Meeting of the Advisory Committee on Reactor Safeguards Subcommittee on Plant License Renewal, 45993-45994 [2018-19601]

Download as PDF Federal Register / Vol. 83, No. 176 / Tuesday, September 11, 2018 / Notices 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–2018–0197. • 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 ‘‘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. • 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. daltland on DSKBBV9HB2PROD with NOTICES B. Submitting Comments Please include Docket ID NRC–2018– 0197 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 as well as 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 they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment into ADAMS. II. Further Information The NRC seeks public comment on the proposed Standard Review Plan (SRP)-draft section revision of Section 13.6, ‘‘Physical Security.’’ The changes made in this revision to this section reflect the latest NRC guidance concerning physical security. Following NRC staff evaluation of public comments, the NRC intends to finalize SRP Section 13.6, ‘‘Physical Security,’’ Revision 4 in ADAMS and post it on the NRC’s public website at https://www.nrc.gov/reading-rm/doccollections/nuregs/staff/sr0800/. The SRP is guidance for the NRC staff. The VerDate Sep<11>2014 18:49 Sep 10, 2018 Jkt 244001 SRP is not a substitute for the NRC regulations, and compliance with the SRP is not required. III. Backfitting and Issue Finality Issuance of this draft SRP, if finalized, would not constitute backfitting as defined in section 50.109 of title 10 of the Code of Federal Regulations (10 CFR) (the Backfit Rule) or otherwise be inconsistent with the issue finality provisions in 10 CFR part 52. The NRC’s position is based upon the following considerations: 1. The draft SRP positions do not constitute backfitting, inasmuch as the SRP is guidance directed to the NRC staff with respect to its regulatory responsibilities. The SRP provides internal guidance to the NRC staff on how to review an application for NRC regulatory approval in the form of licensing. Changes in guidance intended for use by only the staff are not matters that constitute backfitting as that term is defined in 10 CFR 50.109(a)(1) or involve the issue finality provisions of 10 CFR part 52. 2. Backfitting and issue finality—with certain exceptions discussed below—do not apply to current or future applicants. Applicants and potential applicants are not, with certain exceptions, the subject of either the Backfit Rule or any issue finality provisions under 10 CFR part 52. This is because neither the Backfit Rule nor the issue finality provisions under 10 CFR part 52 were intended to apply to every NRC action that substantially changes the expectations of current and future applicants. The exceptions to the general principle are applicable whenever a 10 CFR part 50 operating license applicant references a construction permit or a 10 CFR part 52 combined license applicant references a license (e.g., an early site permit) and/or NRC regulatory approval (e.g., a design certification rule) for which specified issue finality provisions apply. The NRC staff does not, at this time, intend to impose the positions represented in this draft SRP section in a manner that constitutes backfitting or is inconsistent with any issue finality provision of 10 CFR part 52. If, in the future, the staff seeks to impose a position in this draft SRP section in a manner that would constitute backfitting or be inconsistent with these issue finality provisions, the NRC staff must make the showing as set forth in the Backfit rule or address the regulatory criteria set forth in the applicable issue finality provision, as PO 00000 Frm 00119 Fmt 4703 Sfmt 4703 45993 applicable, that would allow the staff to impose the position. 3. The NRC staff has no intention to impose the SRP positions on existing nuclear power plant licensees either now or in the future (absent a voluntary request for a change from the licensee, holder of a regulatory approval or a design certification applicant). The NRC staff does not intend to impose or apply the positions described in the draft SRP to existing (already issued) licenses (e.g., operating licenses and combined licenses) and regulatory approvals. Hence, the issuance of this SRP guidance—even if considered guidance subject to the Backfit Rule or the issue finality provisions in 10 CFR part 52—would not need to be evaluated as if it were a backfit or as being inconsistent with these issue finality provisions. If, in the future, the NRC staff seeks to impose a position in the SRP on holders of already issued licenses in a manner that would constitute backfitting or does not provide issue finality as described in the applicable issue finality provision, then the staff must make a showing as set forth in the Backfit Rule or address the criteria set forth in the applicable issue finality provision, as applicable, that would allow the staff to impose the position. Dated at Rockville, Maryland, this 6th day of September 2018. For the Nuclear Regulatory Commission. Jennivine K. Rankin, Acting Chief, Division of Licensing, Siting, and Environmental Analysis, Licensing Branch 3, Office of New Reactors. [FR Doc. 2018–19684 Filed 9–10–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Meeting of the Advisory Committee on Reactor Safeguards Subcommittee on Plant License Renewal The ACRS Subcommittee on Plant License Renewal will hold a meeting on September 20, 2018 at U.S. Nuclear Regulatory Commission, 11545 Rockville Pike, Room T–2B1, Rockville, Maryland 20852. The entire meeting will be open to public attendance. The agenda for the subject meeting shall be as follows: Thursday, September 20, 2018, 1 p.m. Until 5 p.m. The Subcommittee will conduct a briefing on the River Bend Nuclear Generating Station Unit 1 License Renewal Application. The Subcommittee will hear presentations E:\FR\FM\11SEN1.SGM 11SEN1 daltland on DSKBBV9HB2PROD with NOTICES 45994 Federal Register / Vol. 83, No. 176 / Tuesday, September 11, 2018 / Notices by and hold discussions with 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), Kent Howard (Telephone 301–415–2989 or Email: Kent.Howard@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 20852. After registering with Security, please contact Mr. Theron Brown (Telephone 301– 415–6702) to be escorted to the conference room. VerDate Sep<11>2014 18:49 Sep 10, 2018 Jkt 244001 Dated: September 5, 2018. Mark L. Banks, Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards. the NRC’s PDR, Room O1–F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. NUCLEAR REGULATORY COMMISSION Ted Carter, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone: 301–415–5543, email: Ted.Carter@nrc.gov. [Docket No. 50–312; NRC–2018–0180] SUPPLEMENTARY INFORMATION: [FR Doc. 2018–19601 Filed 9–10–18; 8:45 am] BILLING CODE 7590–01–P Sacramento Municipal Utility District; Rancho Seco Nuclear Generating Station Nuclear Regulatory Commission. ACTION: License termination; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is providing public notice of the termination of the Operating License (Possession Only) No. DPR–54. The NRC has terminated the license of the decommissioned Rancho Seco Nuclear Generating Station (Rancho Seco) in Herald, California and has approved the site for unrestricted release. DATES: Notice of termination of Operating License No. DPR–54 issued on August 31, 2018. ADDRESSES: Please refer to Docket ID NRC–2018–0180 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 https://www.regulations.gov and search for Docket ID NRC–2018–0180. 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. • 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 ‘‘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 that document is available in ADAMS) is provided the first time that a document is referenced. • NRC’s PDR: You may examine and purchase copies of public documents at SUMMARY: PO 00000 Frm 00120 Fmt 4703 Sfmt 4703 FOR FURTHER INFORMATION CONTACT: The NRC has terminated License No. DPR–54, held by Sacramento Municipal Utility District (SMUD), for Rancho Seco in Herald, California, and has approved the site for unrestricted release. Accordingly, the existing indemnity agreement between SMUD and the NRC has been terminated. Rancho Seco initially went critical on September 16, 1974, and began commercial operation on April 18, 1975. On June 7, 1989, SMUD permanently terminated nuclear power operations at Rancho Seco. On December 8, 1989, SMUD completed defueling the reactor. On March 17, 1992, the NRC amended the Rancho Seco operating license to ‘‘Possession Only’’ status (ADAMS Accession No. ML17283A071). On March 20, 1995, the NRC issued the Rancho Seco Decommissioning Order. The Order authorized SMUD to decommission the facility and accepted the Rancho Seco decommissioning funding plan. SMUD began actively decommissioning Rancho Seco in February 1997. In March 1997, SMUD revised the Rancho Seco Decommissioning Plan to conform to the content requirements of the Post Shutdown Decommissioning Activities Report. On June 30, 2000, the NRC issued Materials License SNM–2510 for the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI). This sitespecific license authorizes SMUD to store Rancho Seco spent fuel at the Rancho Seco ISFSI. The licensee completed transferring all of the spent fuel to the ISFSI on August 21, 2002. All of the spent fuel is now stored at the ISFSI. The ISFSI is a separately licensed facility located outside the operating licensed site. On October 10, 2002, NRC approved a license amendment that eliminated the security plan requirements from the operating licensed facility (ADAMS Accession No. ML022840145). Dated at Rockville, Maryland, this 5th day of August 2018. E:\FR\FM\11SEN1.SGM 11SEN1

