18262 Federal Register / Vol. 74, No. 75 / Tuesday, April 21, 2009 / Notices 

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 March 27, 2009. 

No significant hazards consideration 

comments received: No. 

Pacific Gas and Electric Company, 

Docket Nos. 50–275 and 50–323, Diablo 

Canyon Nuclear Power Plant, Unit Nos. 

1 and 2, San Luis Obispo County, 

California 

Date of application for amendments: 

April 3, 2008, as supplemented by 

letters dated June 20, October 1, 

November 6, and December 16, 2008. 

Brief description of amendments: The 

amendments revised Technical 

Specification (TS) 3.7.5, ‘‘Auxiliary 

Feedwater (AFW) System,’’ to remove 

Surveillance Requirement (SR) 3.7.5.6, 

and revised TS 3.7.6, ‘‘Condensate 

Storage Tank (CST) and Fire Water 

Storage Tank (FWST),’’ to remove the 

FWST level requirements, revise the 

CST level requirements, and revise TS 

3.7.6 to be consistent with the NUREG– 

1431, ‘‘Standard Technical 

Specifications (STS).’’ Specifically, 

these changes reflect design changes 

made to the CSTs and are necessary to 

support the on-line refurbishment of the 

FWST and replacement of the 

recirculation piping for the fire water 

pumps. The design changes to the CSTs 

are intended to eliminate the reliance on 

the FWST for additional seismicallyqualified feedwater supply and thus, 

make the existing TS requirements for 

the FWST unnecessary. 

Date of issuance: March 30, 2009. 

Effective date: As of its date of 

issuance and shall be implemented 

within 60 days from the date of 

issuance. 

Amendment Nos.: Unit 1–204; Unit 

2–205. 

Facility Operating License Nos. DPR– 

80 and DPR–82: The amendments 

revised the Facility Operating Licenses 

and Technical Specifications. 

Date of initial notice in Federal 

Register: July 29, 2008 (78 FR 43956). 

The supplemental letters dated June 20, 

October 1, November 6, and December 

16, 2008, 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 amendments is contained in a 

Safety Evaluation dated March 30, 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: 

September 18, 2008. 

Brief description of amendment: The 

amendment revised WBN Unit 1 

Technical Specification 3.8.7, 

‘‘Inverters—Operating.’’ The 

amendment revised the requirement to 

two inverters for each of the four 

channels. 

Date of issuance: March 24, 2009. 

Effective date: As of the date of 

issuance and shall be implemented 

within 240 days of issuance. 

Amendment No.: 76. 

Facility Operating License No. NPF– 

90: Amendment revises the Technical 

Specification 3.8.7 and Updated Final 

Safety Analysis Report. 

Date of initial notice in Federal 

Register: November 4, 2008 (73 FR 

65697). 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated March 24, 2009. 

No significant hazards consideration 

comments received: No. 

Wolf Creek Nuclear Operating 

Corporation, Docket No. 50–482, Wolf 

Creek Generating Station, Coffey 

County, Kansas 

Date of amendment request: March 

14, 2007, as supplemented by letters 

dated April 18, May 9, June 15, August 

31, September 12 and 20, October 16, 

November 16, two letters dated 

December 14, and December 18, 2007; 

two letters dated January 18, January 31, 

February 26 and 28, March 14, April 26, 

May 14, June 19, and July 31, 2008; and 

January 16 and 29, and February 17 and 

27, 2009. 

Brief description of amendment: The 

amendment revised the licensing basis 

for the Main Steam and Feedwater 

Isolation System (MSFIS) controls to 

incorporate field programmable gate 

array technology. Other related changes 

requested in the March 14, 2007, 

application were previously approved 

in Amendment No. 174, dated August 

28, 2007, Amendment No. 175, dated 

March 3, 2008, Amendment No. 176, 

dated March 21, 2008, and Amendment 

No. 177, dated April 3, 2008. 

Date of issuance: March 31, 2009. 

