Fire Protection for Nuclear Power Plants, 6243-6244 [2018-02870]

Download as PDF 6243 Federal Register / Vol. 83, No. 30 / Tuesday, February 13, 2018 / Notices addition, for the convenience of the reader, the ADAMS accession numbers are provided in a table in the ‘‘Availability of Documents’’ section of this document. • NRC’s PDR: You may examine and purchase copies of public documents at the NRC’s PDR, Room O1–F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Kristina L. Banovac, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415–7116, email: Kristina.Banovac@nrc.gov. SUPPLEMENTARY INFORMATION: I. Discussion Based upon the application dated May 25, 2016, as supplemented January 20, 2017, February 28, 2017, June 5, 2017, July 10, 2017, and August 16, 2017, the NRC has issued a renewed license to the licensee for the North Anna ISFSI, located in Louisa County, Virginia. The renewed license SNM– 2507 authorizes and requires operation of the North Anna ISFSI in accordance with the provisions of the renewed license and its technical specifications. The renewed license will expire on June 30, 2058. The licensee’s application for a renewed license complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the NRC’s rules and regulations. The NRC has made appropriate findings as required by the Act and the NRC’s regulations in chapter 1 of title 10 of the Code of Federal Regulations (10 CFR), and sets forth those findings in the renewed license. The agency afforded an opportunity for a hearing in the Notice of Opportunity for a Hearing published in the Federal Register on August 23, 2016 (81 FR 57629). The NRC received no request for a hearing or petition for leave to intervene following the notice. The NRC staff prepared a safety evaluation report for the renewal of the ISFSI license and concluded, based on that evaluation, the ISFSI will continue to meet the regulations in 10 CFR part 72. The NRC staff also prepared an environmental assessment and finding of no significant impact for the renewal of this license, which were published on February 2, 2018 (83 FR 4932). The NRC staff’s consideration of the impacts of continued storage of spent nuclear fuel (as documented in NUREG–2157, ‘‘Generic Environmental Impact Statement for Continued Storage of Spent Fuel’’) was included in the environmental assessment. The NRC staff concluded that renewal of this ISFSI license will not have a significant impact on the quality of the human environment. II. Availability of Documents The following table includes the ADAMS accession numbers for the documents referenced in this notice. For additional information on accessing ADAMS, see the ADDRESSES section of this document. ADAMS accession No. Document Licensee’s application, dated May 25, 2016 ................................................................................................................................. Response to First Request for Additional Information, dated January 20, 2017 .......................................................................... Response to Request for Referenced Information, dated February 28, 2017 .............................................................................. Decommissioning Cost Estimate Information, dated June 5, 2017 .............................................................................................. Response to Second Request for Additional Information, dated July 10, 2017 ........................................................................... Response to Second Request for Additional Information, Response to RAI 3–15, dated August 16, 2017 ............................... Special Nuclear Materials License No. SNM–2507 ...................................................................................................................... SNM–2507 Technical Specifications ............................................................................................................................................. NRC Safety Evaluation Report ...................................................................................................................................................... NRC Environmental Assessment .................................................................................................................................................. NUREG–2157, ‘‘Generic Environmental Impact Statement for Continued Storage of Spent Fuel’’ Vols. 1 and 2 ...................... Dated at Rockville, Maryland, this 8th day of February, 2018. For the Nuclear Regulatory Commission. Hipolito J. Gonzalez, Acting Chief, Renewals and Materials Branch, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2018–02904 Filed 2–12–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION sradovich on DSK3GMQ082PROD with NOTICES [NRC–2018–0024] Fire Protection for Nuclear Power Plants Nuclear Regulatory Commission. ACTION: Regulatory guide; revision. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 to Regulatory Guide (RG) 1.189, ‘‘Fire SUMMARY: VerDate Sep<11>2014 23:12 Feb 12, 2018 Jkt 244001 Protection for Nuclear Power Plants.’’ Revision 3 of RG 1.189 includes administrative changes involving editorial corrections that make the document consistent with existing policy. None of the revisions involve changes to the staff regulatory positions. This guide describes a method that the NRC staff considers acceptable to meet regulatory requirements for fire protection in nuclear power plants. ADDRESSES: Please refer to Docket ID NRC–2018–0024 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods: • Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC–2018–0024. Address questions about NRC dockets to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For PO 00000 Frm 00085 Fmt 4703 Sfmt 4703 ML16153A140 ML17025A128 ML17065A248 ML17160A300 ML17198A023 ML17233A170 ML18031A225 ML18031A227 ML18031A228 ML17311A450 ML14196A105, ML14196A107 technical questions, contact the individuals listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and then select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301–415–4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. RG 1.189 is available at ADAMS Accession No. ML17340A875. E:\FR\FM\13FEN1.SGM 13FEN1 6244 Federal Register / Vol. 83, No. 30 / Tuesday, February 13, 2018 / Notices sradovich on DSK3GMQ082PROD with NOTICES • NRC’s Public Document Room: You may examine and purchase copies of public documents at the NRC’s Public Document Room O1–F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. FOR FURTHER INFORMATION CONTACT: Daniel Frumkin, Office of Nuclear Reactor Regulations, telephone: 301– 415–2280, email: Daniel.Frumkin@ nrc.gov; or Stanley Gardocki, Office of Nuclear Regulatory Research, telephone: 301–415–1067, email: Stanley.Gardocki@nrc.gov. Both are staff members of the U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. SUPPLEMENTARY INFORMATION: I. Discussion The NRC is issuing a revision to an existing guide in the NRC ‘‘Regulatory Guide’’ series. Regulatory guides were developed to describe and make available to the public information methods that are acceptable to the NRC staff for implementing specific parts of the agency’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 NRC is issuing Revision 3 of RG 1.189 directly as a final RG, because the changes between Revision 2 and Revision 3 are administrative and nonsubstantive. Revision 3 of RG 1.189 also updated the guide to the current program guidance for RGs. The NRC added language to Section 1, ‘‘Fire Protection Program,’’ to clarify the primary objectives of fire protection plans. Since the issuance of Revision 2 of RG 1.189 in 2009, the NRC issued a Regulatory Issuance Summary to inform licensees that Inspection Manual Part 9900, Technical Guidance (TG 9900), ‘‘Operability Determinations & Functionality Assessments for Resolution of Degraded and Nonconforming Conditions Adverse to Quality and Safety,’’ was reissued as Inspection Manual Chapter (IMC) 0326, ‘‘Operability Determinations and Functionality Assessments for Conditions to Quality or Safety,’’ dated January 31, 2014. Revision 3 of RG 1.189 now includes a reference to IMC 0326 (see Section 1.5, ‘‘Compensatory Measures’’). Revision 3 of RG 1.189 also corrects typographic errors that previously appeared in Section 1.7.7, ‘‘Nonconforming Items,’’ Section 1.7.4, VerDate Sep<11>2014 23:12 Feb 12, 2018 Jkt 244001 ‘‘Inspection,’’ Section 2.1.1, ‘‘Transient Fire Hazards,’’ Section 3.2.1, ‘‘Fire Protection Water Supply,’’ and Section 3.2.3, ‘‘Fire Mains.’’ Previously, these errors occurred during publishing of the final regulatory guide, when several paragraphs were incorrectly indented, resulting in incorrect sub-bullet numbering. These changes are intended to improve clarity and do not substantially alter the staff’s regulatory guidance. II. Backfitting and Issue Finality Issuance of this final RG does not constitute backfitting as defined in section 50.109 of title 10 of the Code of Federal Regulations (10 CFR), (the Backfit Rule), and is not otherwise inconsistent with the issue finality provisions in 10 CFR part 52. The changes in Revision 3 of RG 1.189 are limited to editorial changes to improve clarity and correct errors. These changes do not fall within the kinds of agency actions that constitute backfitting or are subject to limitations in the issue finality provisions of 10 CFR part 52. Accordingly, the NRC did not address the Backfit Rule or issue finality provisions of 10 CFR part 52. III. Congressional Review Act Revision 3 of Regulatory Guide 1.189 is not a rule as defined in the Congressional Review Act (5 U.S.C. 801–808). IV. Submitting Suggestions for Improvement of Regulatory Guides Revision 3 of RG 1.189 is being issued without public comment. However, a member of the public may, at any time, submit suggestions to the NRC for improvement of existing RGs or for the development of new RGs to address new issues. Suggestions can be submitted on the NRC’s public website at http:// www.nrc.gov/reading-rm/doccollections/reg-guides/contactus.html. Suggestions will be considered in future updates and enhancements to the ‘‘Regulatory Guide’’ series. Dated at Rockville, Maryland, this 7th day of February 2018. For the Nuclear Regulatory Commission. Thomas H. Boyce, Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2018–02870 Filed 2–12–18; 8:45 am] BILLING CODE 7590–01–P PO 00000 Frm 00086 Fmt 4703 Sfmt 4703 NUCLEAR REGULATORY COMMISSION [Docket Nos. 72–1014, 72–59, and 50–271; NRC–2018–0020] Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Independent Spent Fuel Storage Installation Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a request submitted by Entergy Nuclear Operations, Inc. (ENO) on May 16, 2017, and supplemented on September 7, 2017 and December 7, 2017, for its general license to operate an independent spent fuel storage installation (ISFSI) at the Vermont Yankee Nuclear Power Station (VYNPS). This exemption would permit the VYNPS to use a new regionalized loading pattern, load fuel cooled for at least 2 years, and establish a per-cell maximum average burnup limit at 65,000 megawatt days per metric ton of uranium (MWD/MTU) in HI–STORM 100 multi-purpose canister (MPC)-68M using Certificate of Compliance (CoC) No. 1014, Amendment No. 10. DATES: February 13, 2018. ADDRESSES: Please refer to Docket ID NRC–2018–0020 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods: • Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC–2018–0020. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–9127; email: Jennifer.Broges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and then select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301–415–4737, or by email to pdr.resource@nrc.gov. The ADAMS Accession No. for each SUMMARY: E:\FR\FM\13FEN1.SGM 13FEN1

