Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors, 89510-89511 [2016-29661]

Download as PDF 89510 Federal Register / Vol. 81, No. 238 / Monday, December 12, 2016 / Notices Estimated Total Annual Burden Hours: 7. By Gerard Poliquin, Secretary of the Board, the National Credit Union Administration, on November 29, 2016. NATIONAL CREDIT UNION ADMINISTRATION Submission for OMB Review; Comment Request National Credit Union Administration (NCUA). ACTION: Notice. AGENCY: The National Credit Union Administration (NCUA) will be submitting the following information collection request to the Office of Management and Budget (OMB) for review and clearance in accordance with the Paperwork Reduction Act of 1995, Public Law 104–13, on or after the date of publication of this notice. DATES: Comments should be received on or before January 11, 2017 to be assured of consideration. ADDRESSES: Send comments regarding the burden estimate, or any other aspect of the information collection, including suggestions for reducing the burden, to (1) Office of Information and Regulatory Affairs, Office of Management and Budget, Attention: Desk Officer for NCUA, New Executive Office Building, Room 10235, Washington, DC 20503, or email at OIRA_Submission@ OMB.EOP.gov and (2) NCUA PRA Clearance Officer, 1775 Duke Street, Alexandria, VA 22314, Suite 5067, or email at PRAComments@ncua.gov. FOR FURTHER INFORMATION CONTACT: Copies of the submission may be obtained by emailing PRAComments@ ncua.gov or viewing the entire information collection request at www.reginfo.gov. SUPPLEMENTARY INFORMATION: OMB Number: 3133–0170. Title: Fidelity Bond and Insurance Coverage for Federal Credit Unions 12 CFR part 713. Abstract: The Federal Credit Union Act (at 12 U.S.C. 1761(b)(2)) requires that the boards of federal credit unions (FCU) arrange for adequate fidelity coverage for officers and employees having custody of or responsibility for handling funds. The regulation contains a number of reporting requirements where a credit union seeks to exercise flexibility under the regulations. These requirements enable NCUA to monitor the FCU’s financial condition for safety and soundness purposes and helps to assure that FCUs are properly and adequately protected against potential losses due to insider abuse such as fraud and embezzlement. Type of Review: Extension of a previously approved collection. Affected Public: Private Sector: Notfor-profit institutions. SUMMARY: mstockstill on DSK3G9T082PROD with NOTICES Dated: December 7, 2016. Troy S. Hillier, NCUA PRA Clearance Officer. VerDate Sep<11>2014 18:59 Dec 09, 2016 Jkt 241001 [FR Doc. 2016–29695 Filed 12–9–16; 8:45 am] BILLING CODE 7535–01–P 10:00 a.m., Thursday, December 15, 2016. Board Room, 7th Floor, Room 7047, 1775 Duke Street (All visitors must use Diagonal Road Entrance), Alexandria, VA 22314–3428. PLACE: Open. MATTERS TO BE CONSIDERED: 1. Corporate Stabilization Fund Quarterly Report. 2. NCUA’s Rules and Regulations, Federal Credit Union Occupancy, Planning, and Disposal of Acquired and Abandoned Premises. 3. NCUA’s Rules and Regulations, Freedom of Information Act. 4. Revised Texas Member Business Loan Rule. 5. Board Briefing, NGN Legacy Asset Disposition Strategy. 11:30 a.m. 11:45 a.m., Thursday, December 15, 2016. TIME AND DATE: Board Room, 7th Floor, Room 7047, 1775 Duke Street, Alexandria, VA 22314–3428. PLACE: Closed. MATTERS TO BE CONSIDERED: 1. Creditor Claim Appeal. Closed pursuant to Exemption (6). 2. Request for Approval under Section 205(d). Closed pursuant to Exemption (6). FOR FURTHER INFORMATION CONTACT: Gerard Poliquin, Secretary of the Board, Telephone: 703–518–6304. Gerard Poliquin, Secretary of the Board. [FR Doc. 2016–29884 Filed 12–8–16; 4:15 pm] BILLING CODE 7535–01–P PO 00000 Frm 00086 Fmt 4703 Sfmt 4703 The U.S. Nuclear Regulatory Commission (NRC) is withdrawing regulatory guide (RG) 1.25, ‘‘Assumptions used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors.’’ This document is being withdrawn because the guidance contained in RG 1.25 has been superseded and is now incorporated into RG 1.183, ‘‘Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,’’ and RG 1.195, ‘‘Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors.’’ DATES: The effective date of the withdrawal of RG 1.25, ‘‘Assumptions used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors’’ is December 12, 2016. ADDRESSES: Please refer to Docket ID NRC–2016–0252 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 Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2016–0252. Address questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual(s) 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 https://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and then SUMMARY: TIME AND DATE: STATUS: Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors Nuclear Regulatory Commission. ACTION: Regulatory guide; withdrawal. Sunshine Act Meeting; Notice of Agency Meeting RECESS: [NRC–2016–0252] AGENCY: NATIONAL CREDIT UNION ADMINISTRATION STATUS: NUCLEAR REGULATORY COMMISSION E:\FR\FM\12DEN1.SGM 12DEN1 mstockstill on DSK3G9T082PROD with NOTICES Federal Register / Vol. 81, No. 238 / Monday, December 12, 2016 / Notices 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 withdrawal notice for RG 1.25 is available in ADAMS under accession No. ML16105A081. • 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: John Parillo, Office of Nuclear Reactor Regulation, telephone 301–415–1344; email John.Parillo@nrc.gov or Mark Orr, Office of Nuclear Regulatory Research, telephone: 301–415–6003; email: Mark.Orr@nrc.gov. Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. SUPPLEMENTARY INFORMATION: Regulatory guides may be withdrawn by the NRC when their guidance no longer provides useful information, or is superseded by technological innovations, congressional actions, or other events. The withdrawal of an RG should be thought of as the final revision of the guide. The NRC issued RG 1.25, ‘‘Assumptions used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors,’’ in March 1972 to provide guidance for the evaluation of the design basis fuel handling accident to demonstrate compliance with the NRC’s regulations in part 100 of Title 10 of the Code of Federal Regulations. The NRC is withdrawing RG 1.25 because the guidance contained in RG 1.25 has been superseded by more current guidance, which has been incorporated into RG 1.183, ‘‘Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,’’ and RG 1.195, ‘‘Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors.’’ The information in RG 1.183 provides guidance for new and existing light-water reactor (LWR) plants that have adopted the alternative source term (AST), and RG 1.195 provides guidance for those LWR plants that have not adopted the AST. The withdrawal of RG 1.25 does not alter any prior or existing NRC licensing approval or the acceptability of licensee commitments to RG 1.25. Although RG 1.25 is withdrawn, current licensees may continue to use it, and withdrawal VerDate Sep<11>2014 18:59 Dec 09, 2016 Jkt 241001 does not affect any existing licenses or agreements. However, RG 1.25 should not be used in future requests or applications for NRC licensing actions. Dated at Rockville, Maryland, this 5th day of December, 2016. For the Nuclear Regulatory Commission. Thomas H. Boyce, Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2016–29661 Filed 12–9–16; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 50–302; NRC–2016–0253] Duke Energy Florida, Inc., LLC; Crystal River Unit 3 Nuclear Generating Plant Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a partial exemption from three record keeping requirements in its regulations in response to a September 14, 2016, request from Duke Energy Florida, (DEF, or the licensee). Specifically, the licensee requested that the Crystal River Unit 3 Nuclear Generating Plant (CR–3), be granted a partial exemption from regulations that require retention of records for certain systems, structures, and components. DATES: The exemption was issued on November 30, 2016. ADDRESSES: Please refer to Docket ID NRC–2016–0253 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 Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2016–0253. Address questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@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 ‘‘ADAMS Public Documents’’ and then select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, SUMMARY: PO 00000 Frm 00087 Fmt 4703 Sfmt 4703 89511 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 it 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: John Hickman, Office of Nuclear Material Safety and Safeguards; U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415– 3017; email: John.Hickman@nrc.gov. SUPPLEMENTARY INFORMATION: I. Background The CR–3 facility is a decommissioning power reactor located in Citrus County, Florida. The licensee, DEF, is the holder of CR–3 Facility Operating License No. DPR–72. The CR– 3 has been shutdown since September 26, 2009. Subsequently, the licensee determined that issues with containment integrity could not be satisfactorily resolved and decided not to attempt to restart the facility. On May 28, 2011, DEF completed the removal of fuel from the reactor vessel at CR–3. By letter dated February 20, 2013 (ADAMS Accession No. ML13056A005), DEF submitted to the NRC a certification in accordance with section 50.82(a)(1)(i) of title 10 of the Code of Federal Regulations (10 CFR), indicating it would permanently cease power operations, and with § 50.82(a)(1)(ii) that it had permanently defueled the reactor vessel at CR–3. Because CR–3 is a permanently shutdown and defueled facility, and in accordance with § 50.82(a)(2), DEF is no longer authorized to operate the reactor or emplace nuclear fuel into the reactor vessel. The licensee is still authorized to possess and store irradiated (i.e., spent) nuclear fuel. The spent fuel is currently being stored onsite in a spent fuel pool (SFP). II. Request/Action By letter dated September 14, 2016 (ADAMS Accession No. ML16258A058), DEF filed a request for NRC approval of an exemption from the record retention requirements of: (1) 10 CFR part 50, appendix B, Criterion XVII, which requires certain records be retained consistent with other regulatory requirements; (2) § 50.59(d)(3), which requires certain records be maintained until termination of a license issued E:\FR\FM\12DEN1.SGM 12DEN1

