81 FR 40354 - Independent Spent Fuel Storage Installation, Department of Energy; Fort St. Vrain
NUCLEAR REGULATORY COMMISSION Federal Register Volume 81, Issue 119 (June 21, 2016)
Federal Register Volume 81, Issue 119 (June 21, 2016)
| Page Range | 40354-40357 | |
| FR Document | 2016-14673 |
[Federal Register Volume 81, Number 119 (Tuesday, June 21, 2016)] [Notices] [Pages 40354-40357] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2016-14673] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket No. 72-09; NRC-2015-0150] Independent Spent Fuel Storage Installation, Department of Energy; Fort St. Vrain 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 the Department of Energy (DOE or the licensee) on April 27, 2016, from NRC's requirement to comply with the terms, conditions, and specifications concerning testing and surveillance in Special Nuclear Material License No. SNM- 2504 for the Fort St. Vrain independent spent fuel storage installation (ISFSI). The exemption request seeks the extension of the time to perform an O-ring leakage rate test required by Technical Specification (TS) 3.3.1 of Appendix A of Special Nuclear Material License No. SNM- 2504 and to perform an aging management surveillance described in the Fort St. Vrain (FSV) Final Safety Analysis Report (FSAR). The DOE requests the dates for performance of the testing and surveillance requirements be extended until December 2016. The NRC previously granted DOE an exemption (80 FR 33299 dated, June 11, 2015) extending the completion date for these actions until June 2016. DATES: The exemption is effective on June 21, 2016. ADDRESSES: Please refer to Docket ID NRC-2015-0150 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 http://www.regulations.gov and search for Docket ID NRC-2015-0150. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; 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 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: Bernard White, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-6577; email: [email protected]. I. Background The DOE is the holder of Special Nuclear Material License No. SNM- [[Page 40355]] 2504 which authorizes receipt, possession, storage, transfer, and use of irradiated fuel elements from the decommissioned FSV Nuclear Generating Station in Platteville, Colorado, under part 72 of title 10 of the Code of Federal Regulations (10 CFR). II. Request/Action In a letter dated, April 27, 2016, the DOE requested an exemption to delay performance of both the fuel storage container O-ring leakage rate test requirement and the FSAR aging management surveillance of fuel storage containers by six months, until December 31, 2016 (ADAMS Accession No. ML16120A410). Technical Specification 3.1.1 in Appendix A of License No. SNM-2504 stipulates that, the fuel storage container seal leakage rate for shall not exceed 1 x 10-\3\ reference cubic centimeters per second (ref-cm\3\/s). Surveillance Requirement (SR) 3.3.1.1 requires that one fuel storage container from each vault to be leakage rate tested every five years to confirm that the seal leakage rate is not exceeded. DOE performed the last leakage rate test in June 2010 and the next leakage rate test is scheduled to be completed in June 2016. Fort St.Vrain implemented its aging management program as part of license renewal in 2011. Condition 9 of SNM-2504 states, in relevant part, that authorized use of the material at the FSV ISFSI shall be ``in accordance with statements, representations, and the conditions of the Technical Specifications and Safety Analysis Report.'' Condition 11 of SNM-2504 directs the licensee to operate the facility in accordance with the Technical Specifications in Appendix A. In Chapter 9 of the FSV FSAR the licensee committed to assess six fuel storage containers for potential hydrogen buildup by the end of June 2015. This date was extended until June 2016, with NRC's grant of an exemption. The hydrogen sampling schedule was established to parallel the fuel storage container seal leakage rate testing schedule. III. Discussion Pursuant to 10 CFR 72.7, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR part 72 when the exemption is authorized by law, will not endanger life or property or the common defense and security, and is otherwise in the public interest. The DOE requested an exemption from both 10 CFR 72.44(c)(1) and 10 CFR 72.44(c)(3). Section 72.44(c)(1) requires, in part, compliance with functional and operational limits to protect the integrity of waste containers and to guard against the uncontrolled release of radioactive material. Section 72.44(c)(3) requires compliance with surveillance requirement in Limiting Condition of Operation (LCO) 3.3.1 which the licensee will use show that the ISFSI has not exceeded the fuel storage container or storage well seal leakage rate. For these reasons, the staff also grants DOE an exemption from the requirements of 10 CFR 72.44(c)(1) and 10 CFR 72.44(c)(3). As is explained in following paragraphs, the proposed exemption