83 FR 42320 - Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station
NUCLEAR REGULATORY COMMISSION Federal Register Volume 83, Issue 162 (August 21, 2018)
Federal Register Volume 83, Issue 162 (August 21, 2018)
| Page Range | 42320-42322 | |
| FR Document | 2018-17988 |
[Federal Register Volume 83, Number 162 (Tuesday, August 21, 2018)] [Notices] [Pages 42320-42322] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2018-17988] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-271 and 72-59; NRC-2018-0179] Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to a May 24, 2018, request from Entergy Nuclear Operations, Inc., for an exemption of up to 3 months from certain security training schedule requirements for the Vermont Yankee Nuclear Power Station. DATES: The exemption was issued on July 31, 2018. ADDRESSES: Please refer to Docket ID NRC-2018-0179 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-2018-0179. Address questions about NRC dockets to Jennifer Borges; telephone: 301-287- 9127; email: [email protected]. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this 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 number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. 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: Jack D. Parrott, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-6634, email: [email protected]. SUPPLEMENTARY INFORMATION: The text of the exemption is attached. Dated at Rockville, Maryland, this 16th day of August 2018. For the Nuclear Regulatory Commission. Bruce A. Watson, Chief, Reactor Decommissioning Branch, Division of Decommissioning, Uranium Recovery and Waste Programs, Office of Nuclear Material Safety and Safeguards. Attachment--Exemption UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ENTERGY NUCLEAR OPERATIONS, INC.; VERMONT YANKEE NUCLEAR POWER STATION DOCKET NOS. 50-271 AND 72-59 EXEMPTION 1.0 BACKGROUND Entergy Nuclear Operations, Inc. (ENO or the licensee) is the holder of Facility Operating License No. DPR-28 for the Vermont Yankee Nuclear Power Station (VY) in Windham County, Vermont. The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the Nuclear Regulatory Commission (NRC or the Commission) now or hereafter in effect. The facility now consists of a permanently shut down and decommissioning boiling water reactor and associated Independent Spent Fuel Storage Installation (ISFSI). The licensee is in the process of transferring the remaining spent fuel from the spent fuel pool into dry storage canisters that are then placed in concrete overpacks and stored on the ISFSI pad. Concurrently, the licensee received, by letter dated July 25, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18165A423), NRC approval of a license amendment for implementation of a revised Physical Security Plan (PSP) to meet the security requirements of an ISFSI-only configuration for spent fuel storage at the site. The effective date of the ISFSI-only PSP approval is the date on which the licensee notifies the NRC in writing that all of the spent nuclear fuel assemblies have been transferred out of the spent fuel pool and have been placed in dry storage within the ISFSI. Implementation of the ISFSI-only PSP shall be within 90 days of the effective date of the approval of the amendment. 2.0 REQUEST/ACTION By letter dated May 24, 2018, and pursuant to 10 CFR 73.5, ``Specific Exemptions,'' ENO requested an exemption from certain schedule [[Page 42321]] requirements of 10 CFR part 73, Appendix B, Section VI.A.7, which covers training and qualification plans for personnel performing security program duties at nuclear power reactors (ADAMS Accession No. ML18150A337). Attachment 2 to the request letter contains security- related information and, accordingly, is not available to the public. 10 CFR part 73, Appendix B, Section VI.A.7, states-- Annual requirements must be scheduled at a nominal twelve (12) month periodicity. Annual requirements may be completed up to three (3) months before or three (3) months after the scheduled date. However, the next annual training must be scheduled twelve (12) months from the previously scheduled date rather than the date the training was actually completed. The scheduled dates for the completion of specified 2018 annual training for certain weapons training and security exercises at VY were May 9, 2018, and June 6, 2018. Consequently, the deadlines for completing these activities (taking into account the 3-month allowance provided in 10 CFR part 73, Appendix B, Section VI.A.7) are August 7, 2018, and September 4, 2018. This exemption was requested to allow the completion date for specified annual training for certain weapons training and security exercises to be no later than November 7, 2018, which would be a 3- month extension from the current due date based on the regulation referenced above. The express purpose of the request is to move the completion due date for the specified annual training