61530 Federal Register / Vol. 75, No. 192 / Tuesday, October 5, 2010 / Notices 

Effective date: As of the date of 

issuance and shall be implemented 90 

days from the date of issuance. 

Amendment No.: 228. 

Facility Operating License No. NPF– 

38: The amendment revised the Facility 

Operating License and Technical 

Specifications. 

Date of initial notice in Federal 

Register: December 15, 2009 (74 FR 

66384). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated September 13, 

2010. 

No significant hazards consideration 

comments received: No. 

Exelon Generation Company, LLC, 

Docket Nos. STN 50–456 and STN 50– 

457, Braidwood Station, Units 1 and 2 

(Braidwood), Will County, Illinois; 

Docket Nos. STN 50–454 and STN 50– 

455, Byron Station, Unit Nos. 1 and 2 

(Byron), Ogle County, Illinois 

Date of application for amendment: 

March 29, 2010. 

Brief description of amendment: The 

amendments revise Technical 

Specification (TS) 5.5.7, ‘‘Reactor 

Coolant Pump Flywheel Inspection 

Program,’’ to extend the reactor coolant 

pump (RCP) motor flywheel 

examination frequency from the 

currently-approved 10-year inspection 

interval to an interval not to exceed 20 

years for certain Braidwood and Byron 

RCPs. These changes are consistent with 

TS Task Force (TSTF) traveler TSTF– 

421, ‘‘Revision to RCP Flywheel 

Inspection Program (WCAP–15666),’’ 

Revision 0, that has been approved 

generically for the Westinghouse 

Standard Technical Specifications, 

NUREG–1431. A notice announcing the 

availability of this proposed TS change 

using the Consolidated Line Item 

Improvement Process was published in 

the Federal Register on October 22, 

2003 (68 FR 60422). 

Date of issuance: September 16, 2010. 

Effective date: As of the date of 

issuance and shall be implemented 

within 60 days. 

Amendment Nos.: Braidwood Unit 1– 

163; Braidwood Unit 2–163; Byron Unit 

No. 1–169; and Byron Unit No. 2–169. 

Facility Operating License Nos. NPF– 

72, NPF–77, NPF–37, and NPF–66: The 

amendments revise the TSs and 

Licenses. 

Date of initial notice in Federal 

Register: May 18, 2010 (75 FR 27827). 

The Commission’s related evaluation 

of the amendments is contained in a 

Safety Evaluation dated September 16, 

2010. 

No significant hazards consideration 

comments received: No. 

Exelon Generation Company, LLC, 

Docket No. 50–461, Clinton Power 

Station, Unit No. 1, DeWitt County, 

Illinois 

Date of application for amendment: 

April 2, 2010, as supplemented by 

letters dated June 19, 2009, and March 

31, 2010. 

Brief description of amendment: The 

amendment revises the Exelon Nuclear 

Radiological Emergency Plan Annex for 

Clinton Station, Table B–1, ‘‘Minimum 

Staffing Requirements for the On-Shift 

Clinton Station ERO,’’ to increase the 

Non-Licensed Operator staffing from 

two to four, allow in-plant protective 

actions to be performed by personnel 

assigned to other functions, and replace 

a Mechanical Maintenance person with 

a Non-Licensed Operator. 

Date of issuance: September 21, 2010. 

Effective date: As of the date of 

issuance and shall be implemented 

within 30 days. 

Amendment No.: 191. 

Facility Operating License No. NPF– 

62: The amendment revised the Facility 

Operating License. 

Date of initial notice in Federal 

Register: June 1, 2010 (75 FR 30445). 

The June 19, 2009, and March 31, 

2010, supplement, contained clarifying 

information and did not change the NRC 

staff’s initial proposed finding of no 

significant hazards consideration. 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated September 21, 

2010. 

No significant hazards consideration 

comments received: No. 

Exelon Generation Company, LLC, 

Docket Nos. 50–373 and 50–374, 

LaSalle County Station, Units 1 and 2, 

LaSalle County, Illinois 

Date of application for amendments: 

January 27, 2010, as supplemented by 

letters dated May 12, and May 13, 2010. 

Brief description of amendments: The 

amendments would revise the Operating 

License and technical Specifications to 

implement an increase of approximately 

1.65 percent in rated thermal power 

from the current licensed thermal power 

of 3489 megawatts thermal (MWt) to 

3546 MWt. 

Date of issuance: September 16, 2010. 

Effective date: As of the date of 

issuance and shall be implemented 

within 90 days for Unit 1 and within 90 

days of completion of refueling outage 

L2R13, which is currently scheduled for 

March 2011, for Unit 2. 

