11574 Federal Register / Vol. 75, No. 47 / Thursday, March 11, 2010 / Notices 

factors specified in 10 CFR 

2.309(c)(1)(i)–(viii). 

Detailed information about the license 

renewal process can be found under the 

Nuclear Reactors icon at http:// 

www.nrc.gov/reactors/operating/ 

licensing/renewal.html on the NRC’s 

Web site. Copies of the application to 

renew the operating license for CGS are 

available for public inspection at the 

Commission’s PDR, located at One 

White Flint North, 11555 Rockville Pike 

(first floor), Rockville, Maryland 20852– 

2738, and at http://www.nrc.gov/ 

reactors/operating/licensing/renewal/ 

applications.html, the NRC’s Web site 

while the application is under review. 

The application may be accessed in 

ADAMS through the NRC’s Public 

Electronic Reading Room on the Internet 

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

adams.html under ADAMS Accession 

Number ML100250668. As stated above, 

persons who do not have access to 

ADAMS or who encounter problems in 

accessing the documents located in 

ADAMS may contact the NRC PDR 

reference staff by telephone at 1–800– 

397–4209 or 301–415–4737, or by e-mail 

to PDR.Resource@nrc.gov. 

The NRC staff has verified that a copy 

of the LRA is also available to local 

residents near the site at the Richland 

Public Library, 955 Northgate Drive, 

Richland, Washington 99352 and at the 

Kennewick Branch of Mid-Columbia 

Libraries, 1620 South Union Street, 

Kennewick, Washington 99338. 

Dated at Rockville, Maryland, this 4th day 

of March 2010. 

For the Nuclear Regulatory Commission. 

Brian E. Holian, 

Director Division of License Renewal, Office 

of Nuclear Reactor Regulation. 

[FR Doc. 2010–5278 Filed 3–10–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2010–0097] 

Draft Regulatory Guide: Issuance, 

Availability 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of issuance and 

availability of draft regulatory guide, 

DG–1242, ‘‘Service Level I, II, and III 

Protective Coatings Applied To Nuclear 

Power Plants.’’ 

FOR FURTHER INFORMATION CONTACT: 

Bruce P. Lin, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, telephone: (301) 251–7653 or email Bruce.Lin@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The U.S. Nuclear Regulatory 

Commission (NRC) is issuing for public 

comment a draft guide in the agency’s 

‘‘Regulatory Guide’’ series. This series 

was developed to describe and make 

available to the public such information 

as methods that are acceptable to the 

NRC staff for implementing specific 

parts of the NRC’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. 

The draft regulatory guide (DG), 

entitled, ‘‘Service Level I, II, and III 

Protective Coatings Applied to Nuclear 

Power Plants’’ is temporarily identified 

by its task number, DG–1242, which 

should be mentioned in all related 

correspondence. DG–1242 is proposed 

Revision 2 of Regulatory Guide 1.54, 

dated July 2000. 

Protective coatings have been used 

extensively in nuclear power plants 

(NPPs) to protect the surfaces of 

facilities and equipment from corrosion 

and contamination from radionuclides 

and for wear protection during plant 

operation and maintenance activities. 

For plants that have a design basis that 

includes a commitment to RG 1.54, 

‘‘Quality Assurance Requirements for 

Protective Coatings Applied to WaterCooled Nuclear Power Plants,’’ issued 

June 1973, the regulations cited above 

require that protective coatings be 

qualified and capable of surviving a 

design-basis accident without adversely 

affecting safety-related structures, 

systems, and components needed to 

mitigate the accident. 

The NRC issued RG 1.54 to describe 

an acceptable method for complying 

with NRC quality assurance 

requirements for protective coatings 

applied to ferritic steels, stainless steel, 

zinc-coated (galvanized) steel, concrete, 

or masonry surfaces of water-cooled 

NPPs. The presumption was that 

protective coatings that met these 

guidelines would not degrade over the 

design life of the plant. However, 

operating history has shown that 

undesirable degradation, detachment, 

and other types of failures of coatings 

have occurred, as described in Generic 

Letter 98–04, ‘‘Potential for Degradation 

of the Emergency Core Cooling System 

and the Containment Spray System after 

a Loss-of-Coolant Accident because of 

Construction and Protective Coating 

Deficiencies and Foreign Material in 

Containment,’’ dated July 14, 1998. 