past the expected implementation date of the NRC-approved revision of the current PSP to an ISFSI-only PSP. Implementation of the ISFSI-only PSP will be performed after the remaining spent fuel is loaded and placed on the ISFSI pad. Because specific security annual training is not required for sites with an ISFSI-only configuration for spent nuclear fuel, this exemption would allow the licensee to delay completion of the training until such time as it is no longer required. The required implementation date for the ISFSI-only PSP is within 90 days from the date that the licensee notifies the NRC in writing that all spent nuclear fuel assemblies have been transferred out of the spent fuel pool and have been placed in dry storage within the ISFSI. The expected completion date for the transfer to dry fuel storage is August 2018. As described in spent fuel cask registration letters dated May 31, 2018 (ADAMS Accession No. ML18156A132) and June 12, 2018 (ADAMS Accession No. ML18172A127), the licensee has loaded four MPC-68M multi- purpose canisters between May 5, 2018, and June 5, 2018, and those canisters in turn have been loaded into HI-STORM 100S Version B overpacks and placed on the ISFSI pad. Therefore, the current loading campaign is capable of loading and placing on the ISFSI pad approximately one canister per week. As of June 12, 2018, there were 9 canisters left to be loaded and placed on the ISFSI pad. Therefore, the completion of loading spent fuel into canisters and placing them on the ISFSI pad is considered achievable by the end of August 2018. With this exemption, the licensee will not be in violation of the training schedule requirements of 10 CFR part 73, Appendix B, Section VI.A.7, provided that, prior to November 7, 2018, the licensee either implements the ISFSI-only PSP, or completes the noted specific security training. 3.0 DISCUSSION OF EXEMPTION FROM 10 CFR PART 73, APPENDIX B, SECTION VI.A.7 TRAINING SCHEDULE REQUIREMENTS The NRC approval of this exemption would allow an extension until November 7, 2018, for certain annual training required by 10 CFR part 73, Appendix B, Section VI.A.7 (i.e., weapons training and security exercises that are specifically referenced in Attachment 2 to the licensee's exemption request (security-related information)). Pursuant to 10 CFR 73.5, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR part 73 when the exemptions are authorized by law, and will not endanger life or property or the common defense and security, and are otherwise in the public interest. Authorized by Law As explained in this SER, the proposed exemption will not endanger life or property, nor the common defense and security, and is otherwise in the public interest. Issuance of this exemption is consistent with the Atomic Energy Act of 1954, as amended, and not otherwise inconsistent with the NRC's regulations or other applicable laws. Therefore, issuance of the exemption is authorized by law. Will Not Endanger Life or Property or the Common Defense and Security Granting of the proposed exemption will allow the completion dates of the specified annual training and qualification activities to be extended beyond the scheduled completion dates specified in 10 CFR part 73, Appendix B Section VI.A.7. The exemption does not affect the requirements for other periodic, specifically quarterly and trimester, security training activities that will continue and will provide training opportunities which ensure the proficiency of the training staff during the limited time affected by the schedule change. The proposed exemption would not significantly reduce the measures currently in place to protect against radiological sabotage, theft or diversion, or significantly reduce the overall effectiveness of the PSP, Training and Qualification Plan, or Safeguards Contingency Plan. Therefore, granting the exemption will not endanger life or property or the common defense and security. Is Otherwise in the Public Interest Completing the annual training by the dates required by 10 CFR part 73, Appendix B, Section VI.A.7 would divert site personnel from the role of providing support and oversight of the ongoing dry fuel storage loading campaign with little benefit considering the short amount of time that the remaining spent fuel would be in the spent fuel pool after the current due date for the training. Allowing the ongoing cask loading campaign to continue without interruptions imposed by the annual training would support safety and efficiency for those activities and more expeditious completion of the transfer of irradiated fuel out of the spent fuel pool. Granting an exemption from the annual training would also avoid diverting site resources from providing support for ongoing efforts to complete construction, testing, training, and implementation of the features associated with the ISFSI-only PSP. The proposed exemption would allow annual training to be rescheduled beyond the current schedule date for completing the transfer of irradiated fuel from the spent fuel pool to dry storage. The exemption would not reduce overall protection of the facility and stored irradiated fuel, but would maintain the current level of safety and security, and would avoid diverting site personnel attention from completing the transfer of spent fuel to dry storage. Therefore, the proposed exemption is in the public interest. 