Amendment Nos.: 198/185. 

Facility Operating License Nos. NPF– 

11 and NPF–18: The amendments 

revised the Technical Specifications and 

License. 

Date of initial notice in Federal 

Register: May 11, 2010 (75 FR 26289). 

The May 12, and May 13, 2010, 

supplements, contained clarifying 

information and did not change the NRC 

staff’s initial proposed finding of no 

significant hazards consideration. 

The Commission’s related evaluation 

of the amendments is contained in a 

Safety Evaluation dated September 16, 

2010. 

No significant hazards consideration 

comments received: No. 

Dated at Rockville, Maryland, this 23rd day 

of September 2010. 

For the Nuclear Regulatory Commission. 

Joseph G. Giitter, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2010–24815 Filed 10–4–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2010–0312] 

Issuance of Regulatory Guides 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice. 

SUMMARY: The Nuclear Regulatory 

Commission (NRC) is providing notice 

of the issuance and availability of 

Regulatory Guides 1.84, Rev. 35, 

‘‘Design, Fabrication, and Materials 

Code Case Acceptability, ASME Section 

III,’’ and RG 1.147, Rev. 16, ‘‘Inservice 

Inspection Code Case Acceptability, 

ASME Section XI, Division 1.’’ 

FOR FURTHER INFORMATION CONTACT: 

Wallace E. Norris, Component Integrity 

Branch, Division of Engineering, Office 

of Nuclear Regulatory Research, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, telephone 

(301) 251–7650 or e-mail 

Wallace.Norris@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The NRC is issuing two final 

Regulatory Guides (RGs) in the agency’s 

‘‘Regulatory Guide’’ series: RG 1.84 and 

RG 1.147. This series was developed to 

describe and make available to the 

public specific program information. 

This information includes methods 

acceptable to the NRC staff for 

implementing specific parts of the 

agency’s regulations, techniques the 

staff uses in evaluating specific 

problems or postulated accidents, and 

data the staff needs in its review of 

applications for permits and licenses. 

mstockstill on DSKH9S0YB1PROD with NOTICES

Federal Register / Vol. 75, No. 192 / Tuesday, October 5, 2010 / Notices 61531 

The NRC published a proposed rule 

that would incorporate by reference RG 

1.84, Revision 35, and RG 1.147, 

Revision 16, on June 2, 2009, 74 FR 

26303. On the same date, the NRC 

published a parallel notice of 

availability for the draft regulatory 

guides and opportunity for public 

comment. See, 74 FR 26440. The NRC 

provided a 75-day public comment 

period for both the proposed rule and 

the draft RGs, which ended on August 

17, 2009. 

This Notice of Issuance and 

Availability addresses final RGs 1.84 

and 1.147. The final rule that 

incorporates RG 1.84 and RG 1.147 by 

reference into Title 10, part 50, of the 

Code of Federal Regulations (10 CFR 

Part 50), ‘‘Domestic Licensing of 

Production and Utilization Facilities’’ 

contains the regulatory analysis and 

responses to the public comments 

relative to the final RGs and is available 

in the NRC’s Agencywide Documents 

Access and Management System 

(ADAMS) under Accession No. 

ML100560148. For further information 

on the final rule, contact Manash K. 

Bagchi, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, telephone (301) 415–2905, e-mail 

Manash.Bagchi@nrc.gov. 

This action allows nuclear power 

plant licensees, and applicants for 

standard design certifications, standard 

design approvals, and manufacturing 

licenses under the regulations that 

govern license certifications, and 

approves the nuclear power plants to 

use the Code Cases listed in these RGs 

as alternatives to requirements in the 

ASME Boiler and Pressure Vessel (BPV) 

Code regarding the construction and inservice inspection (ISI) of nuclear power 

plant components. RG 1.84 lists all 

Section III Code Cases that NRC has 

approved for use, and RG 1.147 lists all 

Section XI Code Cases that have been 

approved for use. For these RG 

revisions, NRC reviewed the Code Cases 

listed in Supplements 2B11 to the 2004 

Edition of the ASME BPV Code and 

Supplement 0 to the 2007 Edition 

(Supplement 0 also serves as 

Supplement 12 to the 2004 Edition). 

