83 FR 6244 - Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Independent Spent Fuel Storage Installation
NUCLEAR REGULATORY COMMISSION Federal Register Volume 83, Issue 30 (February 13, 2018)
Federal Register Volume 83, Issue 30 (February 13, 2018)
| Page Range | 6244-6247 | |
| FR Document | 2018-02930 |
[Federal Register Volume 83, Number 30 (Tuesday, February 13, 2018)] [Notices] [Pages 6244-6247] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2018-02930] ----------------------------------------------------------------------- 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 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: 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: [email protected]. 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 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 No. for each [[Page 6245]] document referenced in this document (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 the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Yen-Ju Chen, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555; telephone: 301-415-1018; email: [email protected]. SUPPLEMENTARY INFORMATION: I. Background The VYNPS began operation in 1972. The reactor was permanently shut down on December 29, 2014. The VYNPS has stored spent boiling-water reactor (BWR) fuel assemblies at its ISFSI in thirteen (13) HI-STORM 100 casks under CoC No. 1014, Amendment No. 2. The remaining spent fuel assemblies were removed from the reactor and transferred to the spent fuel pool. ENO, which owns the facility, submitted the VYNPS Post- Shutdown Decommissioning Activities Report (PSDAR) (ADAMS Accession No. ML14357A110) to the NRC on December 19, 2014, and supplemented with a schedule change in a letter dated on April 12, 2017 (ADAMS Accession No. ML17104A050). In the PSDAR, as supplemented, ENO stated its intention to move all of the spent nuclear fuel assemblies into dry cask storage in late 2018, and put the plant into SAFSTOR \1\ until it is ready to fully decommission the facility. --------------------------------------------------------------------------- \1\ A method of decommissioning in which a nuclear facility is placed and maintained in a condition that allows the facility to be safely stored and subsequently decontaminated (deferred decontamination) to levels that permit release for unrestricted use. --------------------------------------------------------------------------- Consistent with subpart K of part 72 of title 10 of the Code of Federal Regulations (10 CFR), a general license is issued for the storage of spent fuel in an ISFSI at power reactor sites to persons authorized to possess or operate nuclear power reactors under 10 CFR part 50. ENO is currently authorized to store spent fuel at the VYNPS ISFSI under the 10 CFR part 72 general license provisions. ENO plans to use Holtec HI-STORM 100 storage casks, as approved by the NRC under CoC No. 1014, Amendment No. 10, at the VYNPS for dry storage of spent nuclear fuel in MPC-68M canisters. II. Request/Action By application dated May 16, 2017 (ADAMS Accession No. ML17142A354), as supplemented on September 7, 2017 (ADAMS Accession No. ML17255A236) and December 7, 2017 (ADAMS Accession No. ML17346A685), ENO submitted a request for an exemption from those provisions of 10 CFR 72.212(a)(2), 72.212(b)(3), 72.212(b)(5)(i), 72.212(b)(11), and 72.214 that require compliance with the terms, conditions, and specifications of CoC No. 1014, Amendment No. 10 (ADAMS Accession No. ML16172A294), for 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 MWD/MTU in Holtec HI-STORM 100 MPC-68M canister. III. Discussion Pursuant to 10 CFR 72.7, the Commission may, upon application by any interested person or upon its own initiative, grant such exemptions from the requirements of the regulations of 10 CFR part 72 as it determines are authorized by law and will not endanger life or property or the common defense and security, and are otherwise in the public interest. The NRC staff prepared a safety evaluation report (SER) (ADAMS Accession No. ML17298A135) to document the evaluation of the proposed actions (i.e., using a new regionalized loading pattern, loading fuel cooled for at least 2 years, and establishing a per-cell maximum average burnup limit at 65,000 MWD/MTU in MPC-68M), to assure continued protection of public health and safety, common defense and security, and the environment. As summarized below, the NRC's safety review concludes that the requested exemption does not affect the ability of the cask system to meet the requirements of 10 CFR part 72. A. The Exemption Is Authorized by Law 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 MWD/MTU in MPC-68M using CoC No. 1014, Amendment No. 10. Section 72.7 allows the Commission to grant exemptions from the requirements of 10 CFR part 72 if the exemption is authorized by law and will not endanger life or property nor the common defense and security. Issuance of this exemption is consistent with the Atomic Energy Act of 1954, as amended, and not otherwise inconsistent with NRC's regulations or other applicable laws. Therefore, issuance of the exemption is authorized by law. B. The Exemption Presents No Undue Risk to Public Health and Safety and Will Not Endanger Life or Property or the Common Defense and Security Approval of this exemption request will allow 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 MWD/MTU in MPC-68M using CoC No. 1014, Amendment No. 10. As discussed in the SER and summarized in the following sections, the NRC staff has found that ENO's proposed action is acceptable