4.0 ENVIRONMENTAL CONSIDERATIONS Under 10 CFR 51.22(c)(25), granting of an exemption from the requirements of any regulation of Chapter I falls within a categorical exclusion to the environmental review requirements of [[Page 42322]] Part 51, provided that (i) there is no significant hazards consideration; (ii) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (iii) there is no significant increase in individual or cumulative public or occupational radiation exposure; (iv) there is no significant construction impact; (v) there is no significant increase in the potential for or consequences from radiological accidents; and (vi) the requirements from which an exemption is sought are among those identified in 10 CFR 51.22(c)(25)(vi). The Director, Division of Decommissioning, Uranium Recovery, and Waste Programs, has determined that approval of the exemption request involves no significant hazards consideration because allowing the licensee to have an exemption of up to 3 months from certain schedule requirements of 10 CFR part 73, Appendix B, ``General Criteria for Security Personnel,'' for VY does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. The exemption from certain schedule requirements of 10 CFR part 73, Appendix B, Section VI.A.7 is unrelated to any operational restriction. Accordingly, there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; and no significant increase in individual or cumulative public or occupational radiation exposure. The exempted regulation is not associated with construction, so there is no significant construction impact. The exempted regulation does not concern the source term (i.e., potential amount of radiation in an accident), nor mitigation. Thus, there is no significant increase in the potential for or consequences from radiological accidents. The requirements from which the exemption is sought fall within categories identified in 10 CFR 51.22(c)(25)(vi), specifically scheduling requirements, as well as education, weapons training, training exercises, qualification, requalification or other employment suitability requirements. Therefore, pursuant to 10 CFR 51.22(b) and 51.22(c)(25), no environmental impact statement or environmental assessment need be prepared in connection with the approval of this exemption request. 5.0 CONCLUSION FOR 10 CFR PART 73, APPENDIX B, SECTION VI.A.7 SCHEDULE EXEMPTION REQUEST The NRC staff has reviewed the licensee's submittals and concludes that the licensee has justified its request for an extension of certain 10 CFR part 73, Appendix B, Section VI.A.7 security training schedules to November 7, 2018. Accordingly, the NRC has determined that pursuant to 10 CFR 73.5, ``Specific exemptions,'' an exemption from certain 10 CFR part 73, Appendix B, Section VI.A.7 security training schedule requirements is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest. The NRC hereby grants the requested exemption. The NRC staff has determined that efficiencies will be gained if the NRC-approved ISFSI-only PSP is implemented within 90 days of the completion of removal of spent fuel from the VY spent fuel pool. The NRC has concluded that approving the licensee's exemption request is in the best interest of protecting the public health and safety through the efficiencies gained by not having to perform the currently scheduled annual security training shortly before the removal of spent fuel from the spent fuel pool and placement in the ISFSI, which would make the scheduled training moot. This exemption expires on November 7, 2018. By that time, the licensee is required to have implemented its ISFSI-only PSP, or be in full compliance with the security training schedule requirements of 10 CFR part 73, Appendix B, Section VI.A.7. Pursuant to 10 CFR 51.22(c)(25), NRC has determined that granting of an exemption from the requirements of 10 CFR part 73, Appendix B, Section VI.A.7 falls within a categorical exclusion to the environmental review requirements of Part 51. This exemption is effective upon issuance. Dated at Rockville, Maryland, this 31st day of July 2018. For The Nuclear Regulatory Commission Andrea Kock, Acting Director, Division of Decommissioning, Uranium Recovery and Waste Programs, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2018-17988 Filed 8-20-18; 8:45 am] BILLING CODE 7590-01-P
![42320 Federal Register / Vol. 83, No. 162 / Tuesday, August 21, 2018 / Notices
B. Submitting Comments NUCLEAR REGULATORY SUPPLEMENTARY INFORMATION: The text of
COMMISSION the exemption is attached.