is lawful, will not endanger life or property, or the common defense and security, and is otherwise in the public interest. Authorized by Law This exemption delays until December 2016, the licensee's performance of (1) a fuel storage container O-ring leakage rate test required by TS 3.3.1 of Appendix A of Special Nuclear Material License No. SNM-2504 and (2) an FSAR aging management surveillance to inspect six fuel storage containers for hydrogen buildup. Condition 9 of SNM- 2504 states, in relevant part, that authorized use of the material at the FSV's ISFSI shall be ``in accordance with statements, representations, and the conditions of the Technical Specifications and Safety Analysis Report.'' Condition 11 of SNM-2504 also directs the licensee to operate the facility in accordance with the Technical Specifications in Appendix A. The provisions in 10 CFR 72.44(c)(1) and (3) require the licensee to follow the technical specifications and the functional and operational limits for the facility. The testing and inspection requirements from which DOE requested exemption are detailed in the Special Nuclear Material License No. SNM-2504, the FSAR, and FSV's technical specifications and must be complied with pursuant to 10 CFR part 72. Section 72.7 allows the NRC to grant specific exemptions from the requirements of 10 CFR part 72. Issuance of this exemption is consistent with the Atomic Energy Act of 1954, as amended, and not otherwise inconsistent with NRC regulations or other applicable laws. Therefore, the exemption is authorized by law. Will Not Endanger Life or Property or the Common Defense and Security In granting the March 19, 2015 exemption request, the NRC staff determined that it would not endanger life or property, or the common defense and security. The current exemption extends the deadline for performance of the testing and surveillance requirements until December 2016. The staff evaluated whether the additional six month extension provided by this exemption would change its earlier finding; the staff finds that the current exemption does not endanger life or property, or the common defense and security for the reasons discussed below. Potential Corrosion Fort St. Vrain's ISFSI Aging Management Program described in Section 9.8 of FSV's ISFSI FSAR identifies a commitment to test one fuel storage container in each vault for hydrogen buildup. The test is designed to identify corrosion in the interior of the fuel storage containers. In its FSAR the licensee committed to complete testing for hydrogen buildup on the same schedule as the leak test, which required the test to be completed no later than June 2015. In its March 2015 exemption request, FSV concluded that hydrogen buildup had not occurred in fuel storage containers in its ISFSI. The NRC extended the completion date for the sampling for actual hydrogen buildup until to June 2016. Fort St. Vrain's conclusions were supported by the following observations: 1. The fuel was stored in dry helium prior to placement in the fuel storage containers. 2. General corrosion, as opposed to galvanic corrosion, was the only corrosion mechanism of concern for the canister. 3. The expected corrosion reactions would not generate significant quantities of hydrogen, because any water inside the fuel storage container is expected to have neutral pH (i.e., not acidic). Therefore, FSV concluded there were no safety implications associated with delaying the hydrogen test for one year. The licensee presented the same conclusions and observations in support of its April 2016 request to extend the testing date. The staff conducted its own evaluation of the data supporting FSV's March 2015 and April 2016 requests and found no safety implications associated with delaying the hydrogen test until December 2016. The staff made specific determinations concerning the safety of granting the exemption, including that the maximum hydrogen volume fraction is 7 percent inside the fuel storage container. Therefore, a fire or explosion of hydrogen at this level is very unlikely [[Page 40356]] and does not present a significant safety issue. The staff's calculation of the hydrogen volume fraction was a time independent calculation to determine the maximum hydrogen concentration assuming the possible reactants, oxygen and water, were fully consumed. A delay in performing the hydrogen test for six additional months will increase the container storage period from 25 years to 25.5 years without the performance of a hydrogen test. However, the staff finds that the extension will not increase the probability of either a hydrogen ignition event during storage or failure of the fuel storage container integrity due to corrosion, and therefore, fuel storage container safety is not reduced. The NRC staff concludes that hydrogen ignition events associated with handling fuel storage containers are very unlikely to occur because the Modular Vault Dry Store building where the fuel storage canisters are located contains no volatile materials