 

surrounds the NRCR in all directions 

except the west. The land remains 

uninhabited. The golf course is 

separated from the NRCR by 100 to 200 

meters (330 to 660 feet) of land. There 

is a parcel of land abutting the NRCR of 

about 10,000 square meters (109,000 

square feet) of virgin prairie land which, 

by regulation or policy, WSU has no 

plans to use. The closest building is 411 

meters (1350 feet) west of the NRCR. 

The closest occupied dwellings are 626 

meters (2060 feet) to the westsouthwest. 

The NRCR is a pool-type, light water 

moderated and cooled research reactor 

licensed to operate at a maximum 

steady-state power level of 1 megawatt 

thermal power (MW(t)). The reactor is 

also licensed to operate in a pulse mode 

to a peak power of approximately 2,000 

MW(t). The fuel is contained in a reactor 

vessel suspended from a movable bridge 

and is located near the bottom of an 8 

meter (25 feet) deep concrete pool 

containing approximately 242,000 liters 

(63,930 gallons) of water. The reactor is 

fueled with standard low-enriched 

uranium TRIGA (Training, Research, 

Isotopes, General Atomic) fuel. A 

detailed description of the reactor can 

be found in the NRCR Safety Analysis 

Report (SAR). There have been two 

major modifications to the Facility 

Operating License since renewal of the 

license on August 11, 1982. Orders were 

issued: (1) Allowing for an increase in 

the possession limits for Uranium-235; 

and (2) conversion from high-enriched 

uranium fuel to low-enriched uranium 

fuel as amendments to the license. 

The licensee has not requested any 

changes in the NRCR design or 

operating conditions as part of the 

application for license renewal. No 

changes are being made in the types or 

quantities of effluents that may be 

released off site. The licensee has 

systems in place for controlling the 

releases of radiological effluents and 

implements a radiation protection 

program to monitor personnel exposures 

and releases of radioactive effluents. 

Accordingly, there would be no increase 

in routine occupational or public 

radiation exposure as a result of the 

license renewal. As discussed in the 

NRC staff’s safety evaluation, the 

proposed action will not significantly 

increase the probability or consequences 

of accidents. Therefore, license renewal 

would not change the environmental 

impact of NRCR operation. The NRC 

staff evaluated information contained in 

the licensee’s application and data 

reported to the NRC by the licensee for 

the last five years of operation to 

determine the projected radiological 

impact of the NRCR on the environment 

during the period of the renewed 

license. The NRC staff finds that 

releases of radioactive material and 

personnel exposures were all well 

within applicable regulatory limits. 

Based on this evaluation, the NRC staff 

concludes that continued operation of 

the reactor would not have a significant 

environmental impact. 

mstockstill on DSKH9S0YB1PROD with NOTICES

Federal Register / Vol. 76, No. 75 / Tuesday, April 19, 2011 / Notices 21929 

I. Radiological Impact 

Environmental Effects of Reactor 

Operations 

Gaseous radioactive effluents are 

vented from the reactor building by the 

NRCR exhaust system via two vents. 

The vents discharge the effluents to a 

common stack located on the roof of the 

Dodgen Research Facility. The effluents 

are discharged at a volumetric flow rate 

of approximately 5.504 E+12 milliliters 

per month (4,500 cubic feet per minute). 

