83_FR_26217 83 FR 26109 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Nuscale; Notice of Meeting

83 FR 26109 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Nuscale; Notice of Meeting

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 83, Issue 108 (June 5, 2018)

Page Range26109-26110
FR Document2018-12024

Federal Register, Volume 83 Issue 108 (Tuesday, June 5, 2018) 
[Federal Register Volume 83, Number 108 (Tuesday, June 5, 2018)]
[Notices]
[Pages 26109-26110]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2018-12024]


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NUCLEAR REGULATORY COMMISSION


Advisory Committee on Reactor Safeguards (ACRS) Meeting of the 
ACRS Subcommittee on Nuscale; Notice of Meeting

    The ACRS Subcommittee on NuScale will hold a meeting on June 6, 
2018, at 11545 Rockville Pike, Room T-2B1, Rockville, Maryland 20852.
    The meeting will be open to public attendance. The agenda for the 
subject meeting shall be as follows:

Wednesday, June 6, 2018, 8:30 a.m. Until 12:00 p.m.

    The Subcommittee will review the staff's SER with open items for 
Chapter 8, ``Electrical Systems,'' of the NuScale design certification 
application. The Subcommittee will hear presentations by and hold 
discussions with the NRC staff and other interested persons regarding 
this matter. The Subcommittee will gather information, analyze relevant 
issues and facts, and formulate proposed positions and actions, as 
appropriate, for deliberation by the Full Committee.
    Members of the public desiring to provide oral statements and/or 
written comments should notify the Designated Federal Official (DFO), 
Michael Snodderly (Telephone 301-415-2241 or Email: 
Michael.Snodderly@nrc.gov) five days prior to the meeting, if possible, 
so that appropriate arrangements can be made. Thirty-five hard copies 
of each presentation or handout should be provided to the DFO thirty 
minutes before the meeting. In addition, one electronic copy of each 
presentation should be emailed to the DFO one day before the meeting. 
If an electronic copy cannot be provided within this timeframe, 
presenters should provide the DFO with a CD containing each 
presentation at least thirty minutes before the meeting. Electronic 
recordings will be permitted only during those portions of the meeting 
that are open to the public. Detailed procedures for the conduct of and 
participation in ACRS meetings were published in the Federal Register 
on October 4, 2017 (82 FR 46312). The bridgeline number for this 
meeting is 866-822-3032, passcode 8272423#.
    Detailed meeting agendas and meeting transcripts are available on 
the NRC website at http://www.nrc.gov/reading-rm/doc-collections/acrs. 
Information regarding topics to be discussed, changes to the agenda, 
whether the meeting has been canceled or rescheduled, and the time 
allotted to present oral statements can be obtained from the website 
cited above or by contacting the identified DFO. Moreover, in view of 
the possibility that the schedule for ACRS meetings may be adjusted by 
the Chairman as necessary to facilitate the conduct of the meeting, 
persons planning to attend should check with these references if such 
rescheduling would result in a major inconvenience.
    If attending this meeting, please enter through the One White Flint 
North building, 11555 Rockville Pike, Rockville, Maryland. After 
registering with Security, please contact Mr. Theron Brown (Telephone 
301-415-6702 or 301-415-8066) to be escorted to the meeting room.


[[Page 26110]]


    Dated: May 23, 2018.
Mark L. Banks,
Chief, Technical Support Branch, Advisory Committee on Reactor 
Safeguards.
[FR Doc. 2018-12024 Filed 6-4-18; 8:45 am]
 BILLING CODE P

Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices 26109 No significant hazards consideration presentation at least thirty minutes design certification application. The comments received: No. before the meeting. Electronic Subcommittee will hear presentations Dated at Rockville, Maryland, this 29th day recordings will be permitted only by and hold discussions with the NRC of May, 2018. during those portions of the meeting staff and other interested persons For the Nuclear Regulatory Commission. that are open to the public. Detailed regarding this matter. The Gregory F. Suber, procedures for the conduct of and Subcommittee will gather information, participation in ACRS meetings were analyze relevant issues and facts, and Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor published in the Federal Register on formulate proposed positions and Regulation. October 4, 2017 (82 FR 46312). The actions, as appropriate, for deliberation [FR Doc. 2018–11843 Filed 6–4–18; 8:45 am] bridgeline number for this meeting is by the Full Committee. 866–822–3032, passcode 8272423#. BILLING CODE 7590–01–P Members of the public desiring to Detailed meeting agendas and meeting provide oral statements and/or written transcripts are available on the NRC comments should notify the Designated NUCLEAR REGULATORY website at http://www.nrc.gov/reading- Federal Official (DFO), Michael COMMISSION rm/doc-collections/acrs. Information Snodderly (Telephone 301–415–2241 or regarding topics to be discussed, Email: Michael.Snodderly@nrc.gov) five Meeting of the Advisory Committee on changes to the agenda, whether the days prior to the meeting, if possible, so Reactor Safeguards (ACRS) meeting has been canceled or that appropriate arrangements can be Subcommittee on APR1400 rescheduled, and the time allotted to made. Thirty-five hard copies of each present oral statements can be obtained The ACRS Subcommittee on APR1400 presentation or handout should be from the website cited above or by will hold a meeting on June 5, 2018, at provided to the DFO thirty minutes contacting the identified DFO. 11545 Rockville Pike, Room T–2B1, before the meeting. In addition, one Moreover, in view of the possibility that Rockville, Maryland 20852. electronic copy of each presentation the schedule for ACRS meetings may be The meeting will be open to public should be emailed to the DFO one day adjusted by the Chairman as necessary attendance with the exception of before the meeting. If an electronic copy to facilitate the conduct of the meeting, portions that may be closed to protect persons planning to attend should check cannot be provided within this information that is proprietary pursuant with these references if such timeframe, presenters should provide to 5 U.S.C. 552b(c)(4). The agenda for rescheduling would result in a major the DFO with a CD containing each the subject meeting shall be as follows: inconvenience. presentation at least thirty minutes before the meeting. Electronic Tuesday, June 5, 2018, 8:30 a.m. Until If attending this meeting, please enter recordings will be permitted only 5:00 p.m. through the One White Flint North during those portions of the meeting The Subcommittee will review the Building, 11555 Rockville Pike, Rockville, Maryland 20852. After that are open to the public. Detailed APR1400 Design Control Document and procedures for the conduct of and Safety Evaluation Report with No Open registering with Security, please contact Ms. Kendra Freeland (Telephone 301– participation in ACRS meetings were Items, Chapter 17 (Quality Assurance & published in the Federal Register on Reliability Assurance), Chapter 19.1 415–6207) to be escorted to the meeting room. October 4, 2017 (82 FR 46312). The (Probabilistic Risk Assessment), and bridgeline number for this meeting is Chapter 19.2 (Severe Accident Dated: May 23, 2018. 866–822–3032, passcode 8272423#. Evaluation). Mark L. Banks, The Subcommittee will hear Detailed meeting agendas and meeting Chief, Technical Support Branch, Advisory presentations by and hold discussions Committee on Reactor Safeguards. transcripts are available on the NRC with the NRC staff and Korea Hydro & website at http://www.nrc.gov/reading- [FR Doc. 2018–12022 Filed 6–4–18; 8:45 am] Nuclear Power Company regarding this rm/doc-collections/acrs. Information BILLING CODE 7590–01–P matter. The Subcommittee will gather regarding topics to be discussed, information, analyze relevant issues and changes to the agenda, whether the facts, and formulate proposed positions meeting has been canceled or NUCLEAR REGULATORY rescheduled, and the time allotted to and actions, as appropriate, for COMMISSION present oral statements can be obtained deliberation by the Full Committee. Members of the public desiring to from the website cited above or by Advisory Committee on Reactor contacting the identified DFO. provide oral statements and/or written Safeguards (ACRS) Meeting of the comments should notify the Designated Moreover, in view of the possibility that ACRS Subcommittee on Nuscale; the schedule for ACRS meetings may be Federal Official (DFO), Christopher Notice of Meeting Brown (Telephone 301–415–7111 or adjusted by the Chairman as necessary Email: Christopher.Brown@nrc.gov) five The ACRS Subcommittee on NuScale to facilitate the conduct of the meeting, days prior to the meeting, if possible, so will hold a meeting on June 6, 2018, at persons planning to attend should check that appropriate arrangements can be 11545 Rockville Pike, Room T–2B1, with these references if such made. Thirty-five hard copies of each Rockville, Maryland 20852. rescheduling would result in a major presentation or handout should be The meeting will be open to public inconvenience. provided to the DFO thirty minutes attendance. The agenda for the subject If attending this meeting, please enter amozie on DSK3GDR082PROD with NOTICES1 before the meeting. In addition, one meeting shall be as follows: through the One White Flint North electronic copy of each presentation building, 11555 Rockville Pike, Wednesday, June 6, 2018, 8:30 a.m. should be emailed to the DFO one day Rockville, Maryland. After registering Until 12:00 p.m. before the meeting. If an electronic copy with Security, please contact Mr. cannot be provided within this The Subcommittee will review the Theron Brown (Telephone 301–415– timeframe, presenters should provide staff’s SER with open items for Chapter 6702 or 301–415–8066) to be escorted to the DFO with a CD containing each 8, ‘‘Electrical Systems,’’ of the NuScale the meeting room. VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 PO 00000 Frm 00115 Fmt 4703 Sfmt 4703 E:\FR\FM\05JNN1.SGM 05JNN1