or gases. A full discussion of this issue is found in FSV's SAR 3 (see ADAMS Accession No. ML102380351). The Component Operational Testing procedures in the Aging Management Program, which must be implemented after license renewal, are described in FSV's SAR (see ADAMS Accession No. ML103640385). These procedures eliminate hydrogen ignition sources by sampling and analyzing the air inside containers for the presence of hydrogen and purging hydrogen before moving or removing lids from containers holding spent fuel. Leakage Rate Limiting Condition of Operation 3.3.1 in Appendix A of License No. SNM-2504 states that the fuel storage containers seal leakage rate shall not exceed 1 x 10-\3\ ref-cm\3\/s. Surveillance Requirement 3.3.1.1 stipulates that one fuel storage container from each vault be subject to a leakage rate test every 5 years. The basis for SR 3.3.1.1 is that performance of a leakage rate test of at least six fuel storage containers every 5 years provides reasonable assurance of continued integrity. The original leakage rate test at FSV was performed in 1991 after the loading of canisters; subsequent leakage rate tests were performed on one fuel storage container from each vault in years 1996, 2001, 2005, and 2010. The results of all FSV's leakage rate tests have never exceeded the maximum rate of 1 x 10-\3\ ref- cm\3\/s. As part of its April 2016 exemption request, DOE evaluated whether the exemption is consistent with the confinement barrier requirements described in FSV's FSAR at 3.3.2.1 and in SR 3.3.1.1. The DOE classified the failure of the redundant metal O-ring seals in a fuel storage cylinder as a low probability event. In addition, Section 8.2.15 of the FSV FSAR identifies no credible failure mechanisms for the fuel storage container O-rings. The DOE calculated that in June 2017, the average and maximum O-ring seal leakage rates for fuel storage containers are expected to be 3.75 x 10-\4\ and 6.76 x 10-\4\ ref-cm\3\/s, respectively. These conservative calculations are presented in Engineering Design File-10727, Estimation of 2017 Leak Rates of Fort St. Vrain Fuel Storage Containers (ADAMS Accession No. ML15104A064). Both the average and maximum seal leakage rate values are below the maximum leakage rate of 1 x 10-\3\ ref-cm\3\/s, permitted by TS 3.3.1. The DOE identified O-ring failure as a potential failure mode that could result in leakage in excess of 1 x 10-\3\ ref-c cm\3\/s, although DOE did not provide specific details of potential O-ring failure mechanisms. The NRC staff's evaluation notes that typical failure modes for O- ring seals include: 1. Corrosion of the O-ring, 2. corrosion of the O-ring flange sealing surface (area in contact with the O-ring), and 3. creep or relaxation of the O-ring. The DOE's March 2015 exemption request, as supplemented on June 1, 2015 (ADAMS Accession No. ML15153A280), describes the O-rings as silver plated alloy X-750 in the work-hardened condition. The O-rings are installed with a grease/lubricant to facilitate sealing and prevent damage to the O-rings during lid installation and compression of the O- rings. The presence of grease, the construction materials used, and the limited amount of water in the vicinity of the O-rings reduce the likelihood of corrosion of the O-rings and the O-ring seal area on the fuel storage containers. The NRC staff reviewed the testing methods and the test pressures generated by previous leakage rate tests. In addition, the staff evaluated the correlations between leakage rate and pressure drop for the O-ring seals. These estimated O-ring seal leakage rates were reported in EDF-10727. The NRC staff determined that the data and correlations that DOE used accurately predict the June 2017 fuel storage container O-ring seal leakage rates. The staff confirmed that DOE's average and maximum 2017 leakage rate estimates of 3.75 x 10-\4\ and 6.76 x 10-\4\ ref-cm\3\/s are both acceptable and below the maximum limit of 1 x 10-\3\ ref- cm\3\/s in LCO 3.3.1. The NRC staff also reviewed Section 8.2.15 of FSV's FSAR and DOE's analyses of the consequences associated with a radiological release from a fuel storage container. The staff confirmed that even if the leakage rate of 1 x 10-\3\ ref-cm\3\/s were grossly exceeded, the consequences would be minimal. For example, 1. The radiological consequences at the controlled area boundary would be within the requirements of 10 CFR 72.106. 2. A radiological release with a leakage rate greater than 1 x 10-\3\ ref-cm\3\/s that passes beyond the redundant O-ring seals would be bounded by the maximum credible accident described in the FSV's FSAR at 8.2.15. 