Federal Register / Vol. 74, No. 153 / Tuesday, August 11, 2009 / Notices 40243 

relief ports. These license conditions 

committed to by the licensee in its letter 

dated April 10, 2008, and were 

implemented via Technical 

Specification Amendment No. 255. 

Date of issuance: July 22, 2009. 

Effective date: As of the date of 

issuance and shall be implemented 

within 180 days from the date of 

issuance. 

Amendment No.: 260. 

Renewed Facility Operating License 

No. DPR–40: The amendment revised 

the Technical Specifications. 

Date of initial notice in Federal 

Register: April 7, 2009 (74 FR 15773). 

The Commission’s related evaluation 

of the amendment is contained in a 

safety evaluation dated July 22, 2009. 

No significant hazards consideration 

comments received: No. 

Omaha Public Power District, Docket 

No. 50–285, Fort Calhoun Station, Unit 

No. 1, Washington County, Nebraska 

Date of amendment request: July 31, 

2008, as supplemented by letter dated 

May 8, 2009. 

Brief description of amendment: The 

amendment modified the transformer 

allowed outage time in Technical 

Specification (TS) Sections 2.7(2)a., 

2.7(2)b., and 2.7(2)c., and deleted the 

associated 2.7(2) special reporting 

requirements in TS 5.9.3j. 

Date of issuance: July 24, 2009. 

Effective date: As of the date of 

issuance and shall be implemented 

within 120 days from the date of 

issuance. 

Amendment No.: 261. 

Renewed Facility Operating License 

No. DPR–40: The amendment revised 

the Technical Specifications. 

Date of initial notice in Federal 

Register: February 10, 2009 (74 FR 

6666). The supplemental letter dated 

May 8, 2009, provided additional 

information that clarified the 

application, did not expand the scope of 

the application as originally noticed, 

and did not change the staff’s original 

proposed no significant hazards 

consideration determination as 

published in the Federal Register. 

The Commission’s related evaluation 

of the amendment is contained in a 

safety evaluation dated July 24, 2009. 

No significant hazards consideration 

comments received: No. 

Omaha Public Power District, Docket 

No. 50–285, Fort Calhoun Station, Unit 

No. 1, Washington County, Nebraska 

Date of amendment request: January 

30, 2009. 

Brief description of amendment: The 

amendment deleted paragraph e of 

Technical Specification (TS) 5.2.2, 

‘‘Unit Staff,’’ consistent with NRCapproved Technical Specification Task 

Force (TSTF) change traveler TSTF–511, 

Revision 0, ‘‘Eliminate Working Hour 

Restrictions from TS 5.2.2 to Support 

Compliance with 10 CFR Part 26.’’ All 

administrative deviations from the 

model application were addressed in 

the application. The availability of the 

TS improvement was published in the 

Federal Register on December 30, 2008 

(73 FR 79923), as part of the 

consolidated line item improvement 

process. 

Date of issuance: July 24, 2009. 

Effective date: As of the date of 

issuance and shall be implemented 

within 180 days from the date of 

issuance. 

Amendment No.: 262. 

Renewed Facility Operating License 

No. DPR–40: The amendment revised 

the Technical Specifications. 

Date of initial notice in Federal 

Register: April 7, 2009 (74 FR 15775). 

The Commission’s related evaluation 

of the amendment is contained in a 

safety evaluation dated July 24, 2009. 

No significant hazards consideration 

comments received: No. 

PSEG Nuclear LLC, Docket No. 50–354, 

Hope Creek Generating Station, Salem 

County, New Jersey 

Date of application for amendment: 

July 30, 2008, as supplemented by letter 

dated February 6, 2009. 

Brief description of amendment: The 

amendment: (1) Relocates Technical 

Specification (TS) 3/4.7.5, ‘‘Snubbers,’’ 

to the Technical Requirements Manual 

(TRM); (2) relocates TS 6.10.3.I, which 

specifies retention requirements for 

records of snubber service life 

monitoring, to the TRM; (3) adds new 

TS Limiting Condition for Operation 

(LCO) 3.0.8, ‘‘Inoperability of 

Snubbers;’’ and (4) modifies LCO 3.0.1 

to reference LCO 3.0.8. 

Date of issuance: July 15, 2009. 

Effective date: As of the date of 

issuance, to be implemented within 90 

days. 

Amendment No.: 179. 

Facility Operating License No. NPF– 

57: The amendment revised the TSs and 

the License. 

Date of initial notice in Federal 

Register: October 7, 2008 (73 FR 58677). 