Agencies

[Federal Register Volume 81, Number 238 (Monday, December 12, 2016)]
[Notices]
[Pages 89510-89511]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-29661]


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NUCLEAR REGULATORY COMMISSION

[NRC-2016-0252]


Assumptions Used for Evaluating the Potential Radiological 
Consequences of a Fuel Handling Accident in the Fuel Handling and 
Storage Facility for Boiling and Pressurized Water Reactors

AGENCY: Nuclear Regulatory Commission.

ACTION: Regulatory guide; withdrawal.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is withdrawing 
regulatory guide (RG) 1.25, ``Assumptions used for Evaluating the 
Potential Radiological Consequences of a Fuel Handling Accident in the 
Fuel Handling and Storage Facility for Boiling and Pressurized Water 
Reactors.'' This document is being withdrawn because the guidance 
contained in RG 1.25 has been superseded and is now incorporated into 
RG 1.183, ``Alternative Radiological Source Terms for Evaluating Design 
Basis Accidents at Nuclear Power Reactors,'' and RG 1.195, ``Methods 
and Assumptions for Evaluating Radiological Consequences of Design 
Basis Accidents at Light-Water Nuclear Power Reactors.''

DATES: The effective date of the withdrawal of RG 1.25, ``Assumptions 
used for Evaluating the Potential Radiological Consequences of a Fuel 
Handling Accident in the Fuel Handling and Storage Facility for Boiling 
and Pressurized Water Reactors'' is December 12, 2016.

ADDRESSES: Please refer to Docket ID NRC-2016-0252 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 Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2016-0252. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact 
the individual(s) 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 https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then

[[Page 89511]]

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 
withdrawal notice for RG 1.25 is available in ADAMS under accession No. 
ML16105A081.
     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: John Parillo, Office of Nuclear 
Reactor Regulation, telephone 301-415-1344; email John.Parillo@nrc.gov 
or Mark Orr, Office of Nuclear Regulatory Research, telephone: 301-415-
6003; email: Mark.Orr@nrc.gov. Both are staff of the U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION: Regulatory guides may be withdrawn by the 
NRC when their guidance no longer provides useful information, or is 
superseded by technological innovations, congressional actions, or 
other events. The withdrawal of an RG should be thought of as the final 
revision of the guide.
    The NRC issued RG 1.25, ``Assumptions used for Evaluating the 
Potential Radiological Consequences of a Fuel Handling Accident in the 
Fuel Handling and Storage Facility for Boiling and Pressurized Water 
Reactors,'' in March 1972 to provide guidance for the evaluation of the 
design basis fuel handling accident to demonstrate compliance with the 
NRC's regulations in part 100 of Title 10 of the Code of Federal 
Regulations. The NRC is withdrawing RG 1.25 because the guidance 
contained in RG 1.25 has been superseded by more current guidance, 
which has been incorporated into RG 1.183, ``Alternative Radiological 
Source Terms for Evaluating Design Basis Accidents at Nuclear Power 
Reactors,'' and RG 1.195, ``Methods and Assumptions for Evaluating 
Radiological Consequences of Design Basis Accidents at Light-Water 
Nuclear Power Reactors.'' The information in RG 1.183 provides guidance 
for new and existing light-water reactor (LWR) plants that have adopted 
the alternative source term (AST), and RG 1.195 provides guidance for 
those LWR plants that have not adopted the AST.
    The withdrawal of RG 1.25 does not alter any prior or existing NRC 
licensing approval or the acceptability of licensee commitments to RG 
1.25. Although RG 1.25 is withdrawn, current licensees may continue to 
use it, and withdrawal does not affect any existing licenses or 
agreements. However, RG 1.25 should not be used in future requests or 
applications for NRC licensing actions.

    Dated at Rockville, Maryland, this 5th day of December, 2016.

    For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic Issues Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2016-29661 Filed 12-9-16; 8:45 am]
 BILLING CODE 7590-01-P
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