3. Furthermore, the failure of the redundant metallic seals (loss of confinement) is considered a low probability event during the entire storage period. Based on the findings discussed in this section, the NRC staff concludes that granting the DOE's exemption will not endanger public health and safety or the common defense and security. Delaying the fuel storage container O-ring leakage rate test required by TS 3.1.1 and the aging management monitoring of six fuel storage containers for hydrogen buildup until December 2016, will not increase the likelihood of a seal leak occurring. Therefore, the extension permitted by the current exemption does not change the licensing basis of the ISFSI design and it does not alter the staff's conclusion in June 2015, that the fuel storage container design and lid seals are acceptable. Otherwise in the Public Interest In the March 2016 exemption application, the DOE sought a delay of the fuel storage container O-ring leakage rate test and FSAR aging management surveillance for one year. The DOE explained that the extension would allow it to prioritize activities at the FSV site and reduce the administrative burden on the licensee and the NRC staff to perform the June 2016 test. The staff finds these statements are still valid and support a six-month extension, therefore issuance of the proposed exemption is otherwise in the public interest. Environmental Consideration The NRC staff evaluated whether significant environmental impacts are associated with the issuance of the requested exemption. The NRC staff determined that the proposed action fits a category of actions that does not require an environmental assessment or [[Page 40357]] environmental impact statement. The exemption meets the categorical exclusion criteria of 10 CFR 51.22(c)(25)(i)-(vi). Granting an exemption from the requirements of 10 CFR 72.44(c)(1) and 10 CFR 72.44(c)(3) will extend the time for DOE to conduct the inspection and surveillance of the fuel storage container O-ring leakage rate test required by TS 3.3.1 and the FSAR aging management surveillance of fuel storage containers for hydrogen buildup required by license Condition No. 9. A categorical exclusion for inspection and surveillance requirements is provided under 10 CFR 51.22(c)(25)(vi)(C), when the criteria in 10 CFR 51.22(c)(25)(i)-(v) are also satisfied. In its review of the exemption request, the NRC staff determined that, under 10 CFR 51.22(c)(25) granting the exemption: (i) Does not involve a significant hazards consideration because it does not reduce a margin of safety, create a new or different kind of accident not previously evaluated, or significantly increase the probability or consequences of an unevaluated accident; (ii) would not significantly change the types or amounts of effluents that may be released offsite because the exemption does not change or produce additional avenues of effluent release; (iii) would not significantly increase occupational or public radiation exposure, individually or cumulatively, because the exemption does not introduce new or increased radiological hazards; (iv) would not result in significant construction impacts because the exemption does not involve construction or other ground disturbing activities, or change the footprint of the existing ISFSI; and (v) would not increase the potential for or the consequences of radiological accidents. For example, a gross leak from a fuel storage container or excessive hydrogen buildup in a fuel storage container is unlikely because the exemption does not reduce the ability of the container to confine radioactive material or create new accident precursors at FSV's ISFSI. Accordingly, this exemption meets the eligibility criteria for categorical exclusion in 10 CFR 51.22(c)(25). There are no significant radiological environmental impacts associated with the proposed action. IV. Conclusions Accordingly, the NRC 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 NRC hereby grants DOE an exemption from the regulations at 10 CFR 72.44(c)(1) and 10 CFR 72.44(c)(3) to permit a delay by six months of the monitoring and surveillance scheduled for June 2016. The exemption extends the date for completion of the O-ring leakage rate test under SR 3.3.1.1 for one fuel storage container from each vault and the FSAR aging management inspection of FSCs for hydrogen until December 31, 2016. This exemption is effective as of June 21, 2016. Dated at Rockville, Maryland, this 15th day of June, 2016. For the Nuclear Regulatory Commission. John McKirgan, Chief, Spent Fuel Licensing Branch, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2016-14673 Filed 6-20-16; 8:45 am] BILLING CODE 7590-01-P
![40354 Federal Register / Vol. 81, No. 119 / Tuesday, June 21, 2016 / Notices
of Materials Research (DMR). With this reports contain similar information and to perform an O-ring leakage rate test
collaborative model PREMs build metrics as annual reports, but are required by Technical Specification (TS)
intellectual and physical infrastructure retrospective. 3.3.1 of Appendix A of Special Nuclear
within and between disciplines, Use of the Information: NSF will use Material License No. SNM–2504 and to
weaving together knowledge creation, the information to continue funding of perform an aging management
knowledge integration, and knowledge PREMs, and to evaluate the progress of surveillance described in the Fort St.