Detached coatings from the substrate 

that are transported to emergency core 

cooling system intake structures may 

make those systems unable to satisfy the 

requirement in 10 CFR 50.46(b)(5) to 

provide long-term cooling. 

II. Further Information 

The NRC staff is soliciting comments 

on DG–1242. Comments may be 

accompanied by relevant information or 

supporting data and should mention 

DG–1242 in the subject line. Comments 

submitted in writing or in electronic 

form will be made available to the 

public in their entirety through the 

NRC’s Agencywide Documents Access 

and Management System (ADAMS). 

ADDRESSES: You may submit comments 

by any one of the following methods. 

Please include Docket ID NRC–2010– 

0097 in the subject line of your 

comments. Comments submitted in 

writing or in electronic form will be 

posted on the NRC Web site and on the 

Federal rulemaking Web site 

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. 

Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for documents filed under Docket ID 

NRC–2010–0097. Address questions 

about NRC dockets to Carol Gallagher 

301–492–3668; e-mail 

Carol.Gallagher@nrc.gov. 

Mail comments to: Michael T. Lesar, 

Chief, Rulemaking and Directives 

Branch (RDB), Office of Administration, 

Mail Stop: TWB–05–B01M, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, or by fax 

to RDB at (301) 492–3446. 

You can access publicly available 

documents related to this notice 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, Room O1 

F21, One White Flint North, 11555 

Rockville Pike, Rockville, Maryland. 

NRC’s Agencywide Documents Access 

and Management System (ADAMS): 

Publicly available documents created or 

received at the NRC are available 

electronically at the NRC’s Electronic 


jlentini on DSKJ8SOYB1PROD with NOTICES
Federal Register / Vol. 75, No. 47 / Thursday, March 11, 2010 / Notices 11575 

Reading Room 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 

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. DG–1242 is 

available electronically under ADAMS 

Accession Number ML093410510. In 

addition, electronic copies of DG–1242 

are available through the NRC’s public 

Web site under Draft Regulatory Guides 

in the ‘‘Regulatory Guides’’ collection of 

the NRC’s Electronic Reading Room at 

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

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–2010–0097. 

Comments would be most helpful if 

received by May 12, 2010. Comments 

received after that date will be 

considered if it is practical to do so, but 

the NRC is able to ensure consideration 

only for comments received on or before 

this date. Although a time limit is given, 

comments and suggestions in 

connection with items for inclusion in 

guides currently being developed or 

improvements in all published guides 

are encouraged at any time. 

Regulatory guides are not 

copyrighted, and Commission approval 

is not required to reproduce them. 

Dated at Rockville, Maryland, this 4th day 

of March, 2010. 

For the Nuclear Regulatory Commission. 

Andrea D. Valentin, 

Chief, Regulatory Guide Development Branch, 

Division of Engineering, Office of Nuclear 

Regulatory Research. 

[FR Doc. 2010–5225 Filed 3–10–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–333; NRC–2010–0095] 

James A. Fitzpatrick Nuclear Power 

Plant Environmental Assessment and 

Finding of No Significant Impact 

The U.S. Nuclear Regulatory 

Commission (NRC) is considering 

issuance of an exemption from the 

requirements of Part 50 of Title 10 of the 

Code of Federal Regulations (10 CFR), 

Appendix R, ‘‘Fire Protection Program 

for Nuclear Power Facilities Operating 

Prior to January 1, 1979,’’ issued to 

Entergy Nuclear Operations, Inc. (the 

licensee), for the operation of the James 

A. FitzPatrick Nuclear Power Plant 

(JAFNPP) located in Oswego County, 

NY. Therefore, as required by 10 CFR 

51.21, the NRC is issuing this 

environmental assessment and finding 

of no significant impact. 