The only significant radionuclide found 

in the gaseous effluent stream is Argon41. The licensee performed 

measurements of Argon-41 production 

over a five-year period to obtain an 

average release rate. Licensee 

calculations, based on those 

measurements, indicate that annual 

Argon-41 releases result in an offsite 

concentration of 2.1 E–10 microcuries 

per milliliter (uCi/ml), which is below 

the limit of 1.0 E–08 uCi/ml specified in 

10 CFR part 20, Appendix B for air 

effluent releases. The NRC staff 

performed independent calculations 

and found the licensee’s calculations to 

be reasonable. The NRC staff also 

reviewed measurements and 

calculations performed by the licensee 

to estimate the potential release of 

tritium resulting from evaporation of the 

reactor pool water, and found them to 

be reasonable. The potential airborne 

tritium concentration was found to be a 

small fraction of the air effluent 

concentration limit specified in 10 CFR 

Part 20, Appendix B. Total gaseous 

radioactive releases reported to the NRC 

in the licensee’s annual reports were 

less than 0.1 percent of the air effluent 

concentration limits set by 10 CFR part 

20, Appendix B. The potential radiation 

dose to a member of the general public 

resulting from this concentration is 

approximately 0.001 milliSieverts (mSv) 

(0.1 millirem (mrem)) and this 

demonstrates compliance with the dose 

limit of 1 mSv (100 mrem) set by 10 CFR 

20.1301. Additionally, this potential 

radiation dose demonstrates compliance 

with the air emissions dose constraint of 

0.1 mSv (10 mrem) specified in 10 CFR 

20.1101(d). 

The licensee disposes of liquid 

radioactive waste by discharge to the 

sanitary sewer. The Radiation Safety 

Office (RSO), which is part of the WSU 

Department of Environmental Health 

and Safety, monitors the levels of 

radioactive waste discharged to the 

sanitary sewer. Discharge of liquid 

waste is initially to a holdup tank where 

levels of radioactive waste are measured 

and the contents diluted, if necessary to 

meet 10 CFR Part 20 discharge limits to 

the sanitary sewer. The RSO calculated 

that discharges to the sanitary sewer 

were in the order of 4 E–08 uCi/ml. The 

NRC staff reviewed the licensee’s 

procedures and results and found they 

met the requirements of 10 CFR 20.2003 

for disposal by release to the sanitary 

sewer. 

An NRC inspection was performed 

from September 8–10, 1998, to review 

the circumstances behind the leakage of 

pool water through the concrete of the 

reactor pool wall. The licensee 

determined that leakage was due to the 

porosity of the concrete and the 

penetrations for the beam tubes. The 

pool water which leaked either 

evaporated or collected in the fuel 

storage area and drained into the facility 

waste holding tank where it was 

analyzed and found to comply with the 

release limits of 10 CFR Part 20, 

Appendix B for liquid effluent. The 

reactor pool leak was successfully 

repaired in 1999. The NRC inspection 

report related to the reactor pool leakage 

concluded that management of liquid 

effluents was appropriate and identified 

no findings of significance. 

The licensee monitored the activity 

level in the waters in the vicinity of the 

NRCR, including the South Fork of the 

Palouse River, local tap water, and 

effluent from the sewage treatment plant 

and did not detect elevated levels of 

radioactive material attributable to the 

operation of the NRCR. 

The RSO oversees the handling of 

solid low-level radioactive waste 

generated at the NRCR. Solid 

radioactive waste consists mainly of 

spent ion resins and neutron activation 

products which are packaged by the 

licensee for shipment by a low-level 

waste broker in accordance with all 

applicable regulations for transportation 

of radioactive materials. If neutron 

activated or other licensed material is 

removed from the NRCR by the RSO or 

a researcher, the licensed material is 

transferred to the University for uses 

authorized under its broad scope 

byproduct material license. The licensee 

transferred the irradiated high-enriched 

uranium and FLIP fuels to Idaho 

National Engineering Laboratory in 

August 2009. The remaining 

unirradiated FLIP fuel will be 

transferred to Oak Ridge National 

Laboratory. To comply with the Nuclear 

Waste Policy Act of 1982, WSU entered 

into a contract with the U.S. Department 

of Energy (DOE) that provides that DOE 

retains title to the fuel utilized at the 

NRCR and that DOE is obligated to take 

the fuel from the site for final 

disposition. 