transfer. PREMs conduct world-class the program. Vrain (FSV) Final Safety Analysis
research through partnerships of Estimate of Burden: 25 hours per Report (FSAR). The DOE requests the
academic institutions, national PREM for 12 PREMs for a total of 300 dates for performance of the testing and
laboratories, industrial organizations, hours. surveillance requirements be extended
and/or other public/private entities. Respondents: Non-profit institutions. until December 2016. The NRC
New knowledge thus created is Estimated Number of Responses per previously granted DOE an exemption
meaningfully linked to society, with an Report: One from each of the twelve (80 FR 33299 dated, June 11, 2015)
emphasis on enhancing diversity. PREMs. extending the completion date for these
PREMs enable and foster excellent Comments: Comments are invited on actions until June 2016.
education, integrate research and (a) whether the proposed collection of DATES: The exemption is effective on
education, and create bonds between information is necessary for the proper June 21, 2016.
learning and inquiry so that discovery performance of the functions of the
ADDRESSES: Please refer to Docket ID
and creativity more fully support the Agency, including whether the
learning process. PREMs capitalize on NRC–2015–0150 when contacting the
information shall have practical utility;
diversity through participation and NRC about the availability of
(b) the accuracy of the Agency’s
collaboration in center activities and information regarding this document.
estimate of the burden of the proposed
demonstrate leadership in the You may obtain publicly-available
collection of information; (c) ways to
involvement of groups information related to this document
enhance the quality, utility, and clarity
underrepresented in science and using any of the following methods:
of the information on respondents, • Federal Rulemaking Web site: Go to
engineering. including through the use of automated
PREMs will be required to submit http://www.regulations.gov and search
collection techniques or other forms of for Docket ID NRC–2015–0150. Address
annual reports on progress and plans, information technology; and (d) ways to
which will be used as a basis for questions about NRC dockets to Carol
minimize the burden of the collection of Gallagher; telephone: 301–415–3463;
performance review and determining information on those who are to
the level of continued funding. To email: Carol.Gallagher@nrc.gov. For
respond, including through the use of technical questions, contact the
support this review and the appropriate automated, electronic,
management of the award PREMs will individual listed in the FOR FURTHER
mechanical, or other technological INFORMATION CONTACT section of this
be required to develop a set of collection techniques or other forms of
management and performance document.
information technology. • NRC’s Agencywide Documents
indicators for submission annually to
NSF via the Research Performance Dated: June 16, 2016. Access and Management System
Project Reporting module in Suzanne H. Plimpton, (ADAMS): You may obtain publicly-
Research.gov and an external technical Reports Clearance Officer, National Science available documents online in the
assistance contractor that collects Foundation. ADAMS Public Documents collection at
programmatic data electronically. These [FR Doc. 2016–14613 Filed 6–20–16; 8:45 am] http://www.nrc.gov/reading-rm/
indicators are both quantitative and BILLING CODE 7555–01–P adams.html. To begin the search, select
descriptive and may include, for ‘‘ADAMS Public Documents’’ and then
example, the characteristics of select ‘‘Begin Web-based ADAMS
personnel and students; sources of NUCLEAR REGULATORY Search.’’ For problems with ADAMS,
financial support and in-kind support; COMMISSION please contact the NRC’s Public
expenditures by operational component; Document Room (PDR) reference staff at
[Docket No. 72–09; NRC–2015–0150] 1–800–397–4209, 301–415–4737, or by
research activities; education activities;
patents, licenses; publications; degrees email to pdr.resource@nrc.gov. The
Independent Spent Fuel Storage
granted to students involved in PREM ADAMS accession number for each
Installation, Department of Energy;
activities; descriptions of significant document referenced (if it is available in
Fort St. Vrain
advances and other outcomes of the ADAMS) is provided the first time that
PREM effort. AGENCY: Nuclear Regulatory it is mentioned in this document.