26110 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices Dated: May 23, 2018. select ‘‘Begin Web-based ADAMS period. The public comment period Mark L. Banks, Search.’’ For problems with ADAMS, closed on January 24, 2015. Public Chief, Technical Support Branch, Advisory please contact the NRC’s Public comments on DG–1309 and the NRC Committee on Reactor Safeguards. Document Room (PDR) reference staff at staff’s responses to the public comments [FR Doc. 2018–12024 Filed 6–4–18; 8:45 am] 1–800–397–4209, 301–415–4737, or by are available in ADAMS under BILLING CODE P email to pdr.resource@nrc.gov. RG Accession No. ML16315A127. 1.207, ‘‘Guidelines for Evaluating the III. Congressional Review Act Effects of Light-Water Reactor Water NUCLEAR REGULATORY Environments in Fatigue Analyses of This RG is a rule as defined in the COMMISSION Metal Components,’’ is available in Congressional Review Act (5 U.S.C. ADAMS under Accession No. 801–808). However, the Office of [NRC–2014–0244] Management and Budget has not found ML16315A130. • NRC’s PDR: You may examine and it to be a major rule as defined in the Guidelines for Evaluating the Effects of Congressional Review Act. Light-Water Reactor Water purchase copies of public documents at Environments in Fatigue Analyses of the NRC’s PDR, Room O1–F21, One IV. Backfitting and Issue Finality Metal Components White Flint North, 11555 Rockville This RG describes methods and Pike, Rockville, Maryland 20852. AGENCY: Nuclear Regulatory procedures that the NRC staff considers RGs are not copyrighted, and NRC Commission. acceptable for use in applications for approval is not required to reproduce license renewal and subsequent license ACTION: Regulatory guide; issuance. them. renewal in determining the acceptable FOR FURTHER INFORMATION CONTACT: fatigue lives of components evaluated SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 Robert Tregoning, Office of Nuclear by a cumulative usage factor calculation to Regulatory Guide (RG) 1.207, Regulatory Research, telephone: 301– in accordance with the fatigue design ‘‘Guidelines for Evaluating the Effects of 415–2324, email: Robert.Tregoning@ provisions in Section III, ‘‘Rules for Light-Water Reactor Water nrc.gov and Stephen Burton, Office of Construction of Nuclear Power Plant Environments in Fatigue Analyses of Nuclear Regulatory Research, telephone: Components,’’ of the ASME Code. This Metal Components.’’ This RG describes 301–415–7000, Stephen.Burton@ RG also supports reviews of methods and procedures that the staff of nrc.gov. Both are staff of the U.S. applications for new nuclear reactor the NRC considers acceptable for use in Nuclear Regulatory Commission, construction permits or operating determining the acceptable fatigue lives Washington, DC 20555–0001. licenses under part 50 of title 10 of the of components evaluated by a SUPPLEMENTARY INFORMATION: Code of Federal Regulations (10 CFR), cumulative usage factor calculation in design certifications under 10 CFR part I. Discussion 52, and combined licenses under 10 accordance with the fatigue design provisions in Section III, ‘‘Rules for The NRC is issuing a revision to an CFR part 52, which do not cite a Construction of Nuclear Power Plant existing guide in the NRC’s ‘‘Regulatory standard design, in addition to renewed Components,’’ of the American Society Guide’’ series. This series was operating licenses under 10 CFR part 54. of Mechanical Engineers Boiler and developed to describe and make This RG may also be used by existing Pressure Vessel Code to account