Meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Structural Analysis, 49138-49139 [2018-21120]

Download as PDF 49138 Federal Register / Vol. 83, No. 189 / Friday, September 28, 2018 / Notices does not, at this time, intend to impose the positions represented in the draft SRP in a manner that is inconsistent with any issue finality provisions. If, in the future, the staff seeks to impose a position in the draft SRP in a manner VI. Availability of Documents The documents identified in the following table are available to interested persons through the following methods, as indicated. Document ADAMS Accession No. Draft NUREG–0800, Section 2.4.6, ‘‘Tsunami Hazards’’ .................................................................................................................... Current Revision of NUREG–0800, Section 2.4.6, ‘‘Tsunami Hazards’’ ............................................................................................ Draft revision to NUREG–0800, Section 2.4.9, ‘‘Channel Migration or Diversion’’ ............................................................................ Current revision to NUREG–0800, Section 2.4.9, ‘‘Channel Migration or Diversion’’ ........................................................................ The redline-strikeout version comparing the Revision 4 of Draft NUREG–0800, Section 2.4.6, ‘‘Tsunami Hazards’’ and the current version of Revision 3 ................................................................................................................................................................ The redline-strikeout version comparing the draft Revision 4 of Draft revision to NUREG–0800, Section 2.4.9, ‘‘Channel Migration or Diversion’’ and the current version of Revision 3 ................................................................................................................ Draft NUREG–0800, Section 2.3.3, ‘‘Onsite Meteorological Measurements Program’’ ..................................................................... Current Revision NUREG–0800, Section 2.3.3, ‘‘Onsite Meteorological Measurements Program’’ .................................................. The redline-strikeout version comparing the draft Revision 4 of Draft revision to NUREG–0800, Section 2.3.3, ‘‘Onsite Meteorological Measurements Program’’ and the current version of Revision 3 ......................................................................................... ML18190A200 ML070160659 ML18190A201 ML070730434 Dated at Rockville, Maryland, this 25th day of September, 2018. For the Nuclear Regulatory Commission. Jennivine K. Rankin, Acting Chief, Licensing Branch 3, Division of Licensing, Siting and Environmental Analysis, Office of New Reactors. APPENDIX: Proposed Definitions amozie on DSK3GDR082PROD with NOTICES1 which does not provide issue finality as described in the applicable issue finality provisions, then the staff must address the criteria for avoiding issue finality as described in the applicable issue finality provision. D Active flood protection feature: A flood protection feature that requires the change of a component’s state in order for it to perform as intended. Examples include sump pumps, portable pumps, isolation and check valves, flood detection devices (e.g., level switches), and flood doors (e.g., watertight doors). D Associated effects: Defined to include those factors such as wind waves and run-up effects; hydrostatic loading; hydrodynamic loading, including debris and water velocities; effects caused by sediment deposition and erosion; concurrent site conditions, including adverse weather conditions; and groundwater ingress. D Cliff-edge effect: A relatively-large increase in the safety consequences due to a relatively small increase in flood severity (e.g., flood height (elevation), associated effects, or flood event duration). D Concurrent hazard: A hazard that occurs along with the occurrence of another hazard as a result of a common cause (e.g., local intense precipitation and/or riverine flood event concurrent with a storm surge event caused by the same hurricane). D Consequential flooding: For Construction Permits, Operating Licenses, and COL applications, a term used to identify conditions in which the flood severity exceeds the capability of protection features (if available), including considerations for flood level, duration and/or associated effects, such that SSCs important-to-safety may be impacted. For ESP applications, the flood severity is expected to be in reference to the site characteristic flood. Consequential flooding may occur for events that are less severe and with differing characteristics (e.g., shorter warning time) than the VerDate Sep<11>2014 19:22 Sep 27, 2018 Jkt 244001 deterministically defined probable maximum events. D Flood event duration: Defines the length of time that a flood event affects the site. Flood event duration typically begins with conditions being met for entry into a flood procedure or notification of an impending flood and end when the plant is in a safe and stable state. It typically includes site warning time (or preparation time, if available) and period of inundation and recession. D Flood hazard: Those hydrometeorologic, geoseismic, or structural failure phenomena (or combination thereof) that may produce flooding at or near nuclear power plant site. D Flood-response SSCs: SSCs that may be used to maintain key safety functions during conditions that might occur during an external flood scenario, including SSCs that are indirectly related to maintenance of key safety functions (e.g., barriers that protect SSCs from floodwaters or other related effects). D Local intense precipitation (LIP): A locally-heavy rainfall event, which is typically defined by specifying three parameters: Total rainfall depth, total rainfall duration, and spatial extent (area). LIP is typically associated with small-scale events over geographic areas on the scale of the reactor powerblock and the controlled area (typically on the order of one to ten mi2) and using an assumption that the short-term rainfall rate is aerially uniform although the rainfall rate (intensity) typically varies over the total rainfall event duration. Although the rainfall duration parameter selected as part of evaluating this flood-causing mechanism will depend on site-specific characteristics (e.g., site drainage, susceptibility to ponding of water, etc.), LIP events are typically associated with a relatively short duration (e.g., 1- to 6-hrs) of intense rainfall compared to the duration of rainfall events applied to the evaluation of basin-wide flooding involving streams and rivers. Smaller-scale intense rainfall events may be imbedded within longer rainfall events for streams and rivers and, depending on site drainage characteristics, may affect a reactor site for longer durations. In the context of the PO 00000 Frm 00091 Fmt 4703 Sfmt 4703 ML18267A055 ML18264A035 ML18183A446 ML063600394 ML18267A076 Standard Review Plan, LIP is defined generically and is not limited to stylized deterministic events, such as the so-called 1hr, 1- mi2, probable maximum precipitation (PMP) event with specified duration and temporal distribution that produces the maximum rainfall inundation at a given plant site. D Passive flood protection feature: A flood protection feature that does not require the change of state of a component in order for it to perform as intended. Examples include dikes, berms, sumps, drains, basins, yard drainage systems, walls, floors, structures, penetration seals, and barriers exterior to the immediate plant area that is under licensee control. D Powerblock elevation (for purposes of plant design and flood hazard assessment): The as-built elevation of the ground surface in the area of the site’s powerblock. [FR Doc. 2018–21140 Filed 9–27–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Structural Analysis The ACRS Subcommittee on Structural Analysis will hold a meeting on October 3, 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, October 3, 2018—1:00 p.m. Until 4:00 p.m. The Subcommittee will review the Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research report NUREG/CR–7237, ‘‘Correlation of Seismic Performance in Similar SSCs (Structures, Systems, and E:\FR\FM\28SEN1.SGM 28SEN1 amozie on DSK3GDR082PROD with NOTICES1 Federal Register / Vol. 83, No. 189 / Friday, September 28, 2018 / Notices Components).’’ 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. This briefing is independent of the ACRS Research Quality Review. Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official (DFO), Girija Shukla (Telephone 301–415–5844 or Email: Girija.Shukla@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. The public bridgeline number for the meeting is 866–822–3032, passcode 8272423. Detailed procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on October 4, 2017 (82 FR 46312). Detailed meeting agendas and meeting transcripts are available on the NRC website at https://www.nrc.gov/readingrm/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. VerDate Sep<11>2014 19:22 Sep 27, 2018 Jkt 244001 Dated: September 21, 2018. Mark L. Banks, Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards. [FR Doc. 2018–21120 Filed 9–27–18; 8:45 am] BILLING CODE 7590–01–P 49139 FOR FURTHER INFORMATION CONTACT: Mark D. Notich, Office of New Reactors, telephone: 301–415–3053; email: Mark.Notich@nrc.gov; U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments NUCLEAR REGULATORY COMMISSION A. Obtaining Information [NRC–2018–0178] Proposed Revisions to Standard Review Plan Section 2.5.3, Surface Deformation Nuclear Regulatory Commission. ACTION: Standard review plan-draft section revision; request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on draft NUREG–0800, ‘‘Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,’’ Section 2.5.3, ‘‘Surface Deformation.’’ SRP Section 2.5.3, Surface Deformation, was last updated in 2014. This proposed update to the SRP focuses on riskinforming the staff’s review in this area on the potential for tectonic or nontectonic surface deformation that could adversely affect the safe operation of a nuclear power plant at the proposed site. SUMMARY: Comments must be filed no later than October 29, 2018. Comments received after this date will be considered, if it is practical to do so, but the Commission is able to ensure consideration only for comments received on or before this date. ADDRESSES: You may submit comments by any of the following methods: • Federal Rulemaking website: Go to https://www.regulations.gov and search for Docket ID NRC–2018–0178. Address questions about NRC dockets to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • Mail comments to: May Ma, Office of Administration, Mail Stop: TWFN–7– A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. For additional direction on obtaining information and submitting comments, see ‘‘Obtaining Information and Submitting Comments’’ in the SUPPLEMENTARY INFORMATION section of this document. DATES: PO 00000 Frm 00092 Fmt 4703 Sfmt 4703 Please refer to Docket ID NRC–2018– 0178 when contacting the NRC about the availability of information for this action. You may obtain publiclyavailable information related to this action by any of the following methods: • Federal Rulemaking website: Go to https://www.regulations.gov and search for Docket ID NRC–2018–0178. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at https://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 draft revision and current revision to NUREG–0800, Section 2.5.3, ‘‘Surface Deformation’’ are available in ADAMS under Accession Nos. ML18183A044 and ML13316C064, respectively. The redline-strikeout version comparing the draft Revision 6 and the current version of Revision 5 is available in ADAMS under Accession No. ML18267A203. • 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. B. Submitting Comments Please include Docket ID NRC–2018– 0178 in your comment submission. The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at https:// www.regulations.gov and enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that E:\FR\FM\28SEN1.SGM 28SEN1