Effective date: Effective as of date of 

issuance and shall be implemented 

before entry into Mode 3 in the restart 

from Refueling Outage 17. 

Amendment No.: 181. 

Renewed Facility Operating License 

No. NPF–42. The amendment revised 

the Operating License. 

Date of initial notice in Federal 

Register: June 19, 2007 (72 FR 33785). 

The supplemental letters dated April 18, 

May 9, June 15, August 31, September 

12 and 20, October 16, November 16, 

two letters dated December 14, and 

December 18, 2007; two letters dated 

January 18, January 31, February 26 and 

28, March 14, April 26, May 14, June 19, 

and July 31, 2008; and January 16 and 

29, and February 17 and 27, 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 March 31, 2009. 

No significant hazards consideration 

comments received: No. 

Dated at Rockville, Maryland, this 10th day 

of April 2009. 

For the Nuclear Regulatory Commission. 

Joseph G. Giitter, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. E9–8832 Filed 4–20–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0176] 

Draft Regulatory Guide: Issuance, 

Availability 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of Issuance and 

Availability of Draft Regulatory Guide, 

DG–1214. 

FOR FURTHER INFORMATION CONTACT: Dan 

Frumkin, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, telephone (301) 415–2280, e-mail 

Dan.Frumkin@nrc.gov, or, R. A. Jervey, 

U.S. Nuclear Regulatory Commission, 

Washington, DC 20555–0001, telephone: 

(301) 251–7407, e-mail to raj@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 

mstockstill on PROD1PC66 with NOTICES

Federal Register / Vol. 74, No. 75 / Tuesday, April 21, 2009 / Notices 18263 

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), titled, 

‘‘Fire Protection for Nuclear Power 

Plants,’’ is temporarily identified by its 

task number, DG–1214, which should be 

mentioned in all related 

correspondence. DG–1214 is proposed 

Revision 2 of Regulatory Guide 1.189. 

The primary objectives of fire 

protection programs (FPPs) at U.S. 

nuclear plants are to minimize both the 

probability of occurrence and the 

consequences of fire. To meet these 

objectives, the FPPs for operating 

nuclear power plants are designed to 

provide reasonable assurance, through 

defense in depth, that a fire will not 

prevent the necessary safe-shutdown 

functions from being performed and that 

radioactive releases to the environment 

in the event of a fire will be minimized. 

The regulatory framework that the 

NRC has established for nuclear plant 

FPPs consists of a number of regulations 

and supporting guidelines, including, 

but not limited to, Title 10 of the Code 

of Federal Regulations, Part 50, 

‘‘Domestic Licensing of Production and 

Utilization Facilities,’’ (10 CFR Part 50), 

Appendix A, ‘‘General Design Criteria 

for Nuclear Power Plants,’’ General 

Design Criterion (GDC) 3, ‘‘Fire 

Protection;’’ 10 CFR 50.48, ‘‘Fire 

Protection;’’ Appendix R, ‘‘Fire 

Protection Program for Nuclear Power 

Facilities Operating Prior to January 1, 

1979,’’ to 10 CFR Part 50; regulatory 

guides; generic communications (e.g., 

generic letters [GLs], regulatory issue 

summaries [RISs], bulletins, and 

information notices [INs]); NUREGseries reports, including NUREG–0800, 

‘‘Standard Review Plan [SRP] for the 

Review of Safety Analysis Reports for 

Nuclear Power Plants;’’ and industry 

standards. Since not all of the fire 

protection regulations promulgated by 

the NRC apply to all plants, this guide 

does not categorize them as regulations. 

Licensees should refer to their plantspecific licensing bases to determine the 

applicability of a specific regulation to 

a specific plant. 