The letter dated February 6, 2009, 

provided clarifying information that did 

not change the initial proposed no 

significant hazards consideration 

determination or expand the application 

beyond the scope of the original Federal 

Register notice. 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated July 15, 2009. 

No significant hazards consideration 

comments received: No. 

Tennessee Valley Authority, Docket No. 

50–390, Watts Bar Nuclear Plant (WBN), 

Unit 1, Rhea County, Tennessee 

Date of application for amendment: 

April 30, 2009. 

Brief description of amendment: The 

amendment revised WBN Unit 1 

Technical Specification (TS) 5.7, 

‘‘Procedures, Programs, and Manuals,’’ 

to correct a typographical error in the 

TS numbering from 5.2.7.20 to 5.7.2.20. 

Date of issuance: July 21, 2009. 

Effective date: As of the date of 

issuance and shall be implemented 

within 30 days of issuance. 

Amendment No.: 78. 

Facility Operating License No. NPF– 

90: Amendment revised TS 5.7. 

Date of initial notice in Federal 

Register: May 19, 2009 (74 FR 23449). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated July 21, 2009. 

No significant hazards consideration 

comments received: No. 

Dated at Rockville, Maryland, this 3rd day 

of August 2009. 

For the Nuclear Regulatory Commission. 

Joseph G. Giitter, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. E9–18946 Filed 8–10–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Sunshine Federal Register Notice 

AGENCY HOLDING THE MEETINGS: Nuclear 

Regulatory Commission. 

DATE: Weeks of August 10, 17, 24, 31, 

September 7, 14, 2009. 

PLACE: Commissioners’ Conference 

Room, 11555 Rockville Pike, Rockville, 

Maryland. 

STATUS: Public and closed. 

Week of August 10, 2009 

Tuesday, August 11, 2009 

9:30 a.m. 

Briefing on Research and Test Reactor 

Challenges (Public Meeting). 

(Contact: Duane Hardesty, 301 415– 

3724.) 

This meeting will be webcast live at 

the Web address—http://www.nrc.gov. 

Week of August 17, 2009—Tentative 

There are no meetings scheduled for 

the week of August 17, 2009. 


sroberts on DSKD5P82C1PROD with NOTICES
40244 Federal Register / Vol. 74, No. 153 / Tuesday, August 11, 2009 / Notices 

Week of August 24, 2009—Tentative 

There are no meetings scheduled for 

the week of August 24, 2009. 

Week of August 31, 2009—Tentative 

Thursday, September 3, 2009 

9:30 a.m. 

Meeting with Organization of 

Agreement States (OAS) and 

Conference of Radiation Control 

Program Directors (CRCPD) (Public 

Meeting) (Contact: Andrea Jones, 

301 415–2309). 

This meeting will be webcast live at 

the Web address—http://www.nrc.gov. 

Week of September 7, 2009—Tentative 

There are no meetings scheduled for 

the week of September 7, 2009. 

Week of September 14, 2009—Tentative 

There are no meetings scheduled for 

the week of September 14, 2009. 

*The schedule for Commission 

meetings is subject to change on short 

notice. To verify the status of meetings, 

call (recording)—(301) 415–1292. 

Contact person for more information: 

Rochelle Bavol, (301) 415–1651. 

Additional Information 

Affirmation of Southern Nuclear 

Operating Co. (Vogtle Electric 

Generating Plant, Units 3 and 4), LBP– 

09–3 (Ruling on Standing and 

Contention Admissibility) previously 

postponed from July 23, 2009, was held 

on July 31, 2009. 

The NRC Commission Meeting 

Schedule can be found on the Internet 

at: http://www.nrc.gov/about-nrc/policymaking/schedule.html. 

The NRC provides reasonable 

accommodation to individuals with 

disabilities where appropriate. If you 

need a reasonable accommodation to 

participate in these public meetings, or 

need this meeting notice or the 

transcript or other information from the 

public meetings in another format (e.g., 

braille, large print), please notify the 

NRC’s Disability Program Coordinator, 

Rohn Brown, at 301–492–2279, TDD: 

301–415–2100, or by e-mail at 

rohn.brown@nrc.gov. Determinations on 

requests for reasonable accommodation 

will be made on a case-by-case basis. 

This notice is distributed 

electronically to subscribers. If you no 

longer wish to receive it, or would like 

to be added to the distribution, please 

contact the Office of the Secretary, 

Washington, DC 20555 (301–415–1969), 

or send an e-mail to 

darlene.wright@nrc.gov. 