Each PREM’s annual report will Commission. • NRC’s PDR: You may examine and
address the following categories of ACTION: Exemption; issuance. purchase copies of public documents at
activities: (1) Research, (2) education, the NRC’s PDR, Room O1–F21, One
(3) knowledge transfer, (4) partnerships, SUMMARY: The U.S. Nuclear Regulatory White Flint North, 11555 Rockville
(5) diversity, (6) management, and (7) Commission (NRC) is issuing an Pike, Rockville, Maryland 20852.
budget issues. exemption in response to a request FOR FURTHER INFORMATION CONTACT:
For each of the categories the report submitted by the Department of Energy Bernard White, Office of Nuclear
will describe overall objectives for the (DOE or the licensee) on April 27, 2016,
asabaliauskas on DSK3SPTVN1PROD with NOTICES
Material Safety and Safeguards, U.S.
year, problems the PREM has from NRC’s requirement to comply with Nuclear Regulatory Commission,
encountered in making progress towards the terms, conditions, and specifications Washington, DC 20555–0001; telephone:
goals, anticipated problems in the concerning testing and surveillance in 301–415–6577; email: Bernard.White@
following year, and specific outputs and Special Nuclear Material License No. nrc.gov.
outcomes. SNM–2504 for the Fort St. Vrain
PREMs are required to file a final independent spent fuel storage I. Background
report through the RPPR and external installation (ISFSI). The exemption The DOE is the holder of Special
technical assistance contractor. Final request seeks the extension of the time Nuclear Material License No. SNM–
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![Federal Register / Vol. 81, No. 119 / Tuesday, June 21, 2016 / Notices 40357
environmental impact statement. The from the regulations at 10 CFR (ADAMS): You may obtain publicly
exemption meets the categorical 72.44(c)(1) and 10 CFR 72.44(c)(3) to available documents online in the
exclusion criteria of 10 CFR permit a delay by six months of the ADAMS Public Documents collection at
51.22(c)(25)(i)–(vi). monitoring and surveillance scheduled http://www.nrc.gov/reading-rm/
Granting an exemption from the for June 2016. The exemption extends adams.html. To begin the search, select
requirements of 10 CFR 72.44(c)(1) and the date for completion of the O-ring ‘‘ADAMS Public Documents’’ and then
10 CFR 72.44(c)(3) will extend the time leakage rate test under SR 3.3.1.1 for one select ‘‘Begin Web-based ADAMS
for DOE to conduct the inspection and fuel storage container from each vault Search.’’ For problems with ADAMS,
surveillance of the fuel storage container and the FSAR aging management please contact the NRC’s Public
O-ring leakage rate test required by TS inspection of FSCs for hydrogen until Document Room (PDR) reference staff at
3.3.1 and the FSAR aging management December 31, 2016. This exemption is
surveillance of fuel storage containers 1–800–397–4209, 301–415–4737, or by
effective as of June 21, 2016. email to pdr.resource@nrc.gov. The
for hydrogen buildup required by
Dated at Rockville, Maryland, this 15th day ADAMS accession number for each
license Condition No. 9. A categorical of June, 2016.
exclusion for inspection and document referenced (if it is available in
For the Nuclear Regulatory Commission. ADAMS) is provided the first time that
surveillance requirements is provided
under 10 CFR 51.22(c)(25)(vi)(C), when John McKirgan, it is mentioned in this document.
Chief, Spent Fuel Licensing Branch, Division
the criteria in 10 CFR 51.22(c)(25)(i)–(v) • NRC’s PDR: You may examine and
are also satisfied. In its review of the of Spent Fuel Management, Office of Nuclear
Material Safety and Safeguards. purchase copies of public documents at
exemption request, the NRC staff the NRC’s PDR, Room O1–F21, One
determined that, under 10 CFR [FR Doc. 2016–14673 Filed 6–20–16; 8:45 am]
White Flint North, 11555 Rockville
51.22(c)(25) granting the exemption: (i) BILLING CODE 7590–01–P
Pike, Rockville, Maryland 20852.
