Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors, 63516-63517 [2013-24888]

Download as PDF 63516 Federal Register / Vol. 78, No. 206 / Thursday, October 24, 2013 / Notices mstockstill on DSK4VPTVN1PROD with NOTICES official, Mr. Brad Fuller of the Pennsylvania Department of Environmental Protection, regarding the environmental impact of the proposed action. The State official had no comments. IV. Draft Finding of No Significant Impact The NRC is proposing to amend Renewed Facility Operating License Nos. DPR–44 and DPR–56 for PBAPS, Units 2 and 3. The proposed amendments would authorize an increase in the maximum reactor power level from 3514 MWt to 3951 MWt. The NRC has determined not to prepare an Environmental Impact Statement for the proposed action. The proposed action will not have a significant effect on the quality of the human environment because, amending the licenses with the higher maximum reactor power level, will not result in any significant radiological or nonradiological impacts. Accordingly, the NRC has determined that a draft Finding of No Significant Impact (FONSI) is appropriate. The NRC’s draft Environmental Assessment (EA), included in Section III above, is incorporated by reference into this finding. The NRC’s draft FONSI and the related environmental documents listed below are available for public inspection and may be inspected online through the NRC’s Agencywide Documents Access and Management System (ADAMS) at http:// www.nrc.gov/reading-rm/adams.html. You may also inspect these documents at the NRC’s Public Document Room as discussed in Section I, ‘‘Accessing Information and Submitting Comments,’’ above. The NRC’s draft FONSI and the associated draft EA are available in ADAMS at Accession No. ML13202A081. Related environmental documents supporting the NRC’s draft FONSI are as follows: (1) Attachment 8, ‘‘Supplemental Environmental Report,’’ to Exelon’s EPU amendment request dated September 28, 2012 (ADAMS Accession No. ML12286A011); (2) NUREG–1437, Volume 1, Addendum 1, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Main Report, Section 6.3—Transportation, Table 9.1, Summary of findings on NEPA issues for license renewal of nuclear power plants,’’ dated August 1999 (ADAMS Accession No. ML040690720); (3) Supplement 10 to NUREG–1437, ‘‘Generic Environmental Impact Statement for the License Renewal of Nuclear Power Plants, Regarding Peach VerDate Mar<15>2010 17:25 Oct 23, 2013 Jkt 232001 Bottom Atomic Power Station, Units 2 and 3,’’ dated January 2003 (ADAMS Accession No. ML030270059); and (4) ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants,’’ NUREG–1437, Volume 1, Revision 1, dated June 2013 (ADAMS Accession No. ML13106A241). Dated at Rockville, Maryland, this 1st day of October 2013. For the Nuclear Regulatory Commission. Veronica Rodriguez, Acting Chief, Plant Licensing Branch I–2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2013–24902 Filed 10–23–13; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2012–0134] Initial Test Program of Emergency Core Cooling Systems for New BoilingWater Reactors Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a new regulatory guide (RG), 1.79.1, ‘‘Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors.’’ This RG describes testing methods the NRC staff considers acceptable for demonstrating the operability of emergency core cooling systems (ECCSs) for boiling-water reactors (BWRs) whose licenses are issued after the date of issuance of this RG (new BWRs). ADDRESSES: Please refer to Docket ID NRC–2012–0134 when contacting the NRC about the availability of information regarding this document. You may access publicly-available information related to this action by the following methods: • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC–2012–0134. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; email: Carol.Gallagher@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 access publicly available documents online in the NRC Library at http://www.nrc.gov/readingrm/adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and SUMMARY: PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 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 in this notice (if that document is available in ADAMS) is provided the first time that a document is referenced. Revision 0 of Regulatory Guide 1.79.1, is available in ADAMS under Accession No. ML12300A329. The regulatory analysis for Draft Regulatory Guide (DG)–1277 may be found in ADAMS under Accession No. ML12300A328. • 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. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. FOR FURTHER INFORMATION CONTACT: Frank X. Talbot, Office of New Reactors; telephone: 301–415–4146, email: Frank.Talbot@nrc.gov, or Mark P. Orr, Office of Nuclear Regulatory Research; telephone: 301–251–7495, email: Mark.Orr@nrc.gov, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. SUPPLEMENTARY INFORMATION: I. Introduction The NRC is issuing a new guide in the NRC’s ‘‘Regulatory Guide’’ series. This series was developed to describe and make available to the public information such as 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. This new guide describes methods that the staff of the NRC considers acceptable for demonstrating compliance with the NRC regulations as they relate to preoperational, low power, and power ascension testing features of the ECCS for new BWRs. This RG also describes methods that the NRC staff finds acceptable for initial plant testing of ECCS structures, systems, and components (SSCs). Additionally, this RG describes methods the NRC staff finds acceptable for testing of the Isolation Condenser System (ICS) and the Reactor Core Isolation Cooling (RCIC) System, which support functions for alternate water injection during station blackout. E:\FR\FM\24OCN1.SGM 24OCN1 Federal Register / Vol. 78, No. 206 / Thursday, October 24, 2013 / Notices II. Additional Information Regulatory Guide 1.79.1 was issued with a temporary identification as Draft Regulatory Guide (DG)–1277, ‘‘Initial Test Program of Emergency Core Cooling Systems for Boiling-Water Reactors.’’ DG–1277, was published in the Federal Register on June 15, 2012 (77 FR 36014), for a 60-day public comment period. The public comment period closed on August 15, 2012. Forty-five public comments were received during this period. The NRC staff’s responses to the public comments on DG–1277 are available in ADAMS under Accession No. ML12300A330. III. Congressional Review Act This regulatory guide is a rule as defined in the Congressional Review Act (5 U.S.C. 801–808). However, the Office of Management and Budget has not found it to be a major rule as defined in the Congressional Review Act. IV. Backfitting Analysis mstockstill on DSK4VPTVN1PROD with NOTICES Issuance of this revised RG does not constitute backfitting as defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise inconsistent with the issue finality provisions in 10 CFR part 52. As discussed in the ‘‘Implementation’’ section of this RG, the NRC has no current intention to impose this RG on holders of current operating licenses, early site permits or combined licenses. The NRC may apply this RG to applications for operating licenses, early site permits and combined licenses docketed by the NRC as of the date of issuance of the final RG, as well as to future applications for operating licenses, early site permits, and combined licenses submitted after the issuance of the RG. Such action does not constitute backfitting as defined in 10 CFR 50.109(a)(1) and is not otherwise inconsistent with the applicable issue finality provision in 10 CFR part 52, inasmuch as such applicants or potential applicants are not within the scope of entities protected by the Backfit Rule or the relevant issue finality provisions in part 52. Dated at Rockville, Maryland, this 4th day of October, 2013. For the Nuclear Regulatory Commission. Thomas H. Boyce, Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2013–24888 Filed 10–23–13; 8:45 am] BILLING CODE 7590–01–P VerDate Mar<15>2010 17:25 Oct 23, 2013 Jkt 232001 NUCLEAR REGULATORY COMMISSION [NRC–2012–0231] Control of Ferrite Content in Stainless Steel Weld Metal Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision to Regulatory Guide (RG) 1.31, ‘‘Control of Ferrite Content in Stainless Steel Weld Metal.’’ This guide (Revision 4) describes a method that the NRC staff considers acceptable for controlling ferrite content in stainless steel weld metal. It updates the guide to remove references to outdated standards and to remove an appendix that has been incorporated into relevant specifications. ADDRESSES: Please refer to Docket ID NRC–2012–0231 when contacting the NRC about the availability of information regarding this document. You may access publicly-available information related to this action by the following methods: • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC–2012–0231. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual(s) listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC Library at http://www.nrc.gov/readingrm/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 in this notice (if that document is available in ADAMS) is provided the first time that a document is referenced. Revision 4 of Regulatory Guide 1.31 is available in ADAMS under Accession No. ML13211A485. The regulatory analysis may be found in ADAMS under Accession No. ML13211A490. • 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. SUMMARY: PO 00000 Frm 00070 Fmt 4703 Sfmt 4703 63517 Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. FOR FURTHER INFORMATION CONTACT: Michael Benson, telephone: 301–251– 7492; email: Michael.Benson@nrc.gov; or Harriet Karagiannis, telephone: 301– 251–7477; email: Harriet.Karagiannis@ nrc.gov. Both of Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. SUPPLEMENTARY INFORMATION: I. Introduction The NRC is issuing a revision to an existing guide in the NRC’s ‘‘Regulatory Guide’’ series. This series was developed to describe and make available to the public information such as 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. Revision 4 of RG 1.31 was issued with a temporary identification as Draft Regulatory Guide DG–1279 and it describes a method that the staff of the NRC considers acceptable for complying with the Commission’s regulations concerning establishing and implementing a procedure for the control of ferrite content in stainless steel weld metal. This guide provides methods that the NRC’s staff considers acceptable to implement certain requirements in part 50 of Title 10 of the Code of Federal Regulations (10 CFR), ‘‘Domestic Licensing of Production and Utilization Facilities.’’ Since microfissures in austenitic welds may have an adverse effect on the integrity of components, the control of weld deposits to ensure the presence of delta ferrite in these welds is advisable. Reason for Revision To achieve control of ferrite content in stainless steel welds, the original version of this guide, Safety Guide 31, ‘‘Control of Stainless Steel Welding,’’ issued August 1972, provided guidance to test production welds. This guidance was retained in Revision 1 of the Safety Guide, which was issued June 1973 as Regulatory Guide 1.31, ‘‘Control of Ferrite Content in Stainless Steel Weld Metal.’’ Revision 2 (issued May 1977) and Revision 3 (issued April 1978) to this guide were based on recommendations of an NRC/industry study group. Revision 2 of this guide replaced the guidance for testing production welds in Revision 1 with E:\FR\FM\24OCN1.SGM 24OCN1

Agencies

[Federal Register Volume 78, Number 206 (Thursday, October 24, 2013)]
[Notices]
[Pages 63516-63517]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-24888]


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NUCLEAR REGULATORY COMMISSION

[NRC-2012-0134]


Initial Test Program of Emergency Core Cooling Systems for New 
Boiling-Water Reactors

AGENCY: Nuclear Regulatory Commission.

