82 FR 22862 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit No. 3; Use of AXIOM Fuel Rod Cladding Material
NUCLEAR REGULATORY COMMISSION Federal Register Volume 82, Issue 95 (May 18, 2017)
Federal Register Volume 82, Issue 95 (May 18, 2017)
| Page Range | 22862-22865 | |
| FR Document | 2017-10073 |
[Federal Register Volume 82, Number 95 (Thursday, May 18, 2017)] [Notices] [Pages 22862-22865] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2017-10073] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket No. 50-423; NRC-2017-0118] Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit No. 3; Use of AXIOM Fuel Rod Cladding Material AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a June 30, 2016, request, as supplemented by letter dated March 27, 2017, from Dominion Nuclear Connecticut, Inc. (DNC or the licensee) in order to use AXIOM fuel rod cladding material at Millstone Power Station, Unit No. 3 (MPS-3). DATES: The exemption was issued on May 10, 2017. ADDRESSES: Please refer to Docket ID NRC-2017-0118 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-2017-0118. 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: Richard V. Guzman, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-1030, email: [email protected]. SUPPLEMENTARY INFORMATION: I. Background Dominion Nuclear Connecticut, Inc. is the holder of Renewed Facility Operating License No. NPF-49, which authorizes operation of MPS-3, a pressurized-water reactor. The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the NRC now or hereafter in effect. Millstone Power Station, Unit No. 3, shares the site with Millstone Power Station, Unit No. 1, a permanently defueled boiling water reactor nuclear unit, and Millstone Power Station, Unit No. 2, a pressurized-water reactor. The facility is located in Waterford, Connecticut, approximately 2.3 miles southwest of New London, Connecticut. This exemption applies to MSP-3 only. The other Millstone Power Station units, No. 1 and No. 2, are not covered by this exemption. II. Request/Action Pursuant to Sec. 50.12 of title 10 of the Code of Federal Regulations (10 CFR), ``Specific exemptions,'' the licensee requested, by letter dated June 30, 2016 (ADAMS Accession No. ML16189A104), as supplemented by letter dated March 27, 2017 (ADAMS Accession No. ML17090A428), an exemption from Sec. 50.46, ``Acceptance criteria for emergency core cooling systems [ECCS] for light-water nuclear power reactors,'' and 10 CFR part 50, appendix K, ``ECCS Evaluation Models,'' to allow the use of fuel rod cladding with AXIOM alloy for future reload applications. The regulations in Sec. 50.46 contain acceptance criteria for the ECCS for reactors fueled with Zircaloy or ZIRLOTM fuel rod cladding material. In addition, 10 CFR part 50, appendix K, requires that the Baker-Just equation be used to predict the rates of energy release, hydrogen concentration, and cladding oxidation from the metal/water reaction. The Baker-Just equation assumes the use of a zirconium alloy, which is a material different from AXIOM. Therefore, the strict application [[Page 22863]] of these regulations does not permit the use of fuel rod cladding material other than Zircaloy or ZIRLOTM. Because the material specifications of AXIOM differ from the specificaitons for Zircaloy or ZIRLOTM, and the regulations specify a cladding material other than AXIOM, a plant-specific exemption is required to allow the use of, and application of these regulations to, AXIOM at MPS-3. The exemption request relates solely to the cladding material specified in these regulations (i.e., fuel rods with Zircaloy or ZIRLOTM cladding material). This exemption would allow application of the acceptance criteria of Sec. 50.46 and appendix K to 10 CFR part 50, for fuel assembly designs using AXIOM fuel rod cladding material. The licensee is not seeking an exemption from the acceptance and analytical criteria of these regulations. The intent of the request is to allow the use of the criteria set forth in these regulations for application of the AXIOM fuel road cladding material at MPS-3. III. Discussion Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR part 50 when: (1) The exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. Under Sec. 50.12(a)(2), special circumstances include, among other things, when application of the specific regulation in the particular circumstance would not serve, or is not necessary to achieve, the underlying purpose of the rule. A. Authorized by Law This exemption would allow the use of AXIOM fuel rod cladding material for future reload applications at MPS-3. As stated above, 10 CFR 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR part 50. The NRC staff has determined that special circumstances exist to grant the requested exemption and that granting the licensee's requested exemption would not result in a violation of the Atomic Energy Act of 1954, as amended, or the Commission's regulations. Therefore, the exemption is authorized by law. B. No Undue Risk to Public Health and Safety Section 50.46 requires that each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical Zircaloy or ZIRLOTM cladding must be provided with an ECCS that must be designed so that its calculated