Does not involve a significant hazards
consideration because it does not reduce FOR FURTHER INFORMATION CONTACT:
a margin of safety, create a new or NUCLEAR REGULATORY Adrian Muñiz, Office of New Reactors,
different kind of accident not previously COMMISSION U.S. Nuclear Regulatory Commission,
evaluated, or significantly increase the [Docket No. 52–036; NRC–2008–0616] Washington, DC 20555–0001; telephone:
probability or consequences of an 301–415–4093; email: Adrian.Muniz@
unevaluated accident; (ii) would not Entergy Operations, Inc., River Bend nrc.gov.
significantly change the types or Station, Unit 3
amounts of effluents that may be SUPPLEMENTARY INFORMATION: A notice
AGENCY: Nuclear Regulatory of receipt and availability of this
released offsite because the exemption
Commission.
does not change or produce additional application was previously published in
avenues of effluent release; (iii) would ACTION: Application for combined the Federal Register on November 17,
not significantly increase occupational license; withdrawal. 2008 (73 FR 67895). On December 10,
or public radiation exposure, SUMMARY: The U.S. Nuclear Regulatory 2008 (73 FR 75141), a subsequent notice
individually or cumulatively, because Commission (NRC) is withdrawing an was published in the Federal Register
the exemption does not introduce new application for a combined license announcing the acceptance of the RBS3
or increased radiological hazards; (iv) (COL) for a single unit of the Economic COL application for docketing in
would not result in significant Simplified Boiling-Water Reactor. This accordance with part 2 of title 10 of the
construction impacts because the reactor would be identified as River Code of Federal Regulations (10 CFR),
exemption does not involve Bend Station, Unit 3 (RBS3) and would ‘‘Agency Rules of Practice and
construction or other ground disturbing be located at the current River Bend Procedure,’’ and 10 CFR part 52,
activities, or change the footprint of the
Nuclear Station site near St. ‘‘Licenses, Certifications, and Approvals
existing ISFSI; and (v) would not
Francisville, Louisiana in West for Nuclear Power Plants.’’ The docket
increase the potential for or the
Feliciana Parish. number established for this application
consequences of radiological accidents.
For example, a gross leak from a fuel DATES: The effective date of the is 52–036.
storage container or excessive hydrogen withdrawal of the application for By letter dated January 9, 2009,
buildup in a fuel storage container is combined license is June 21, 2016. Entergy Operations, Inc. (EOI) requested
unlikely because the exemption does ADDRESSES: Please refer to Docket ID that the NRC temporarily suspend the
not reduce the ability of the container to NRC–2008–0616 when contacting the COL application review, including any
confine radioactive material or create NRC about the availability of supporting reviews by external agencies,
new accident precursors at FSV’s ISFSI. information regarding this document. until further notice (ADAMS Accession
Accordingly, this exemption meets the You may obtain publicly-available No. ML090130174). The NRC granted
eligibility criteria for categorical information related to this action by the
the suspension request (ADAMS
exclusion in 10 CFR 51.22(c)(25). There following methods:
• Federal Rulemaking Web site: Go to Accession No. ML090080277). By letter
are no significant radiological
http://www.regulations.gov and search dated December 4, 2015, EOI requested
environmental impacts associated with
for Docket ID NRC–2008–0616. Address the NRC to withdraw the RBS3 COL
the proposed action.
questions about NRC dockets to Carol application from the docket (ADAMS
asabaliauskas on DSK3SPTVN1PROD with NOTICES
IV. Conclusions Gallagher; telephone: 301–415–3463; Accession No. ML15338A298). Pursuant
Accordingly, the NRC has determined email: Carol.Gallagher@nrc.gov. For to the requirements in 10 CFR part 2,
that, pursuant to 10 CFR 72.7, this technical questions, contact the the Commission grants EOI its request to
exemption is authorized by law, will not individual listed in the FOR FURTHER withdraw the RBS3 COL application.
endanger life or property or the common INFORMATION CONTACT section of this Dated at Rockville, Maryland, this 14th day
defense and security, and is otherwise document. of June, 2016.
in the public interest. Therefore, the • NRC’s Agencywide Documents
NRC hereby grants DOE an exemption Access and Management System
VerDate Sep<11>2014 18:37 Jun 20, 2016 Jkt 238001 PO 00000 Frm 00099 Fmt 4703 Sfmt 4703 E:\FR\FM\21JNN1.SGM 21JNN1](https://thefederalregister.org/doc/81_FR_40473/page/4.svg)
Document Created: 2016-06-21 01:30:46
Document Modified: 2016-06-21 01:30:46
| 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 is effective on June 21, 2016. | |
| Contact | Bernard White, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-6577; email: [email protected] | |
| FR Citation | 81 FR 40354 |
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