Dated: August 6, 2009. 

Rochelle C. Bavol, 

Office of the Secretary. 

[FR Doc. E9–19294 Filed 8–7–09; 4:15 pm] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0350] 

Withdrawal of Regulatory Guide 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Withdrawal of Regulatory Guide 

1.16, ‘‘Reporting of Operating 

Information—Appendix A Technical 

Specifications.’’ 

FOR FURTHER INFORMATION CONTACT: Carl 

S. Schulten, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, telephone: 301–415–1192 or email Carl.Schulten@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The Nuclear Regulatory Commission 

(NRC) is withdrawing Regulatory Guide 

(RG) 1.16, ‘‘Reporting of Operating 

Information—Appendix A Technical 

Specifications.’’ Revision 4 of the 

Regulatory Guide was issued for 

comment in August 1975 and never 

finalized. The guide provides a 

description of each of the periodic 

reports licensees are required to submit 

to demonstrate compliance with the 

reporting requirements listed in 

Appendix A, ‘‘Technical Specifications 

Related to Health and Safety’’ of the 

license. 

Regulatory Guide 1.16 is being 

withdrawn because it is no longer 

needed. Technical specification 

reporting requirements for licensees are 

contained in Title 10 of the Code of 

Federal Regulations, Part 50, ‘‘Domestic 

Licensing of Production and Utilization 

Facilities’’ (10 CFR Part 50) as well as 

other parts of 10 CFR Chapter I, 

‘‘Nuclear Regulatory Commission.’’ 

Guidance on the content and frequency 

of required reports is contained in 

Chapter 5, ‘‘Administrative Controls,’’ of 

the standard technical specifications in 

the following NUREGs: 

• NUREG–1430, Volume 1, ‘‘Standard 

Technical Specifications, Babcock and 

Wilcox Plants,’’ 

• NUREG–1431, Volume 1, ‘‘Standard 

Technical Specifications, Westinghouse 

Plants,’’ 

• NUREG–1432, Volume 1, ‘‘Standard 

Technical Specifications, Combustion 

Engineering Plants,’’ 

• NUREG–1433, Volume 1, Standard 

Technical Specifications, General 

Electric Plants, BWR/4,’’ and 

• NUREG–1434, Volume 1, Standard 

Technical Specifications, General 

Electric Plants, BWR/6.’’ 

II. Further Information 

Withdrawal of RG 1.16 does not, in 

and of itself, alter any prior or existing 

licensing commitments based on its use. 

The guidance provided in this RG is no 

longer necessary. Regulatory Guides 

may be withdrawn when their guidance 

is superseded by Congressional action, 

the methods or techniques described in 

the Regulatory Guide no longer describe 

a preferred approach, or the Regulatory 

Guide does not provide useful 

information. 

Regulatory guides are available for 

inspection or downloading through the 

NRC’s public Web site under 

‘‘Regulatory Guides’’ in the NRC’s 

Electronic Reading Room at http:// 

www.nrc.gov/reading-rm/doccollections. Regulatory guides are also 

available for inspection at the NRC’s 

Public Document Room (PDR), Room O– 

1 F21, One White Flint North, 11555 

Rockville Pike, Rockville, MD 20852– 

2738. The PDR’s mailing address is US 

NRC PDR, Washington, DC 20555–0001. 

You can reach the staff 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. 

Regulatory guides are not 

copyrighted, and NRC approval is not 

required to reproduce them. 

Dated at Rockville, Maryland, this 4th day 

of August, 2009. 

For the Nuclear Regulatory Commission. 

John N. Ridgely, 

Acting Chief, Regulatory Guide Development 

Branch, Division of Engineering, Office of 

Nuclear Regulatory Research. 

[FR Doc. E9–19211 Filed 8–10–09; 8:45 am] 

BILLING CODE 7590–01–P 

PENSION BENEFIT GUARANTY 

CORPORATION 

Proposed Submission of Information 

Collection for OMB Review; Comment 

Request; Customer Satisfaction 

Surveys and Focus Groups 

AGENCY: Pension Benefit Guaranty 

Corporation. 

ACTION: Notice of intention to request 

extension of OMB approval. 

SUMMARY: The Pension Benefit Guaranty 

Corporation (‘‘PBGC’’) intends to 

request that the Office of Management 

and Budget (‘‘OMB’’) extend its 

approval of a collection of information 


sroberts on DSKD5P82C1PROD with NOTICES