As described in Section 7, ‘‘Personnel 

and Visitor Radiation Exposures,’’ of the 

NRCR Annual Reports from 2004 

through 2009, personnel exposures are 

well within the limits set by 10 CFR 

20.1201, and as low as reasonably 

achievable (ALARA). The RSO tracks 

personnel exposures, which are usually 

less than 0.85 mSv (85 mrem) per year 

whole body. The WSU ALARA program 

requires the RSO to investigate any 

annual personnel exposures greater than 

90 mrem deep dose, 940 mrem 

extremities or 10 mrem fetal dose. 

Personnel monitors were mounted in 

locations throughout the controlled 

access areas of the NRCR, the control 

room, reactor hall, and beam room. The 

monitors provide a quarterly 

measurement of total radiation 

exposures at those locations. These 

dosimeters typically measure annual 

doses of less than 0.5 mSv (50 mrem) in 

the control room and less than 2 mSv 

(200 mrem) in the reactor hall and beam 

room. The above information is based 

on the NRC staff’s review of the past five 

years of radiation exposure data as 

monitored by the licensee using 

NVLAP-approved and processed 

dosimetry. No changes in reactor 

operation that would lead to an increase 

in occupational dose are expected as a 

result of the proposed action. 

The licensee conducts an 

environmental monitoring program to 

record and track the radiological impact 

of NRCR operation on the surrounding 

unrestricted area. The program consists 

of quarterly exposure measurements at 

12 locations adjacent to the Nuclear 

Radiation Center and at 24 control 

locations away from any direct 

influence from the reactor. The RSO 

administers the program and maintains 

the appropriate records. Over the past 

five years, the survey program indicated 

that radiation exposures at the 

monitoring locations were not 

significantly higher than those 

measured at the control locations. Yearto-year trends in exposures are 

consistent between monitoring 

locations. Also, no correlation exists 

between total annual reactor operation 

and annual exposures measured at the 

monitoring locations. Based on the NRC 

staff’s review of the past five years of 

data, the NRC staff concludes that 

operation of the NRCR does not have 

any significant radiological impact on 

the surrounding environment. No 

changes in reactor operation that would 

affect offsite radiation levels are 

expected as a result of license renewal. 

Environmental Effects of Accidents 

Accident scenarios are discussed in 

Chapter 13 of the NRCR SAR. The 

maximum hypothetical accident (MHA) 

is the uncontrolled release of the 

gaseous fission products contained in 

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21930 Federal Register / Vol. 76, No. 75 / Tuesday, April 19, 2011 / Notices 

the gap between the fuel and the fuel 

cladding in one fuel element in the 

reactor building and into the 

environment. The licensee 

conservatively calculated doses to 

NRCR personnel and the maximum 

potential dose to a member of the 

general public. The NRC staff performed 

independent calculations to verify that 

the doses represent conservative 

estimates for the MHA. Occupational 

doses resulting from this accident 

would be well below the 10 CFR Part 20 

limit of 50 mSv (5,000 mrem). 

Maximum doses for members of the 

general public resulting from this 

accident would be well below the 10 

CFR Part 20 limit of 1 mSv (100 mrem). 

The proposed action will not increase 

the probability or consequences of 

accidents. 

II. Non-Radiological Impacts 

The NRCR core is cooled by a light 

water primary system consisting of the 

reactor pool, a heat removal system, and 

an evaporative cooling system. Cooling 

occurs by natural convection, with the 

heated coolant rising out of the core and 

into the bulk pool water. The heated 

coolant is dissipated by using a heat 

exchanger and an evaporative induced 

draft cooling tower located on the north 

side of the NRCR. Higher pressure is 

maintained on the secondary side of the 

heat exchanger so that, in case of the 

failure of the heat exchanger, coolant 

would flow back into the pool. The 

cooling tower transfers heat to the 

atmosphere by evaporation, an average 

of 120,000 liters (32,000 gallons) per 

month. A minor amount of heat removal 

occurs due to evaporation (5,000 liters 

(1,330 gallons) per month) of coolant 

from the reactor pool’s surface. 