Please include Docket ID NRC–2018–
[Docket Nos. 50–271 and 72–59; NRC–2018– Dated at Rockville, Maryland, this 16th day
0159 in your comment submission. of August 2018.
0179]
The NRC cautions you not to include For the Nuclear Regulatory Commission.
identifying or contact information that Entergy Nuclear Operations, Inc.; Bruce A. Watson,
you do not want to be publicly Vermont Yankee Nuclear Power Chief, Reactor Decommissioning Branch,
disclosed in your comment submission. Station Division of Decommissioning, Uranium
The NRC will post all comment Recovery and Waste Programs, Office of
AGENCY: Nuclear Regulatory Nuclear Material Safety and Safeguards.
submissions at http://
Commission.
www.regulations.gov as well as enter the Attachment—Exemption
comment submissions into ADAMS. ACTION: Exemption; issuance.
The NRC does not routinely edit UNITED STATES OF AMERICA
SUMMARY: The U.S. Nuclear Regulatory
comment submissions to remove Commission (NRC) has issued an NUCLEAR REGULATORY
identifying or contact information. exemption in response to a May 24, COMMISSION ENTERGY NUCLEAR
If you are requesting or aggregating 2018, request from Entergy Nuclear OPERATIONS, INC.; VERMONT
comments from other persons for Operations, Inc., for an exemption of up YANKEE NUCLEAR POWER STATION
submission to the NRC, then you should to 3 months from certain security DOCKET NOS. 50–271 AND 72–59
inform those persons not to include training schedule requirements for the
Vermont Yankee Nuclear Power Station. EXEMPTION
identifying or contact information that
they do not want to be publicly DATES: The exemption was issued on 1.0 BACKGROUND
disclosed in their comment submission. July 31, 2018. Entergy Nuclear Operations, Inc.
Your request should state that the NRC ADDRESSES: Please refer to Docket ID (ENO or the licensee) is the holder of
does not routinely edit comment NRC–2018–0179 when contacting the Facility Operating License No. DPR–28
submissions to remove such information NRC about the availability of for the Vermont Yankee Nuclear Power
before making the comment information regarding this document. Station (VY) in Windham County,
submissions available to the public or You may obtain publicly-available Vermont. The license provides, among
entering the comment into ADAMS. information related to this document other things, that the facility is subject
using any of the following methods: to all rules, regulations, and orders of
II. Discussion • Federal Rulemaking Website: Go to the Nuclear Regulatory Commission
http://www.regulations.gov and search (NRC or the Commission) now or
On August 1, 2018, the NRC solicited
for Docket ID NRC–2018–0179. Address hereafter in effect. The facility now
comments on its draft ISG on DFPs for questions about NRC dockets to Jennifer
materials licensees. The purpose of this consists of a permanently shut down
Borges; telephone: 301–287–9127; and decommissioning boiling water
ISG is to provide NRC staff and industry email: Jennifer.Borges@nrc.gov. For reactor and associated Independent
with guidance based on developments technical questions, contact the Spent Fuel Storage Installation (ISFSI).
and lessons learned regarding financial individual listed in the FOR FURTHER The licensee is in the process of
assurance since the last update to INFORMATION CONTACT section of this transferring the remaining spent fuel
NUREG–1757, Volume 3. The ISG • NRC’s Agencywide Documents from the spent fuel pool into dry storage
covers decommissioning cost estimates Access and Management System canisters that are then placed in
describing current facility conditions, (ADAMS): You may obtain publicly- concrete overpacks and stored on the
evaluating events since the last DFP available documents online in the ISFSI pad. Concurrently, the licensee
approval, and updates for certain ADAMS Public Documents collection at received, by letter dated July 25, 2018
financial instruments. The public http://www.nrc.gov/reading-rm/ (Agencywide Documents Access and
comment period was originally adams.html. To begin the search, select Management System (ADAMS)
scheduled to close on September 17, ‘‘ADAMS Public Documents’’ and then Accession No. ML18165A423), NRC
2018. The NRC has decided to extend select ‘‘Begin Web-based ADAMS approval of a license amendment for
the public comment period on this Search.’’ For problems with ADAMS, implementation of a revised Physical
document until October 5, 2018, to please contact the NRC’s Public Security Plan (PSP) to meet the security
allow more time for industry and Document Room (PDR) reference staff at requirements of an ISFSI-only
members of the public to submit their 1–800–397–4209, 301–415–4737, or by configuration for spent fuel storage at
comments. email to pdr.resource@nrc.gov. The the site. The effective date of the ISFSI-
ADAMS accession number for each only PSP approval is the date on which
Dated at Rockville, Maryland, this 14th day document referenced (if it is available in
of August 2018.