Environmental Assessment 

Identification of Proposed Action 

Regulatory Issue Summary (RIS) 

2006–10 documents the NRC position 

on the use of operator manual actions as 

part of a compliance strategy to meet the 

requirements of 10 CFR Part 50, 

Appendix R, Section III.G.2. The NRC 

requires plants which credit manual 

actions for 10 CFR Part 50, Appendix R, 

Section III.G.2 compliance to obtain 

NRC approval for the manual action 

using the exemption process in 

accordance with the requirements of 10 

CFR 50.12. In response to RIS 2006–10, 

the licensee requested this licensing 

action which would exempt the JAFNPP 

from the requirements of 10 CFR Part 

50, Appendix R, Section III.G.2. The 

proposed exemption would allow 

operator manual action, in a safe area of 

the reactor building, that will prevent 

the failure of the systems in Fire Area 

10 from affecting the ability to achieve 

and maintain hot shutdown conditions 

of the reactor as required by Title 10 of 

the Code of Federal Regulations Part 50, 

Appendix R, Section III.G.2. 

The proposed action is in accordance 

with the licensee’s application dated 

February 18, 2009, as supplemented by 

letters dated March 30, November 17, 

December 11, 2009, and January 19, 

2010. Portions of letters dated February 

18 and March 30, 2009, contain security 

related sensitive information, and are 

withheld from public disclosure in 

accordance with 10 CFR 2.390. Publicly 

available versions of the letters dated 

February 18, and March 30, 2009, are 

accessible electronically from the 

Agencywide Documents Access and 

Management System (ADAMS) with 

Accession Nos. ML090860980 and 

ML091320387, respectively. Also, the 

letters dated November 17, December 

11, 2009, and January 19, 2010, are 

accessible electronically from ADAMS 

with Accession Nos. ML093270075, 

ML093520408, and ML100210195, 

respectively. 

The Need for the Proposed Action 

The proposed action is needed to 

allow the licensee an alternate method, 

not authorized in 10 CFR Part 50, to 

achieve and maintain hot shutdown 

conditions in the event of a fire that 

could disable electrical cables and 

equipment in Fire Area 10. 

The criteria for granting specific 

exemptions from 10 CFR Part 50 

Regulations are specified in 10 CFR 

50.12. In accordance with 10 CFR 

50.12(a)(1), the NRC is authorized to 

grant an exemption upon determining 

that the exemption 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. 

Environmental Impacts of the Proposed 

Action 

The NRC has completed its evaluation 

of the environmental impact of the 

proposed action. The staff has 

concluded that such actions would not 

adversely affect the environment. The 

proposed action would not result in an 

increased radiological hazard. There 

will be no change to the radioactive 

effluent releases that effect radiation 

exposures to plant workers and 

members of the public. The proposed 

action will be performed inside the 

reactor building. No changes will be 

made to plant structures or the site 

property. Therefore, no changes or 

different types of radiological impacts 

are expected as a result of the proposed 

exemption. 

The proposed action does not result 

in changes to land use or water use, or 

result in changes to the quality or 

quantity of non-radiological effluents. 

No changes to the National Pollution 

Discharge Elimination System permit 

are needed. No effects on the aquatic or 

terrestrial habitat in the vicinity or the 

plant, or to threatened, endangered, or 

protected species under the Endangered 

Species Act, or impacts to essential fish 

habitat covered by the MagnusonSteven’s Act are expected. There are no 

impacts to historical and cultural 

resources. There would be no impact to 

socioeconomic resources. Therefore, no 

changes or different types of nonradiological environmental impacts are 

expected as a result of the proposed 

exemption. 

Accordingly, the NRC concludes that 

there are no significant environmental 

impacts associated with the proposed 

action. 

The details of the staff’s safety 

evaluation will be provided in the 

license exemption that will be issued as 

part of the letter to the licensee 

approving the exemption to the 

regulation. 

Environmental Impacts of the 

Alternatives to the Proposed Action 

As an alternative to the proposed 

action, the NRC staff considered denial 

of the proposed action (i.e., the ‘‘noaction’’ alternative). Denial of the 


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