and will not endanger life or property or the common defense and security. Review of the Requested Exemption ENO requested this exemption to maintain its decommissioning schedule through its optimized loading campaigns. The exemption will allow VYNPS to use a more optimized regionalized loading pattern for MPC-68M, so that VYNPS could store hotter fuel from its final operating cycle, as well as store damaged fuel or fuel debris in a DFC, with cooler fuel in the same cask. The exemption will also allow VYNPS to load fuel that has been cooled for at least 2 years into the MPC-68M. In addition, the exemption will allow VYNPS to establish a per-cell maximum average burnup limit at 65,000 MWD/MTU in MPC-68M rather than using an equation to calculate the maximum burnup. The NRC staff reviewed the requested exemption and determined that it does not change the fundamental design, components, or safety features of the storage system. The NRC staff evaluated the applicable potential safety impacts of granting the exemption to assess the potential for any danger to life or property or the common defense and security. Specifically, the NRC staff reviewed the applicant's structural, thermal, shielding, radiation protection, and material evaluations for the proposed exemption. Structural Review for the Requested Exemption: The NRC staff evaluated the exemption request to ensure that the cask system will maintain confinement, subcriticality, radiation shielding, and retrievability or recovery of the fuel, as applicable, under all credible loads for normal and off-normal conditions accidents, and natural phenomenon events. Since the maximum projected MPC-68M heat load for fuels to be loaded at VYNPS will be 24.5 kW, well below the maximum heat load limit of 36.9 kW for MPC-68M approved in CoC No. 1014, Amendment No. 10, the proposed exemption is bounded by [[Page 6246]] NRC's previous evaluation and would not alter the structural integrity of the dry storage system. Thermal Review for the Requested Exemption: The NRC staff evaluated the exemption request to ensure that the cask and fuel material temperatures of the dry storage system will remain within the allowable values or criteria for normal, off-normal, and accident conditions. The staff verified that the calculated fuel cladding temperatures and other cask component temperatures are below the allowable design temperature limits for normal, off-normal, and accident conditions of storage at VYNPS ISFSI. The staff also confirmed that the heat removal capability of the MPC-68M, using the new regionalized loading pattern and actual total aggregated cask heat load of 36.9 kW, loaded with all undamaged fuel assemblies or loaded with damaged fuel and/or fuel debris at VYNPS ISFSI remains acceptable and continues to meet the requirements of 10 CFR 72.122(h)(1) and 72.236(f). Shielding Review for the Requested Exemption: The NRC staff evaluated the exemption request to ensure that the design of the HI- STORM 100 cask system continues to provide adequate protection against direct radiation to the onsite operating workers and members of the public, and that the ISFSI continues to satisfy the regulatory requirements during normal operating, off-normal, and design-basis accident conditions. The staff determined the new regionalized loading pattern is bounded by the design basis loading pattern previously approved by the NRC and will allow the MPC-68M to maintain the dose rates below the applicable regulatory limits in 10 CFR 72.104 and 72.106. In addition, the staff found that the use of the maximum average burnup limit of 65,000 MWD/MTU is acceptable as it provides sufficient conservatism in comparison with the actual site-specific maximum. Radiation Protection Review for the Requested Exemption: The NRC staff evaluated the exemption request to determine whether the design features and operations meet the regulatory requirements. The staff evaluated the source terms and the calculated dose rates for normal, off-normal, and accident conditions, and found that the dose rates and annual dose are in compliance with the dose limits specified in 10 CFR 72.104 and 72.106. Material Review for the Requested Exemption: The NRC staff evaluated the exemption request to ensure adequate material performance of components important to safety of the spent fuel storage system under normal, off-normal, and accident conditions. The staff found that the material properties of structures, systems, and components important to safety will be maintained during normal, off-normal, and accident conditions so that the spent nuclear fuel can be safely stored for the minimum required years and maintenance can be conducted as required. Review of Common Defense and Security: The NRC staff also considered potential impacts of granting the exemption on the common defense and security. The requested exemption for the VYNPS ISFSI does not relate to security or the common defense, and therefore, granting the exemption would not result in any potential impacts to common defense and security. Based on its review, the NRC staff has determined that under the requested exemption, the storage system will continue to meet the safety requirements of 10 CFR part 72 and the offsite dose limits of 10 CFR part 20 and, therefore, will not endanger life or property. The NRC staff also found that the exemption would not endanger common defense and security. D. Otherwise in the Public Interest In determining whether the exemption is in the public interest, the staff considered the no-action alternative of denying the exemption request. Denial