the licensee notifies the NRC in writing
ADAMS) is provided the first time that that all of the spent nuclear fuel
For the Nuclear Regulatory Commission. it is mentioned in this document. assemblies have been transferred out of
Andrea L. Kock, • NRC’s PDR: You may examine and the spent fuel pool and have been
Deputy Director, Division of purchase copies of public documents at placed in dry storage within the ISFSI.
Decommissioning, Uranium Recovery and the NRC’s PDR, Room O1–F21, One Implementation of the ISFSI-only PSP
White Flint North, 11555 Rockville
sradovich on DSK3GMQ082PROD with NOTICES
Waste Programs, Office of Nuclear Material shall be within 90 days of the effective
Safety and Safeguards. Pike, Rockville, Maryland 20852. date of the approval of the amendment.
[FR Doc. 2018–17983 Filed 8–20–18; 8:45 am] FOR FURTHER INFORMATION CONTACT: Jack
D. Parrott, Office of Nuclear Material 2.0 REQUEST/ACTION
BILLING CODE 7590–01–P
Safety and Safeguards, U.S. Nuclear By letter dated May 24, 2018, and
Regulatory Commission, Washington, pursuant to 10 CFR 73.5, ‘‘Specific
DC 20555–0001; telephone: 301–415– Exemptions,’’ ENO requested an
6634, email: Jack.Parrott@nrc.gov. exemption from certain schedule
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![42322 Federal Register / Vol. 83, No. 162 / Tuesday, August 21, 2018 / Notices
Part 51, provided that (i) there is no 5.0 CONCLUSION FOR 10 CFR PART OFFICE OF PERSONNEL
significant hazards consideration; (ii) 73, APPENDIX B, SECTION VI.A.7 MANAGEMENT
there is no significant change in the SCHEDULE EXEMPTION REQUEST
types or significant increase in the Federal Prevailing Rate Advisory
amounts of any effluents that may be The NRC staff has reviewed the Committee; Open Committee Meetings
released offsite; (iii) there is no licensee’s submittals and concludes that
the licensee has justified its request for AGENCY: Office of Personnel
significant increase in individual or
an extension of certain 10 CFR part 73, Management.
cumulative public or occupational
radiation exposure; (iv) there is no Appendix B, Section VI.A.7 security ACTION: Notice of Federal Prevailing
significant construction impact; (v) training schedules to November 7, 2018. Rate Advisory Committee Meeting Dates
there is no significant increase in the in 2018.
Accordingly, the NRC has determined
potential for or consequences from that pursuant to 10 CFR 73.5, ‘‘Specific According to the provisions of section
radiological accidents; and (vi) the exemptions,’’ an exemption from certain 10 of the Federal Advisory Committee
requirements from which an exemption 10 CFR part 73, Appendix B, Section Act (Pub. L. 92–463), notice is hereby
is sought are among those identified in given that meetings of the Federal
VI.A.7 security training schedule
10 CFR 51.22(c)(25)(vi). Prevailing Rate Advisory Committee
requirements is authorized by law and
The Director, Division of will not endanger life or property or the will be held on—
Decommissioning, Uranium Recovery, Thursday, September 20, 2018
common defense and security, and is
and Waste Programs, has determined Thursday, October 18, 2018
otherwise in the public interest. The
that approval of the exemption request Thursday, November 15, 2018
involves no significant hazards NRC hereby grants the requested
exemption. Thursday, December 20, 2018
consideration because allowing the The meetings will start at 10 a.m. and
licensee to have an exemption of up to The NRC staff has determined that will be held in Room 5A06A, Office of
3 months from certain schedule efficiencies will be gained if the NRC- Personnel Management Building, 1900 E
requirements of 10 CFR part 73, approved ISFSI-only PSP is Street, NW, Washington, DC.