ACTION: Regulatory guide; issuance.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a new 
regulatory guide (RG), 1.79.1, ``Initial Test Program of Emergency Core 
Cooling Systems for New Boiling-Water Reactors.'' This RG describes 
testing methods the NRC staff considers acceptable for demonstrating 
the operability of emergency core cooling systems (ECCSs) for boiling-
water reactors (BWRs) whose licenses are issued after the date of 
issuance of this RG (new BWRs).

ADDRESSES: Please refer to Docket ID NRC-2012-0134 when contacting the 
NRC about the availability of information regarding this document. You 
may access publicly-available information related to this action by the 
following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0134. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@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 access publicly available documents online in the NRC 
Library 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 in this notice (if that document is 
available in ADAMS) is provided the first time that a document is 
referenced. Revision 0 of Regulatory Guide 1.79.1, is available in 
ADAMS under Accession No. ML12300A329. The regulatory analysis for 
Draft Regulatory Guide (DG)-1277 may be found in ADAMS under Accession 
No. ML12300A328.
     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.
    Regulatory guides are not copyrighted, and NRC approval is not 
required to reproduce them.

FOR FURTHER INFORMATION CONTACT: Frank X. Talbot, Office of New 
Reactors; telephone: 301-415-4146, email: Frank.Talbot@nrc.gov, or Mark 
P. Orr, Office of Nuclear Regulatory Research; telephone: 301-251-7495, 
email: Mark.Orr@nrc.gov, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION:

I. Introduction

    The NRC is issuing a new guide in the NRC's ``Regulatory Guide'' 
series. This series was developed to describe and make available to the 
public information such as 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.
    This new guide describes methods that the staff of the NRC 
considers acceptable for demonstrating compliance with the NRC 
regulations as they relate to preoperational, low power, and power 
ascension testing features of the ECCS for new BWRs. This RG also 
describes methods that the NRC staff finds acceptable for initial plant 
testing of ECCS structures, systems, and components (SSCs). 
Additionally, this RG describes methods the NRC staff finds acceptable 
for testing of the Isolation Condenser System (ICS) and the Reactor 
Core Isolation Cooling (RCIC) System, which support functions for 
alternate water injection during station blackout.

[[Page 63517]]

II. Additional Information

    Regulatory Guide 1.79.1 was issued with a temporary identification 
as Draft Regulatory Guide (DG)-1277, ``Initial Test Program of 
Emergency Core Cooling Systems for Boiling-Water Reactors.'' DG-1277, 
was published in the Federal Register on June 15, 2012 (77 FR 36014), 
for a 60-day public comment period. The public comment period closed on 
August 15, 2012. Forty-five public comments were received during this 
period. The NRC staff's responses to the public comments on DG-1277 are 
available in ADAMS under Accession No. ML12300A330.

III. Congressional Review Act

    This regulatory guide is a rule as defined in the Congressional 
Review Act (5 U.S.C. 801-808). However, the Office of Management and 
Budget has not found it to be a major rule as defined in the 
Congressional Review Act.

IV. Backfitting Analysis

    Issuance of this revised RG does not constitute backfitting as 
defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise 
inconsistent with the issue finality provisions in 10 CFR part 52. As 
discussed in the ``Implementation'' section of this RG, the NRC has no 
current intention to impose this RG on holders of current operating 
licenses, early site permits or combined licenses. The NRC may apply 
this RG to applications for operating licenses, early site permits and 
combined licenses docketed by the NRC as of the date of issuance of the 
final RG, as well as to future applications for operating licenses, 
early site permits, and combined licenses submitted after the issuance 
of the RG. Such action does not constitute backfitting as defined in 10 
CFR 50.109(a)(1) and is not otherwise inconsistent with the applicable 
issue finality provision in 10 CFR part 52, inasmuch as such applicants 
or potential applicants are not within the scope of entities protected 
by the Backfit Rule or the relevant issue finality provisions in part 
52.

    Dated at Rockville, Maryland, this 4th day of October, 2013.

    For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guide Development Branch, Division of Engineering, 
Office of Nuclear Regulatory Research.
[FR Doc. 2013-24888 Filed 10-23-13; 8:45 am]
BILLING CODE 7590-01-P