of the exemption request would require ENO to load and store spent fuel in accordance with the current conditions of Amendment No. 10 of CoC No. 1014, which uses the regionalized loading pattern shown in CoC Appendix B, Figure 2.1-4; requires fuel to be cooled for at least 3 years; and use the equation in Appendix B, Section 2.4.3, to calculate maximum allowable fuel assembly average burnup based on fuel decay heat, enrichment, and cooling time. ENO's proposed exemption would allow VYNPS to use a new regionalized loading pattern, load fuel that has been cooled for at least 2 years in MPC-68M, and use a per-cell maximum average burnup limit at 65,000 MWD/MTU. With this exemption, VYNPS stated that it would be able to use a more optimized loading pattern for MPC-68M, so that VYNPS could store hotter fuel from its final operating cycle, as well as for storing damaged fuel or fuel debris in a DFC, with cooler fuel in the same cask. ENO also noted that by loading higher-burned, shorter-cooled assemblies into the inner regions of the cask and low-burned, longer- cooled assemblies on the periphery of the cask, the longer-cooled assemblies on the periphery of the cask acts as shielding and blocks the radiation from the shorter-cooled fuel assemblies stored in the inner region of the cask, and thus reduces dose rates to the onsite workers and at the site boundary. This exemption request will also allow VYNPS to maintain continuous loading campaign without interruption to wait for the fuel to meet the heat loading requirement. ENO noted that this could avoid potential higher personal exposure and human errors due to loss of experienced workers. ENO indicated that by using this exemption, VYNPS would be able to complete the transfer of irradiated fuel to the ISFSI within a shorter time period. It would permit the spent fuel pool related structures, systems, and components to be removed from service earlier, and allow for staffing reductions to a level commensurate with dry fuel storage only operations. The staff determined if the transfer of irradiated fuel to the ISFSI is completed in a shorter time, that there would be a savings to the Decommissioning Trust Fund. The staff also determined, based on Entergy Nuclear Vermont Yankee, LLC. Master Decommissioning Trust Agreement for Vermont Yankee Nuclear Power Station, Exhibit D (ADAMS Accession No. ML15111A086), that savings to the Decommission Trust Fund could financially benefit the electric consumers. The staff has reviewed the information provided by ENO and concluded that granting the requested exemption continues to provide adequate protection of public health and safety and is otherwise in the public interest. E. Environmental Considerations The NRC staff also considered whether there would be any significant environmental impacts associated with the exemption. For this proposed action, the NRC staff performed an environmental assessment pursuant to 10 CFR 51.30. The environmental assessment concluded that the proposed action would not significantly impact the quality of the human environment. The NRC staff concluded that the proposed action would not result in any changes in the types or amounts of any radiological or non-radiological effluents that may be released offsite, and there is no significant increase in occupational or public radiation exposure because of the proposed action. The Environmental Assessment and the Finding of No Significant Impact was published on January 23, 2018 (83 FR 3192). [[Page 6247]] IV. Conclusion Accordingly, the Commission has determined that, pursuant to 10 CFR 72.7, this exemption is authorized by law, will not endanger life or property or the common defense and security, and is otherwise in the public interest. Therefore, the Commission hereby grants ENO an exemption from those provisions of 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), 10 CFR 72.214, and the portion of 10 CFR 72.212(b)(11) that require compliance with terms, conditions, and specifications of the CoC No. 1014, Amendment No. 10, for 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 MWD/MTU in MPC-68M using CoC No. 1014, Amendment No. 10. The exemption is effective upon issuance. Dated at Rockville, Maryland, this 8th day of February 2018. For the Nuclear Regulatory Commission. Meraj Rahimi, Acting Chief, Spent Fuel Licensing Branch, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2018-02930 Filed 2-12-18; 8:45 am] BILLING CODE 7590-01-P
![6244 Federal Register / Vol. 83, No. 30 / Tuesday, February 13, 2018 / Notices
• NRC’s Public Document Room: You ‘‘Inspection,’’ Section 2.1.1, ‘‘Transient NUCLEAR REGULATORY
may examine and purchase copies of Fire Hazards,’’ Section 3.2.1, ‘‘Fire COMMISSION
public documents at the NRC’s Public Protection Water Supply,’’ and Section
[Docket Nos. 72–1014, 72–59, and 50–271;
Document Room O1–F21, One White 3.2.3, ‘‘Fire Mains.’’ Previously, these NRC–2018–0020]
Flint North, 11555 Rockville Pike, errors occurred during publishing of the
Rockville, Maryland 20852. Regulatory final regulatory guide, when several Entergy Nuclear Operations, Inc.;
guides are not copyrighted, and NRC paragraphs were incorrectly indented, Vermont Yankee Nuclear Power
approval is not required to reproduce resulting in incorrect sub-bullet Station; Independent Spent Fuel
them. numbering. These changes are intended Storage Installation
FOR FURTHER INFORMATION CONTACT: to improve clarity and do not
Daniel Frumkin, Office of Nuclear AGENCY: Nuclear Regulatory
substantially alter the staff’s regulatory
Reactor Regulations, telephone: 301– Commission.