cooling performance following a postulated loss-of-coolant accident (LOCA) conforms to the criteria set forth in Sec. 50.46(b). The underlying purpose of Sec. 50.46 is to establish acceptance criteria for adequate ECCS performance in response to LOCAs. The licensee states that there will be up to eight lead test assemblies (LTAs) containing fuel rods fabricated with AXIOM cladding inserted into the core for MPS-3, Cycle 19. These LTAs will be placed in non-limiting locations. Westinghouse performed preliminary high temperature steam oxidation tests on AXIOM cladding and confirmed that AXIOM cladding exhibits a ductile response to ring compression tests for peak cladding temperature and equivalent cladding reacted values up to and beyond the Sec. Sec. 50.46(b)(1) and (b)(2) acceptance criteria, therefore satisfying the underlying cladding performance metric used to judge ECCS performance. This evidence supports the use of the existing acceptance criteria for fuel rods fabricated with AXIOM cladding. Paragraph I.A.5 of appendix K to 10 CFR part 50 states that the rates of energy, hydrogen concentration, and cladding oxidation from the metal-water reaction shall be calculated using the Baker-Just equation. Since the Baker-Just equation presumes the use of Zircaloy clad fuel, strict application of the rule would not permit use of the equation for AXIOM cladding. The Baker-Just equation predicts conservatively high oxidation rates compared with modern correlations (i.e., Cathcart-Pawell) and has been shown to remain conservative and applicable for many modern zirconium alloys. The licensee provided the nominal alloying composition for ZIRLOTM, Optimized ZIRLOTM, and AXIOM cladding material. The licensee provided evidence that the Baker-Just equation conservatively predicts the rate of energy release, hydrogen generation, and cladding oxidation for the AXIOM material. Based upon similar material composition, the high temperature metal-water reaction rates are expected to be similar, and the continued use of the Baker-Just equation is judged by the NRC staff to be acceptable. Additionally, the licensee performs cycle-specific reload evaluations to assure that Sec. 50.46 acceptance criteria are satisfied and will include the LTAs in such analysis. Therefore, the NRC staff determined that the application of paragraph I.A.5 of 10 CFR part 50, appendix K, related to cladding material is not necessary to achieve the underlying purpose of the rule in these circumstances. Since these evaluations demonstrate that the underlying purpose of the rule will be met, there will be no undue risk to the public health and safety. Based on the regulatory review of the exemption request, the NRC staff concludes that the intent of Sec. 50.46 and 10 CFR part 50, appendix K, will continue to be satisfied for the planned operation of MPS-3 with Westinghouse AXIOM fuel cladding and fuel assembly material used for non-limiting LTAs. C. Consistent With the Common Defense and Security The licensee's exemption request is to allow the application of the aforementioned regulations to an improved fuel rod cladding material. In its letter dated June 30, 2016, the licensee stated that all the requirements and acceptance criteria will be maintained. The licensee is required to handle and control special nuclear material in these assemblies in accordance with its approved procedures. The use of LTAs with AXIOM fuel rod cladding in the MPS-3 core is not related to and does not raise security issues. Therefore, the NRC staff has determined that this exemption does not impact common defense and security. D. Special Circumstances Special circumstances, in accordance with Sec. 50.12(a)(2)(ii), are present whenever application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule. The underlying purpose of Sec. 50.46 and 10 CFR part 50, appendix K, is to establish acceptance criteria for ECCS performance to provide reasonable assurance of safety in the event of a LOCA. The regulations in Sec. 50.46 and 10 CFR part 50, appendix K, are not directly applicable to AXIOM, even though the evaluations described in the following sections of this exemption show that the intent of the regulation is met. Therefore, since the underlying purposes of Sec. 50.46 and 10 CFR part 50, appendix K, are achieved through the use of AXIOM fuel rod cladding material, the special circumstances required by Sec. 50.12(a)(2)(ii) for the granting of an exemption exist. E. Environmental Considerations The NRC staff determined that the exemption discussed herein meets the eligibility criteria for the categorical exclusion set forth in Sec. 51.22(c)(9) because it is related to a requirement concerning the installation or use of a facility component located within the [[Page 22864]] restricted area, as defined in 10 CFR part 20, and the granting of this exemption involves: (i) No significant hazards consideration, (ii) no significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, and (iii) no significant increase in individual or cumulative occupational radiation exposure. Therefore, in accordance with Sec. 51.22(b), no environmental impact statement or environmental assessment need to be prepared in connection with the