Replacement water is pumped from 

dedicated wells not associated with the 

municipal well water system of 

Pullman, Washington. Coolant leakage 

from the primary pump or the heat 

exchanger is diverted to a hold up tank 

for analysis, dilution, and transfer to the 

sanitary sewer. 

Release of thermal effluents from the 

NRCR will not have a significant effect 

on the environment. According to the 

licensee, Washington State University 

maintains and complies with the 

appropriate Washington Department of 

Health permit for secondary water 

discharge. Given that the proposed 

action does not involve any change in 

the operation of the reactor and the heat 

load dissipated to the environment, the 

NRC staff concludes that the proposed 

action will not have a significant impact 

on the local water supply. 

National Environmental Policy Act 

(NEPA) Considerations 

The NRC has responsibilities that are 

derived from NEPA and from other 

environmental laws, which include the 

Endangered Species Act (ESA), Coastal 

Zone Management Act (CZMA), 

National Historic Preservation Act 

(NHPA), Fish and Wildlife Coordination 

Act (FWCA), and Executive Order 12898 

Environmental Justice. The following 

provides a brief discussion of impacts 

associated with these laws and other 

requirements. 

I. Endangered Species Act 

No effects on the terrestrial or aquatic 

habitat in the vicinity of the plant, or to 

threatened, endangered, or protected 

species under the Endangered Species 

Act would be expected. 

II. Coastal Zone Management Act 

The NRCR is not located within any 

managed coastal zones, nor would 

NRCR effluents and emissions impact 

any managed coastal zones. 

III. National Historic Preservation Act 

The NHPA requires Federal agencies 

to consider the effects of their 

undertakings on historic properties. The 

National Register of Historic Places 

(NRHP) lists 9 historic sites located in 

and around Pullman, Washington with 

two of the sites on the WSU main 

campus. None of the sites are located 

within 0.8 kilometers (0.5 miles) of the 

NRCR and all are to the west of the 

NRCR except one site to the south. 

Given the distance between the NRCR 

and the 9 historical sites listed in the 

NRHP, continued operation of the NRCR 

will not impact any historical sites. 

Based on this information, the NRC staff 

finds that the potential impacts of 

license renewal would have no adverse 

effect on historic and archaeological 

resources. 

IV. Fish and Wildlife Coordination Act 

The licensee is not planning any 

water resource development projects, 

including any modifications related to 

impounding a body of water, damming, 

diverting a stream or river, deepening a 

channel, irrigation, or altering a body of 

water for navigation or drainage. 

V. Executive Order 12898— 

Environmental Justice 

The environmental justice impact 

analysis evaluates the potential for 

disproportionately high and adverse 

human health and environmental effects 

on minority and low-income 

populations that could result from the 

relicensing and the continued operation 

of the NRCR. Such effects may include 

human health, biological, cultural, 

economic, or social impacts. Minority 

and low-income populations are subsets 

of the general public residing around 

the NRCR, and all are exposed to the 

same health and environmental effects 

generated from activities at the NRCR. 

Minority Populations in the Vicinity 

of the NRCR—According to 2000 census 

data, 9.5 percent of the population 

(approximately 159,000 individuals) 

residing within a 50-mile radius of the 

NRCR identified themselves as minority 

individuals. There are 14 counties that 

fall entirely or partly within the 50-mile 

radius, seven in Washington and seven 

in Idaho. The largest minority was 

American Indian (5,800 persons or 3.6 

percent), followed by Asian (4,300 

persons or 2.7 percent). For Whitman 

County, (where the NRCR is located), 

the 2000 Census data shows that about 

13.3 percent of the population identified 

themselves as minorities, with persons 

of Asian origin comprising the largest 

minority group (6.6 percent). According 

to American Community Survey 3-year 

average census data estimates for 2006– 

2008, the minority population of 

Whitman County, as a percent of the 

total population, had increased to 16.6 

percent. 