guidance.
415–2280, email: Daniel.Frumkin@ ACTION: Exemption; issuance.
nrc.gov; or Stanley Gardocki, Office of II. Backfitting and Issue Finality
SUMMARY: The U.S. Nuclear Regulatory
Nuclear Regulatory Research, telephone: Issuance of this final RG does not Commission (NRC) is issuing an
301–415–1067, email:
constitute backfitting as defined in exemption in response to a request
Stanley.Gardocki@nrc.gov. Both are staff
section 50.109 of title 10 of the Code of submitted by Entergy Nuclear
members of the U.S. Nuclear Regulatory
Federal Regulations (10 CFR), (the Operations, Inc. (ENO) on May 16, 2017,
Commission, Washington, DC 20555–
Backfit Rule), and is not otherwise and supplemented on September 7,
0001.
inconsistent with the issue finality 2017 and December 7, 2017, for its
SUPPLEMENTARY INFORMATION: provisions in 10 CFR part 52. The general license to operate an
I. Discussion changes in Revision 3 of RG 1.189 are independent spent fuel storage
limited to editorial changes to improve installation (ISFSI) at the Vermont
The NRC is issuing a revision to an Yankee Nuclear Power Station (VYNPS).
existing guide in the NRC ‘‘Regulatory clarity and correct errors. These changes
do not fall within the kinds of agency This exemption would permit the
Guide’’ series. Regulatory guides were VYNPS to use a new regionalized
developed to describe and make actions that constitute backfitting or are
subject to limitations in the issue loading pattern, load fuel cooled for at
available to the public information least 2 years, and establish a per-cell
methods that are acceptable to the NRC finality provisions of 10 CFR part 52.
maximum average burnup limit at
staff for implementing specific parts of Accordingly, the NRC did not address
65,000 megawatt days per metric ton of
the agency’s regulations, techniques that the Backfit Rule or issue finality
uranium (MWD/MTU) in HI–STORM
the staff uses in evaluating specific provisions of 10 CFR part 52. 100 multi-purpose canister (MPC)-68M
problems or postulated accidents, and using Certificate of Compliance (CoC)
III. Congressional Review Act
data that the staff needs in its review of No. 1014, Amendment No. 10.
applications for permits and licenses. Revision 3 of Regulatory Guide 1.189
The NRC is issuing Revision 3 of RG DATES: February 13, 2018.
is not a rule as defined in the
1.189 directly as a final RG, because the ADDRESSES: Please refer to Docket ID
Congressional Review Act (5 U.S.C. NRC–2018–0020 when contacting the
changes between Revision 2 and 801–808).
Revision 3 are administrative and non- NRC about the availability of
substantive. Revision 3 of RG 1.189 also IV. Submitting Suggestions for information regarding this document.
updated the guide to the current Improvement of Regulatory Guides You may obtain publicly-available
program guidance for RGs. The NRC information related to this document
added language to Section 1, ‘‘Fire Revision 3 of RG 1.189 is being issued using any of the following methods:
Protection Program,’’ to clarify the without public comment. However, a • Federal Rulemaking Website: Go to
primary objectives of fire protection member of the public may, at any time, http://www.regulations.gov and search
plans. submit suggestions to the NRC for for Docket ID NRC–2018–0020. Address
Since the issuance of Revision 2 of RG improvement of existing RGs or for the questions about NRC dockets to Carol
1.189 in 2009, the NRC issued a development of new RGs to address new Gallagher; telephone: 301–287–9127;
Regulatory Issuance Summary to inform issues. Suggestions can be submitted on email: Jennifer.Broges@nrc.gov. For
licensees that Inspection Manual Part the NRC’s public website at http:// technical questions, contact the
9900, Technical Guidance (TG 9900), www.nrc.gov/reading-rm/doc- individual listed in the FOR FURTHER
‘‘Operability Determinations & collections/reg-guides/contactus.html. INFORMATION CONTACT section of this
Functionality Assessments for Suggestions will be considered in future document.