NRC's consideration of this exemption request. The basis for the NRC staff's determination is discussed as follows with an evaluation against each of the requirements in Sec. 51.22(c)(9). Requirements in Sec. 51.22(c)(9)(i) The NRC staff evaluated the issue of no significant hazards consideration, using the standards described in Sec. 50.92(c), as presented below: 1. Does the proposed exemption involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed exemption would allow DNC to insert up to eight LTAs with AXIOM fuel rod cladding at MPS-3. The proposed exemption from the requirements of Sec. 50.46 and 10 CFR part 50, appendix K, to permit the use of the AXIOM cladding material in the MPS-3 core does not adversely affect any fission product barrier, nor does it alter the safety function of safety systems, structures, or components, or their roles in accident prevention or mitigation. AXIOM cladding material is not an accident initiator. The response of the fuel to an accident is analyzed using conservative techniques, and the results are compared to NRC-approved acceptance criteria. Reload specific analyses conducted by DNC and the fuel vendor demonstrate that the design limits of the fuel cladding are met. Station operation and analysis will continue to be in compliance with NRC regulations. Westinghouse will perform a cycle- specific analysis of the MPS-3 core using LOCA methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Therefore, the plant will continue to meet applicable design criteria and safety analysis acceptance criteria. Consequently, permitting the insertion of up to eight LTAs with AXIOM fuel rod cladding in the MPS-3 core does not affect the probability of an accident or the consequences thereof. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed exemption create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed exemption from the requirements of Sec. 50.46 and 10 CFR part 50, appendix K, does not impact the plant configuration or system performance. The proposed exemption does not modify any interfaces with existing equipment, change the equipment's function, or change the method of operating the equipment. Use of the AXIOM fuel rod cladding material in the MPS-3 core does not adversely affect any fission product barrier, nor does it alter the safety function of safety systems, structures, or components, or their roles in accident prevention or mitigation. Westinghouse will perform a cycle-specific analysis of the MPS-3 core using LOCA methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Prior to each cycle, the AXIOM LTAs will be evaluated to ensure that current design criteria are met for the projected burnup. Current NRC-approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior. If any current design criteria are not met, the LTAs with AXIOM fuel rod cladding will not be inserted into the core. The proposed exemption assures there is adequate margin available to meet safety analysis criteria and does not introduce any failure modes, accident initiators, or equipment malfunctions that would cause a new or different kind of accident. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed exemption involve a significant reduction in a margin of safety? Response: No. The proposed exemption from the requirements of Sec. 50.46 and 10 CFR part 50, appendix K, does not impact the plant configuration or system performance, and use of the AXIOM cladding material in the MPS-3 core does not adversely affect any fission product barrier. Current NRC-approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior to ensure the plant continues to meet applicable design criteria and safety analysis acceptance criteria. The proposed exemption does not alter the manner in which safety limits, limiting safety system settings, or limiting conditions for operation are determined, and the dose analysis acceptance criteria are not affected. The proposed exemption does not result in plant operation in a configuration outside the analysis or design basis and does not adversely affect systems that respond to safely shut down the plant and maintain the plant in a safe shutdown condition. Westinghouse will perform a cycle-specific analysis of the MPS-3 core using LOCA methods approved for the site to ensure that assemblies with AXIOM fuel rod cladding material meet the LOCA safety criteria. Prior to each cycle, the AXIOM LTAs will be evaluated to ensure that current design criteria are met for the projected burnup. Current NRC-approved models will be conservatively applied to bound AXIOM cladding material properties and expected behavior. If any current design criteria are not met, the AXIOM cladding LTAs will not be inserted into the core. Therefore, the proposed change does not involve a significant reduction in a margin of safety. Based on the above, the NRC staff concludes that the proposed exemption presents no significant hazards consideration under the standards set forth in Sec. 