Low-income Populations in the 

Vicinity of the NRCR—According to 

2000 Census data, approximately 3,700 

families and 25,000 individuals 

(approximately 9.6 and 15.7 percent, 

respectively) residing within a 50-mile 

radius of the NRCR were identified as 

living below the Federal poverty 

threshold in 1999. The 1999 Federal 

poverty threshold was $17,029 for a 

family of four. 

According to American Community 

Survey 3-year average census data 

estimates for 2006–2008, the median 

household income for Washington was 

$57,234, while 11.6 percent of the state 

population and 7.9 percent of families 

were determined to be living below the 

Federal poverty threshold. Whitman 

County had a lower median household 

income average ($35,945) and higher 

percentages (25.1 percent) of 

individuals and families (9.0 percent) 

living below the poverty level, 

respectively. 

Impact Analysis—Potential impacts to 

minority and low-income populations 

would mostly consist of radiological 

effects, however, radiation doses from 

continued operations associated with 

this license renewal are expected to 

continue at current levels, and would be 

well below regulatory limits. 

Based on this information and the 

analysis of human health and 

environmental impacts presented in this 

environmental assessment, the NRC 

mstockstill on DSKH9S0YB1PROD with NOTICES

Federal Register / Vol. 76, No. 75 / Tuesday, April 19, 2011 / Notices 21931 

1Public Law 111–203 (July 21, 2010). 

2 15 U.S.C. 7262. 

3 17 CFR 240.12b–2. 

4 15 U.S.C. 78a et seq. 

5Release No. 33–9142 (Sept. 15, 2010) [75 FR 

57385]. 

staff finds that the proposed action 

would not have disproportionately high 

and adverse human health and 

environmental effects on minority and 

low-income populations residing in the 

vicinity of NRCR. 

Environmental Impacts of the 

Alternatives to the Proposed Action 

As an alternative to license renewal, 

the NRC staff considered denying the 

proposed action. If the NRC denied the 

application for license renewal, reactor 

operations would cease and 

decommissioning would be required. 

The NRC notes that, even with a 

renewed license, the NRCR will 

eventually be decommissioned, at 

which time the environmental effects of 

decommissioning would occur. 

Decommissioning would be conducted 

in accordance with an NRC-approved 

decommissioning plan which would 

require a separate environmental review 

under 10 CFR 51.21. Cessation of reactor 

operations would reduce or eliminate 

radioactive effluents and emissions. 

However, as previously discussed in 

this environmental assessment, 

radioactive effluents and emissions from 

reactor operations constitute a small 

fraction of the applicable regulatory 

limits. Therefore, the environmental 

impacts of license renewal and the 

denial of the application for license 

renewal would be similar. In addition, 

denying the application for license 

renewal would eliminate the benefits of 

teaching opportunities, research, and 

services provided by the NRCR. 

Alternative Use of Resources 

The proposed action does not involve 

the use of any different resources or 

significant quantities of resources 

beyond those previously considered in 

the issuance of Amendment No. 10 to 

Facility Operating License No. R–76 for 

the Washington State University 

Nuclear Research Center Reactor dated 

August 11, 1982, which renewed the 

Facility Operating License for a period 

of 20 years. 

Agencies and Persons Consulted 

In accordance with the agency’s stated 

policy, the staff consulted with the State 

Historic Preservation Officer between 

May 13 and October 21, 2010, and the 

State Liaison Officer between May 13 

and December 2, 2010, regarding the 

environmental impact of the proposed 

action. The consultation involved a 

thorough explanation of the 

environmental review, the details of this 

environmental assessment, and the 

NRC’s findings. The State officials 

stated that they understood the NRC 

review and had no comments regarding 

the proposed action. 

III. Finding of No Significant Impact 

On the basis of the environmental 

assessment, the NRC staff concludes 

that the proposed action will not have 

a significant effect on the quality of the 

human environment. Accordingly, the 

NRC staff has determined not to prepare 

an environmental impact statement for 

the proposed action. 