Resolution of Degraded and updates and enhancements to the • NRC’s Agencywide Documents
Nonconforming Conditions Adverse to ‘‘Regulatory Guide’’ series. Access and Management System
Quality and Safety,’’ was reissued as (ADAMS): You may obtain publicly-
Inspection Manual Chapter (IMC) 0326, Dated at Rockville, Maryland, this 7th day available documents online in the
‘‘Operability Determinations and of February 2018. ADAMS Public Documents collection at
Functionality Assessments for For the Nuclear Regulatory Commission. http://www.nrc.gov/reading-rm/
Conditions to Quality or Safety,’’ dated Thomas H. Boyce, adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
sradovich on DSK3GMQ082PROD with NOTICES
January 31, 2014. Revision 3 of RG 1.189 Chief, Regulatory Guidance and Generic
now includes a reference to IMC 0326 Issues Branch, Division of Engineering, Office select ‘‘Begin Web-based ADAMS
(see Section 1.5, ‘‘Compensatory of Nuclear Regulatory Research. Search.’’ For problems with ADAMS,
Measures’’). [FR Doc. 2018–02870 Filed 2–12–18; 8:45 am] please contact the NRC’s Public
Revision 3 of RG 1.189 also corrects Document Room (PDR) reference staff at
BILLING CODE 7590–01–P
typographic errors that previously 1–800–397–4209, 301–415–4737, or by
appeared in Section 1.7.7, email to pdr.resource@nrc.gov. The
‘‘Nonconforming Items,’’ Section 1.7.4, ADAMS Accession No. for each
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![Federal Register / Vol. 83, No. 30 / Tuesday, February 13, 2018 / Notices 6247
IV. Conclusion must be made by March 5, 2018, to meeting agenda or transcript, contact
Accordingly, the Commission has ensure receiving the meeting rate for Davonya Barnes: barnes@nwtrb.gov. All
determined that, pursuant to 10 CFR available rooms. three can be reached by mail at 2300
The meeting will begin at 8:00 a.m. on Clarendon Boulevard, Suite 1300,
72.7, this exemption is authorized by
Tuesday, March 27, 2018, and is Arlington, VA 22201–3367; by
law, will not endanger life or property
scheduled to adjourn at 5:00 p.m. telephone at 703–235–4473; or by fax at
or the common defense and security,
Representatives from several countries 703–235–4495.
and is otherwise in the public interest.
will discuss national policies and
Therefore, the Commission hereby Dated: February 6, 2018.
approaches to monitoring and
grants ENO an exemption from those Nigel Mote,
retrievability. Technical specialists will
provisions of 10 CFR 72.212(a)(2), 10 Executive Director, U.S. Nuclear Waste
discuss sensors and technologies for
CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), Technical Review Board.
monitoring subsurface seepage, in-drift
10 CFR 72.214, and the portion of 10 environmental conditions, and [FR Doc. 2018–02883 Filed 2–12–18; 8:45 am]
CFR 72.212(b)(11) that require corrosion of waste packages for HLW BILLING CODE 6820–AM–P
compliance with terms, conditions, and and SNF emplaced in a geologic
specifications of the CoC No. 1014, repository. A detailed meeting agenda
Amendment No. 10, for the VYNPS to will be available on the Board’s website PENSION BENEFIT GUARANTY
use a new regionalized loading pattern, at www.nwtrb.gov approximately one CORPORATION
load fuel cooled for at least 2 years, and week before the meeting.
establish a per-cell maximum average The meeting will be open to the Privacy Act of 1974; Systems of
burnup limit at 65,000 MWD/MTU in public, and opportunities for public Records
MPC–68M using CoC No. 1014, comment will be provided before the
Amendment No. 10. AGENCY: Pension Benefit Guaranty
lunch break and at the end of the day. Corporation.