for the available to the public information holders of combined licenses and effects of light-water reactor water regarding methods that are acceptable to operating licenses in accordance with environments. the NRC staff for implementing specific their existing licensing basis and parts of the agency’s regulations, applicable regulatory requirements. DATES: Revision 1 to RG 1.207 is techniques that the NRC staff uses in This RG does not constitute available on June 5, 2018. evaluating specific issues or postulated backfitting as defined in 10 CFR 50.109 ADDRESSES: Please refer to Docket ID events, and data that the NRC staff (the Backfit Rule) and is not otherwise NRC–2014–0244 when contacting the needs in its review of applications for inconsistent with the issue finality NRC about the availability of permits and licenses. provisions in 10 CFR part 52. information regarding this document. Revision 1 of RG 1.207 was issued Applicants and potential applicants are You may obtain publicly-available with a temporary identification of Draft not, with certain exceptions, protected information related to this document Regulatory Guide, DG–1309. This RG by either the Backfit Rule or any issue using any of the following methods: describes methods and procedures that finality provisions under 10 CFR part • Federal Rulemaking Website: Go to the NRC staff considers acceptable for 52. Neither the Backfit Rule nor the http://www.regulations.gov and search use in determining the acceptable issue finality provisions under 10 CFR for Docket ID NRC–2014–0244. Address fatigue lives of components evaluated part 52, with certain exclusions questions about NRC dockets to Jennifer by a cumulative usage factor calculation discussed below, were intended to Borges; telephone: 301–287–9127; in accordance with the fatigue design apply to every NRC action that email: Jennifer.Borges@nrc.gov. For provisions in Section III, ‘‘Rules for substantially changes the expectations technical questions, contact the Construction of Nuclear Power Plant of current and future applicants. individuals listed in the FOR FURTHER Components,’’ of the American Society The exceptions to the general INFORMATION CONTACT section of this of Mechanical Engineers’ Boiler and principle are applicable whenever a document. Pressure Vessel Code to account for the combined license applicant references a • NRC’s Agencywide Documents effects of light-water reactor water part 52 license (i.e., an early site permit amozie on DSK3GDR082PROD with NOTICES1 Access and Management System environments. or a manufacturing license) and/or part (ADAMS): You may obtain publicly 52 regulatory approval (i.e., a design available documents online in the II. Additional Information certification rule or design approval). ADAMS Public Documents collection at The NRC published a notice of the The NRC staff does not, at this time, http://www.nrc.gov/reading-rm/ availability of DG–1309 in the Federal intend to impose the positions adams.html. To begin the search, select Register on November 24, 2014 (79 FR represented in the RG in a manner that ‘‘ADAMS Public Documents’’ and then 69884), for a 60-day public comment is inconsistent with any issue finality VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 PO 00000 Frm 00116 Fmt 4703 Sfmt 4703 E:\FR\FM\05JNN1.SGM 05JNN1


Document Created: 2018-11-02 11:47:24
Document Modified: 2018-11-02 11:47:24
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionNotices
FR Citation83 FR 26109 
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