For further details with respect to the 

proposed action, see the licensee’s 

application dated June 24, 2002 

(ML092390202), as supplemented by 

letters dated August 15, 2007 

(ML072410493), June 13, 2008 

(ML082380266), and April 7, 2010 

(ML101031097). Documents may be 

examined, and/or copied for a fee, at the 

NRC’s Public Document Room (PDR), 

located at One White Flint North, 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 NRC 

Web site 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 PDR Reference staff at 

1–800–397–4209, or 301–415–4737, or 

send an e-mail to pdr@nrc.gov. 

Dated at Rockville, Maryland this 8th day 

of April, 2011. 

For the Nuclear Regulatory Commission. 

Jessie F. Quichocho, 

Chief, Research and Test Reactors Licensing 

Branch, Division of Policy and Rulemaking, 

Office of Nuclear Reactor Regulation. 

[FR Doc. 2011–9436 Filed 4–18–11; 8:45 am] 

BILLING CODE 7590–01–P 

RAILROAD RETIREMENT BOARD 

Sunshine Act; Notice of Public Meeting 

Notice is hereby given that the 

Railroad Retirement Board will hold a 

meeting on April 27, 2011, 10 a.m. at 

the Board’s meeting room on the 8th 

floor of its headquarters building, 844 

North Rush Street, Chicago, Illinois 

60611. The agenda for this meeting 

follows: 

Executive Committee Reports 

The entire meeting will be open to the 

public. The person to contact for more 

information is Beatrice Ezerski, 

Secretary to the Board, Phone No. 312– 

751–4920. 

Dated: April 14, 2011. 

Beatrice Ezerski, 

Secretary to the Board. 

[FR Doc. 2011–9537 Filed 4–15–11; 11:15 am] 

BILLING CODE 7905–01–P 

SECURITIES AND EXCHANGE 

COMMISSION 

Submission for OMB Review; 

Comment Request 

Upon Written Request, Copies Available 

From: Securities and Exchange 

Commission, Office of Investor 

Education and Advocacy, 

Washington, DC 20549. 

Requested Change: 

Form 10–K, OMB Control No. 3235–0063; 

SEC File No. 270–48. 

Form 20–F, OMB Control No. 3235–0288; 

SEC File No. 270–156. 

Section 989G of the Dodd-Frank Wall 

Street Reform and Consumer Protection 

Act of 2010 1 (the ‘‘Act’’) provides that 

Section 404(b) of the Sarbanes-Oxley 

Act 2 does not apply to any audit report 

prepared for an issuer that is neither an 

accelerated filer nor a large accelerated 

filer as defined in Rule 12b–2 3 under 

the Securities Exchange Act.4 Notice is 

hereby given that, pursuant to the 

Paperwork Reduction Act of 1995 

(44 U.S.C. 3501–3520), the Securities 

and Exchange Commission (the 

‘‘Commission’’) has submitted to the 

Office of Management and Budget the 

request for approval of extension of the 

previously approved collection of 

information discussed below. 

In a separate release,5 the Commission 

amended its rules in light of the Act, 

which amends Section 404 of the 

Sarbanes-Oxley Act. The Commission 

had previously estimated the burden of 

complying with Section 404(b) of the 

Sarbanes-Oxley Act assuming that all 

filers of Forms 10–K and 20–F would 

file an auditor’s attestation report. The 

filers that were included in the estimate 

but are no longer subject to the 404 

requirement are sometimes referred to 

as ‘‘non-accelerated filers.’’ 

Form 10–K sets forth the disclosure 

requirements for annual reports filed by 

issuers under the Securities Exchange 

Act. Form 20–F sets forth the disclosure 

requirements for annual reports and 

registration statements filed by foreign 

private issuers under the Securities 

Exchange Act, as well as many of the 

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