The NRC staff developed this guide to 

provide a comprehensive fire protection 

guidance document and to identify the 

scope and depth of fire protection that 

the staff would consider acceptable for 

nuclear power plants. The original issue 

of this guide addressed only plants 

operating as of January 1, 2001. Revision 

1 of the document added guidance for 

new reactor designs and incorporated 

the guidance previously included in 

Branch Technical Position (BTP) SPLB 

9.5–1, ‘‘Guidelines for Fire Protection 

for Nuclear Power Plants (formerly BTP 

CMEB 9.5–1).’’ DG–1214 incorporates 

guidance related to analysis of safeshutdown capabilities as found in 

regulatory position 5.3. 

II. Further Information 

The NRC staff is soliciting comments 

on DG–1214. Comments may be 

accompanied by relevant information or 

supporting data and should mention 

DG–1214 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). 

Personal information will not be 

removed from your comments. You may 

submit comments by any of the 

following methods: 

1. Mail comments to: Rulemaking, 

Directives, and Editing Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001. 

2. E-mail comments to: 

nrcrep.resource@nrc.gov. 

Requests for technical information 

about DG–1214 may be directed to the 

NRC contact, Dan Frumkin at (301) 415– 

2280 or e-mail to Dan.Frumkin@nrc.gov. 

Comments would be most helpful if 

received by May 29, 2009. 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. 

Electronic copies of DG–1214 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/. Electronic copies are also 

available in ADAMS (http:// 

www.nrc.gov/reading-rm/adams.html), 

under Accession No. ML090070453. 

In addition, regulatory guides are 

available for inspection at the NRC’s 

Public Document Room (PDR), which is 

located at 11555 Rockville Pike, 

Rockville, Maryland. 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) 397–4205, by fax at (301) 415– 

3548, and by e-mail to 

pdr.resource@nrc.gov. 

Regulatory guides are not 

copyrighted, and Commission approval 

is not required to reproduce them. 

Dated at Rockville, Maryland, this 7th day 

of April 2009. 

For the Nuclear Regulatory Commission. 

Andrea D. Valentin, 

Chief, Regulatory Guide Development Branch, 

Division of Engineering, Office of Nuclear 

Regulatory Research. 

[FR Doc. E9–9099 Filed 4–20–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards 

In accordance with the purposes of 

Sections 29 and 182b of the Atomic 

Energy Act (42 U.S.C. 2039, 2232b), the 

Advisory Committee on Reactor 

Safeguards (ACRS) will hold a meeting 

on May 7–9, 2009, 11545 Rockville Pike, 

Rockville, Maryland. The date of this 

meeting was previously published in 

the Federal Register on Monday, 

October 6, 2008 (73 FR 58268–58269). 

Thursday, May 7, 2009, Conference 

Room T–2b3, Two White Flint North, 

Rockville, Maryland 

8:30 a.m.–8:35 a.m.: Opening 

Remarks by the ACRS Chairman 

(Open)—The ACRS Chairman will make 

opening remarks regarding the conduct 

of the meeting. 

8:35 a.m.–10:30 a.m.: Proposed Rule 

on Risk-Informed Changes to Loss-ofCoolant Accident Technical 

Requirements (Open)—The Committee 

will hear presentations by and hold 

discussions with representatives of the 

NRC staff regarding the proposed rule 

on a voluntary risk-informed alternative 

to the current requirements of 

emergency core cooling systems, and 

related matters. 

10:45 a.m.–12:15 p.m.: Proposed 

Resolution of Generic Safety Issue 

(GSI)–163, ‘‘Multiple Steam Generator 

Tube Leakage’’ (Open)—The Committee 

will hear presentations by and hold 

discussions with representatives of the 

NRC staff regarding the proposed 

resolution of GSI–163 regarding 

multiple steam generator tube leakage, 

and related matters. 

1:15 p.m.–2:45 p.m.: Draft Final 

Regulatory Guide 1.214, ‘‘Response 

Procedures for Potential or Actual 

Aircraft Attacks’’ (Open/Closed)—The 

Committee will hear presentations by 

and hold discussions with 

representatives of the NRC staff 

regarding the draft final Regulatory 

Guide 1.214 and related matters. [Note: 

mstockstill on PROD1PC66 with NOTICES