Agencies

[Federal Register Volume 83, Number 176 (Tuesday, September 11, 2018)]
[Notices]
[Pages 45993-45994]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-19601]


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

NUCLEAR REGULATORY COMMISSION


Meeting of the Advisory Committee on Reactor Safeguards 
Subcommittee on Plant License Renewal

    The ACRS Subcommittee on Plant License Renewal will hold a meeting 
on September 20, 2018 at U.S. Nuclear Regulatory Commission, 11545 
Rockville Pike, Room T-2B1, Rockville, Maryland 20852.
    The entire meeting will be open to public attendance. The agenda 
for the subject meeting shall be as follows:

Thursday, September 20, 2018, 1 p.m. Until 5 p.m.

    The Subcommittee will conduct a briefing on the River Bend Nuclear 
Generating Station Unit 1 License Renewal Application. The Subcommittee 
will hear presentations

[[Page 45994]]

by and hold discussions with 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), 
Kent Howard (Telephone 301-415-2989 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 20852. After 
registering with Security, please contact Mr. Theron Brown (Telephone 
301-415-6702) to be escorted to the conference room.

    Dated: September 5, 2018.
Mark L. Banks,
Chief, Technical Support Branch, Advisory Committee on Reactor 
Safeguards.
[FR Doc. 2018-19601 Filed 9-10-18; 8:45 am]
 BILLING CODE 7590-01-P
This site is protected by reCAPTCHA and the Google Privacy Policy and Terms of Service apply.