Appendix B, ‘‘General Criteria for implemented within 90 days of the The Federal Prevailing Rate Advisory
Security Personnel,’’ for VY does not (1) completion of removal of spent fuel Committee is composed of a Chair, five
involve a significant increase in the from the VY spent fuel pool. The NRC representatives from labor unions
probability or consequences of an has concluded that approving the holding exclusive bargaining rights for
accident previously evaluated; or (2) licensee’s exemption request is in the Federal prevailing rate employees, and
create the possibility of a new or best interest of protecting the public five representatives from Federal
different kind of accident from any health and safety through the agencies. Entitlement to membership on
accident previously evaluated; or (3) efficiencies gained by not having to the Committee is provided for in 5
involve a significant reduction in a perform the currently scheduled annual U.S.C. 5347.
margin of safety. The exemption from security training shortly before the The Committee’s primary
certain schedule requirements of 10 CFR removal of spent fuel from the spent responsibility is to review the Prevailing
part 73, Appendix B, Section VI.A.7 is Rate System and other matters pertinent
fuel pool and placement in the ISFSI,
unrelated to any operational restriction. to establishing prevailing rates under
which would make the scheduled
Accordingly, there is no significant subchapter IV, chapter 53, 5 U.S.C., as
training moot.
change in the types or significant amended, and from time to time advise
increase in the amounts of any effluents This exemption expires on November the Office of Personnel Management.
that may be released offsite; and no 7, 2018. By that time, the licensee is These scheduled meetings are open to
significant increase in individual or required to have implemented its ISFSI- the public with both labor and
cumulative public or occupational only PSP, or be in full compliance with management representatives attending.
radiation exposure. The exempted the security training schedule During the meetings either the labor
regulation is not associated with requirements of 10 CFR part 73, members or the management members
construction, so there is no significant Appendix B, Section VI.A.7. may caucus separately to devise strategy
construction impact. The exempted Pursuant to 10 CFR 51.22(c)(25), NRC and formulate positions. Premature
regulation does not concern the source has determined that granting of an disclosure of the matters discussed in
term (i.e., potential amount of radiation exemption from the requirements of 10 these caucuses would unacceptably
in an accident), nor mitigation. Thus, CFR part 73, Appendix B, Section impair the ability of the Committee to
there is no significant increase in the reach a consensus on the matters being
VI.A.7 falls within a categorical
potential for or consequences from considered and would disrupt
exclusion to the environmental review
radiological accidents. The substantially the disposition of its
requirements of Part 51.
requirements from which the exemption business. Therefore, these caucuses will
is sought fall within categories This exemption is effective upon be closed to the public because of a
identified in 10 CFR 51.22(c)(25)(vi), issuance. determination made by the Director of
specifically scheduling requirements, as Dated at Rockville, Maryland, this 31st day the Office of Personnel Management
well as education, weapons training, of July 2018. under the provisions of section 10(d) of
training exercises, qualification, For The Nuclear Regulatory Commission the Federal Advisory Committee Act
requalification or other employment (Pub. L. 92–463) and 5 U.S.C.
sradovich on DSK3GMQ082PROD with NOTICES
suitability requirements. Andrea Kock,
552b(c)(9)(B). These caucuses may,
Therefore, pursuant to 10 CFR Acting Director, Division of depending on the issues involved,
51.22(b) and 51.22(c)(25), no Decommissioning, Uranium Recovery and constitute a substantial portion of a
environmental impact statement or Waste Programs, Office of Nuclear Material meeting.
environmental assessment need be Safety and Safeguards. Annually, the Chair compiles a report
prepared in connection with the [FR Doc. 2018–17988 Filed 8–20–18; 8:45 am] of pay issues discussed and concluded
approval of this exemption request. BILLING CODE 7590–01–P recommendations. These reports are
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Document Created: 2018-08-21 00:08:09
Document Modified: 2018-08-21 00:08:09
| 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 | The exemption was issued on July 31, 2018. | |
| Contact | Jack D. Parrott, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-6634, email: [email protected] | |
| FR Citation | 83 FR 42320 |
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