The exemption is effective upon Those wanting to speak are encouraged
issuance. ACTION: Notice of modified systems of
to sign the ‘‘Public Comment Register’’
Dated at Rockville, Maryland, this 8th day at the check-in table. Depending on the records; notice of a rescinded system of
of February 2018. number of people who sign up to speak, records; notice of a new system of
For the Nuclear Regulatory Commission. it may be necessary to set a time limit records.
Meraj Rahimi, on individual remarks. However, SUMMARY: Pursuant to the Privacy Act of
Acting Chief, Spent Fuel Licensing Branch, written comments of any length may be 1974, the Pension Benefit Guaranty
Division of Spent Fuel Management, Office submitted, and all comments received Corporation (PBGC) proposes the
of Nuclear Material Safety and Safeguards. in writing will be included in the record following changes to its system of
[FR Doc. 2018–02930 Filed 2–12–18; 8:45 am] of the meeting, which will be posted on records notices to: Amend a general
BILLING CODE 7590–01–P the Board’s website after the meeting. routine use, rescind a duplicative
The meeting will be webcast, and the system of records, establish a new
link to the webcast will be available on system of records for collection of data
NUCLEAR WASTE TECHNICAL the Board’s website (www.nwtrb.gov) a from the agency website, add or amend
REVIEW BOARD few days before the meeting. The routine uses in ten systems of records,
meeting presentations and an archived
make clarifying changes to all nineteen
Board Meeting version of the webcast will be available
systems of records notices, and
on the Board’s website following the
March 27, 2018—The U.S. Nuclear republish all existing systems of records
meeting. The transcript of the meeting
Waste Technical Review Board will notices. The PBGC determined that the
will be available on the Board’s website
meet in Washington, DC to discuss proposed changes were necessary after
no later than May 25, 2018.
performance confirmation monitoring The Board was established in the conducting the biennial review of its
and retrievability of emplaced high- NWPPA of 1987 as an independent systems of records notices.
level radioactive waste and spent federal agency in the Executive Branch DATES: Comments are due by March 15,
nuclear fuel. to evaluate the technical and scientific 2018. The revised and additional
Pursuant to its authority under validity of DOE activities related to the systems of records described herein will
section 5051 of Public Law 100–203, management and disposal of SNF and become effective 30 days after the date
Nuclear Waste Policy Amendments Act HLW and to provide objective expert of publication, without further notice,
(NWPAA) of 1987, the U.S. Nuclear advice to Congress and the Secretary of unless comments results in a contrary
Waste Technical Review Board will Energy on these issues. Board members determination and a notice is published
hold a public meeting in Washington, are experts in their fields and are to that effect.
DC on Tuesday, March 27, 2018, to appointed to the Board by the President ADDRESSES: You may submit written
review information related to from a list of candidates submitted by comments to PBGC by any of the
operational and performance the National Academy of Sciences. The following methods:
confirmation monitoring of a geologic Board reports its findings, conclusions, • Federal eRulemaking Portal: http://
repository and retrievability of and recommendations to Congress and www.regulations.gov. Follow the
emplaced high-level radioactive waste the Secretary of Energy. All Board website instructions for submitting
(HLW) and spent nuclear fuel (SNF). reports, correspondence, congressional comments.
The Board meeting will be held at the • Email: reg.comments@pbgc.gov.
sradovich on DSK3GMQ082PROD with NOTICES
testimony, and meeting transcripts and
Embassy Suites DC Convention Center, related materials are posted on the • Mail or Hand Delivery:
900 10th Street NW, Washington, DC Board’s website. Communications Outreach and
20001. A block of rooms has been For information on the meeting Legislative Affairs Department, Pension
reserved for meeting attendees at a rate agenda, contact Daniel Metlay: metlay@ Benefit Guaranty Corporation, 1200 K
of $253.00 per night. Reservations may nwtrb.gov or Karyn Severson: severson@ Street NW, Washington, DC 20005.
be made by phone (1–202–739–2001, nwtrb.gov. For information on lodging With appropriate redactions of
refer to NWTRB meeting). Reservations and logistics, or to request copies of the personally identifiable information,
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Document Created: 2018-02-13 02:32:20
Document Modified: 2018-02-13 02:32:20
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Exemption; issuance. | |
| Dates | February 13, 2018. | |
| Contact | Yen-Ju Chen, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555; telephone: 301-415-1018; email: yen- [email protected] | |
| FR Citation | 83 FR 6244 |
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