Agencies

NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 83, Number 189 (Friday, September 28, 2018)]
[Notices]
[Pages 49138-49139]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-21120]


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NUCLEAR REGULATORY COMMISSION


Meeting of the Advisory Committee on Reactor Safeguards (ACRS) 
Subcommittee on Structural Analysis

    The ACRS Subcommittee on Structural Analysis will hold a meeting on 
October 3, 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, October 3, 2018--1:00 p.m. Until 4:00 p.m.

    The Subcommittee will review the Nuclear Regulatory Commission 
(NRC) Office of Nuclear Regulatory Research report NUREG/CR-7237, 
``Correlation of Seismic Performance in Similar SSCs (Structures, 
Systems, and

[[Page 49139]]

Components).'' 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. This briefing is independent of the ACRS Research Quality 
Review.
    Members of the public desiring to provide oral statements and/or 
written comments should notify the Designated Federal Official (DFO), 
Girija Shukla (Telephone 301-415-5844 or Email: [email protected]) 
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. The public 
bridgeline number for the meeting is 866-822-3032, passcode 8272423. 
Detailed procedures for the conduct of and participation in ACRS 
meetings were published in the Federal Register on October 4, 2017 (82 
FR 46312).
    Detailed meeting agendas and meeting transcripts are available on 
the NRC website at https://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.

    Dated: September 21, 2018.
Mark L. Banks,
Chief, Technical Support Branch, Advisory Committee on Reactor 
Safeguards.
[FR Doc. 2018-21120 Filed 9-27-18; 8:45 am]
 BILLING CODE 7590-01-P

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