Draft Regulatory Guide: Issuance, Availability, 18262-18263 [E9-9099]

Download as PDF 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. mstockstill on PROD1PC66 with NOTICES 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. VerDate Nov<24>2008 20:25 Apr 20, 2009 Jkt 217001 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. PO 00000 Frm 00065 Fmt 4703 Sfmt 4703 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 E:\FR\FM\21APN1.SGM 21APN1 mstockstill on PROD1PC66 with NOTICES Federal Register / Vol. 74, No. 75 / Tuesday, April 21, 2009 / Notices 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 VerDate Nov<24>2008 20:25 Apr 20, 2009 Jkt 217001 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 https://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also available in ADAMS (https:// 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. PO 00000 Frm 00066 Fmt 4703 Sfmt 4703 18263 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: E:\FR\FM\21APN1.SGM 21APN1

Agencies

[Federal Register Volume 74, Number 75 (Tuesday, April 21, 2009)]
[Notices]
[Pages 18262-18263]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-9099]


-----------------------------------------------------------------------

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

[[Page 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]); 
NUREG-series 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 
plant-specific 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 
safe-shutdown 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 https://www.nrc.gov/reading-rm/doc-collections/. Electronic copies are also available in 
ADAMS (https://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
This site is protected by reCAPTCHA and the Google Privacy Policy and Terms of Service apply.