Agencies

[Federal Register Volume 83, Number 30 (Tuesday, February 13, 2018)]
[Notices]
[Pages 6243-6244]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-02870]


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NUCLEAR REGULATORY COMMISSION

[NRC-2018-0024]


Fire Protection for Nuclear Power Plants

AGENCY: Nuclear Regulatory Commission.

ACTION: Regulatory guide; revision.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing 
Revision 3 to Regulatory Guide (RG) 1.189, ``Fire Protection for 
Nuclear Power Plants.'' Revision 3 of RG 1.189 includes administrative 
changes involving editorial corrections that make the document 
consistent with existing policy. None of the revisions involve changes 
to the staff regulatory positions. This guide describes a method that 
the NRC staff considers acceptable to meet regulatory requirements for 
fire protection in nuclear power plants.

ADDRESSES: Please refer to Docket ID NRC-2018-0024 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly-available information related to this document 
using any of the following methods:
     Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0024. Address 
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: [email protected]. For technical questions, contact 
the individuals listed in the FOR FURTHER INFORMATION CONTACT section 
of this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to [email protected]. The 
ADAMS accession number for each document referenced (if it is available 
in ADAMS) is provided the first time that it is mentioned in this 
document. RG 1.189 is available at ADAMS Accession No. ML17340A875.

[[Page 6244]]

     NRC's Public Document Room: You may examine and purchase 
copies of public documents at the NRC's Public Document Room O1-F21, 
One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. 
Regulatory guides are not copyrighted, and NRC approval is not required 
to reproduce them.

FOR FURTHER INFORMATION CONTACT: Daniel Frumkin, Office of Nuclear 
Reactor Regulations, telephone: 301-415-2280, email: 
[email protected]; or Stanley Gardocki, Office of Nuclear 
Regulatory Research, telephone: 301-415-1067, email: 
[email protected]. Both are staff members of the U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION:

I. Discussion

    The NRC is issuing a revision to an existing guide in the NRC 
``Regulatory Guide'' series. Regulatory guides were developed to 
describe and make available to the public information methods that are 
acceptable to the NRC staff for implementing specific parts of the 
agency'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 NRC is issuing Revision 3 of RG 1.189 directly as a final RG, 
because the changes between Revision 2 and Revision 3 are 
administrative and non-substantive. Revision 3 of RG 1.189 also updated 
the guide to the current program guidance for RGs. The NRC added 
language to Section 1, ``Fire Protection Program,'' to clarify the 
primary objectives of fire protection plans.
    Since the issuance of Revision 2 of RG 1.189 in 2009, the NRC 
issued a Regulatory Issuance Summary to inform licensees that 
Inspection Manual Part 9900, Technical Guidance (TG 9900), 
``Operability Determinations & Functionality Assessments for Resolution 
of Degraded and Nonconforming Conditions Adverse to Quality and 
Safety,'' was reissued as Inspection Manual Chapter (IMC) 0326, 
``Operability Determinations and Functionality Assessments for 
Conditions to Quality or Safety,'' dated January 31, 2014. Revision 3 
of RG 1.189 now includes a reference to IMC 0326 (see Section 1.5, 
``Compensatory Measures'').
    Revision 3 of RG 1.189 also corrects typographic errors that 
previously appeared in Section 1.7.7, ``Nonconforming Items,'' Section 
1.7.4, ``Inspection,'' Section 2.1.1, ``Transient Fire Hazards,'' 
Section 3.2.1, ``Fire Protection Water Supply,'' and Section 3.2.3, 
``Fire Mains.'' Previously, these errors occurred during publishing of 
the final regulatory guide, when several paragraphs were incorrectly 
indented, resulting in incorrect sub-bullet numbering. These changes 
are intended to improve clarity and do not substantially alter the 
staff's regulatory guidance.

II. Backfitting and Issue Finality

    Issuance of this final RG does not constitute backfitting as 
defined in section 50.109 of title 10 of the Code of Federal 
Regulations (10 CFR), (the Backfit Rule), and is not otherwise 
inconsistent with the issue finality provisions in 10 CFR part 52. The 
changes in Revision 3 of RG 1.189 are limited to editorial changes to 
improve clarity and correct errors. These changes do not fall within 
the kinds of agency actions that constitute backfitting or are subject 
to limitations in the issue finality provisions of 10 CFR part 52. 
Accordingly, the NRC did not address the Backfit Rule or issue finality 
provisions of 10 CFR part 52.

III. Congressional Review Act

    Revision 3 of Regulatory Guide 1.189 is not a rule as defined in 
the Congressional Review Act (5 U.S.C. 801-808).

IV. Submitting Suggestions for Improvement of Regulatory Guides

    Revision 3 of RG 1.189 is being issued without public comment. 
However, a member of the public may, at any time, submit suggestions to 
the NRC for improvement of existing RGs or for the development of new 
RGs to address new issues. Suggestions can be submitted on the NRC's 
public website at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html. Suggestions will be considered in future updates 
and enhancements to the ``Regulatory Guide'' series.

    Dated at Rockville, Maryland, this 7th day of February 2018.

    For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic Issues Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2018-02870 Filed 2-12-18; 8:45 am]
 BILLING CODE 7590-01-P