II. Further Information 

Copies of the RGs are available in 

ADAMS under Accession Numbers 

ML101800532 (RG 1.84) and 

ML101800536 (RG 1.147). Electronic 

copies of RG 1.84 and RG 1.147 are 

available through the NRC=s public 

Web site under ‘‘Regulatory Guides’’ at 

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

In addition, RGs are available for 

inspection at NRC’s Public Document 

Room (PDR) located at 11555 Rockville 

Pike, Rockville, Maryland. The PDR’s 

mailing address is USNRC PDR, 

Washington, DC 20555–0001. The PDR 

also can be reached by telephone at 

(301) 415–4737 or (800) 397–4205, by 

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

pdr.resource@nrc.gov. 

Regulatory guides are not copyrighted 

and NRC approval is not required to 

reproduce them. 

Dated at Rockville, Maryland, this 23rd day 

of September, 2010. 

For the U.S. Nuclear Regulatory 

Commission. 

Brian W. Sheron, 

Director, Office of Nuclear Regulatory 

Research. 

[FR Doc. 2010–24812 Filed 10–4–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2010–0311] 

Issuance of Regulatory Guide 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice. 

SUMMARY: The Nuclear Regulatory 

Commission (NRC) is providing notice 

of the issuance and availability of 

Regulatory Guide 1.193, Rev. 3, ‘‘ASME 

Code Cases Not Approved for Use.’’ 

FOR FURTHER INFORMATION CONTACT: 

Wallace E. Norris, Component Integrity 

Branch, Division of Engineering, Office 

of Nuclear Regulatory Research, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, telephone 

(301) 251–7650 or e-mail 

Wallace.Norris@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The NRC is issuing Regulatory Guide 

(RG) 1.193 in the agency’s ‘‘Regulatory 

Guide’’ series. This series was developed 

to describe and make available to the 

public specific program information. 

This information includes methods 

acceptable to the NRC staff for 

implementing specific parts of the 

agency’s regulations, techniques the 

staff uses in evaluating specific 

problems or postulated accidents, and 

data the staff needs in its review of 

applications for permits and licenses. 

II. Discussion 

RG 1.193 lists the Code Cases that 

NRC has determined not to be 

acceptable for use on a generic basis. 

Two separate RGs list Code Cases that 

NRC has found to be acceptable 

alternatives to requirements in the 

American Society of Mechanical 

Engineers (ASME) Boiler and Pressure 

Vessel Code. RG 1.84, Rev. 35, ‘‘Design, 

Fabrication, and Materials Code Case 

Acceptability, ASME Section III,’’ lists 

all Section III Code Cases that NRC has 

approved for use. RG 1.147, Rev. 16, 

‘‘Inservice Inspection Code Case 

Acceptability, ASME Section XI, 

Division 1,’’ lists all Section XI Code 

Cases that NRC has approved for use. 

RG 1.84 and RG 1.147 are being noticed 

under a separate notice of availability. 

For Revision 3 of RG 1.193, NRC 

reviewed the Code Cases listed in 

Supplements 2–11 to the 2004 Edition 

of the ASME Boiler and Pressure Vessel 

(BPV) Code and Supplement 0 to the 

2007 Edition (Supplement 0 also serves 

as Supplement 12 to the 2004 Edition). 

A brief description of the basis for the 

unacceptability determination is 

provided with each Code Case in RG 

1.193. Licensees may submit a request 

to implement one or more of the Code 

Cases listed in RG 1.193 through 10 CFR 

50.55a(a)(3), which permits the use of 

alternatives to the Code requirements 

referenced in 10 CFR 50.55a provided 

that the proposed alternatives result in 

an acceptable level of quality and safety. 

Licensees must submit a plant-specific 

request that addresses NRC’s concerns 

about the Code Case at issue. 

III. Further Information 

In June 2009, draft Regulatory Guide 

(DG) 1191, DG 1192, and DG 1193 were 

published with a public comment 

period of 60 days from their issuance. 

The comment period closed on August 

16, 2009. Copies of the final RGs are 

available in ADAMS under Accession 

Numbers ML101800532 (RG 1.84), 

ML101800536 (RG 1.147), and 

ML101800540 (RG 1.193). 

The responses to the public comments 

on the three RGs are contained in the 

final rule that incorporates RG 1.84 and 

RG 1.147 by reference into Title 10, part 

50, of the Code of Federal Regulations 

(10 CFR part 50), ‘‘Domestic Licensing of 

Production and Utilization Facilities,’’ 

and is available in NRC’s Agencywide 

Documents Access and Management 

System (ADAMS) under Accession No. 

ML100560148. For further information 

on the final rule, contact Manash K. 

Bagchi, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, telephone (301) 415–2905, e-mail 

Manash.Bagchi@nrc.gov. 

Electronic copies of RG 1.84, RG 

1.147, and RG 1.193 are available 

through NRC’s public Web site under 

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