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified (i.e., satisfies the provisions of Sec. 51.22(c)(9)(i)). Requirements in Sec. 51.22(c)(9)(ii) The proposed exemption would allow the use of AXIOM fuel rod cladding material in the MPS-3 reactor. AXIOM material has essentially the same properties as the currently licensed Optimized ZIRLOTM cladding and standard ZIRLOTM alloys. The use of the AXIOM fuel rod cladding material will not significantly change the types of effluents that may be released offsite or significantly increase the amount of effluents that may be released offsite. Therefore, the provisions of Sec. 51.22(c)(9)(ii) are satisfied. Requirements in Sec. 51.22(c)(9)(iii) The proposed exemption would allow the use of AXIOM fuel rod cladding material in the reactors. AXIOM material has essentially the same properties as the currently licensed Optimized ZIRLOTM cladding and standard ZIRLOTM alloys. The use of the AXIOM fuel rod cladding material will not significantly increase individual occupational radiation exposure or significantly increase cumulative occupational radiation exposure. Therefore, the provisions of Sec. 51.22(c)(9)(iii) are satisfied. [[Page 22865]] Conclusion Based on the above, the NRC staff concludes that the proposed exemption meets the eligibility criteria for the categorical exclusion set forth in Sec. 51.22(c)(9). Therefore, in accordance with Sec. 51.22(b), no environmental impact statement or environmental assessment need to be prepared in connection with the NRC's proposed issuance of this exemption. IV. Conclusion Accordingly, the Commission has determined that pursuant to 10 CFR 50.12, the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. Also, special circumstances are present. Therefore, the Commission hereby grants DNC an exemption from the requirements of 10 CFR 50.46 and appendix K of 10 CFR part 50, to allow the use of AXIOM fuel rod cladding material at MPS-3. As stated above, this exemption relates solely to the cladding material specified in these regulations. Dated at Rockville, Maryland, this 10th day of May 2017. For the Nuclear Regulatory Commission. MaryJane Ross-Lee, Acting Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2017-10073 Filed 5-17-17; 8:45 am] BILLING CODE 7590-01-P
![22862 Federal Register / Vol. 82, No. 95 / Thursday, May 18, 2017 / Notices
not impact remaining decommissioning Dated at Rockville, Maryland, this 10th day ADAMS) is provided the first time that
activities; plant operations, of May 2017. it is mentioned in this document.
configuration, and/or radiological For the Nuclear Regulatory Commission. • NRC’s PDR: You may examine and
effluents; or nuclear security. The NRC John R. Tappert, purchase copies of public documents at
has determined that the destruction of Director, Division of Decommissioning, the NRC’s PDR, Room O1–F21, One
the identified records does not involve Uranium Recovery and Waste Programs, White Flint North, 11555 Rockville
information or activities that could Office of Nuclear Material Safety and Pike, Rockville, Maryland 20852.
potentially impact the common defense Safeguards.
FOR FURTHER INFORMATION CONTACT:
and security of the United States. [FR Doc. 2017–10071 Filed 5–17–17; 8:45 am]
Richard V. Guzman, Office of Nuclear
BILLING CODE 7590–01–P
The purpose for the record keeping Reactor Regulation, U.S. Nuclear
regulations is to assist the NRC in Regulatory Commission, Washington DC
carrying out its mission to protect the 20555–0001; telephone: 301–415–1030,
NUCLEAR REGULATORY
public health and safety by ensuring email: Richard.Guzman@nrc.gov.
COMMISSION
that the licensing and design basis of the SUPPLEMENTARY INFORMATION:
facility is understood, documented, [Docket No. 50–423; NRC–2017–0118]
preserved and retrievable in such a way I. Background
that will aid the NRC in determining Dominion Nuclear Connecticut, Inc.; Dominion Nuclear Connecticut, Inc. is
compliance and noncompliance, taking Millstone Power Station, Unit No. 3; the holder of Renewed Facility
action on possible noncompliance, and Use of AXIOM Fuel Rod Cladding Operating License No. NPF–49, which
examining facts following an incident. Material authorizes operation of MPS–3, a
Since the HBPP–3 SSCs that were AGENCY: Nuclear Regulatory pressurized-water reactor. The license
safety-related or important to safety Commission. provides, among other things, that the
during operations have been removed ACTION: Exemption; issuance. facility is subject to all rules,
from the licensing basis and removed regulations, and orders of the NRC now
from the plant, the staff finds that the SUMMARY: The U.S. Nuclear Regulatory or hereafter in effect. Millstone Power
records associated with the HBPP–3 Commission (NRC) is issuing an Station, Unit No. 3, shares the site with
licensing basis requirements previously exemption in response to a June 30, Millstone Power Station, Unit No. 1, a
applicable to the nuclear power unit, 2016, request, as supplemented by letter permanently defueled boiling water
safe storage of fuel in the SFP and dated March 27, 2017, from Dominion reactor nuclear unit, and Millstone
associated SSCs that no longer remain Nuclear Connecticut, Inc. (DNC or the Power Station, Unit No. 2, a
on site will no longer be required to licensee) in order to use AXIOM fuel pressurized-water reactor. The facility is
achieve the underlying purpose of the rod cladding material at Millstone located in Waterford, Connecticut,
records retention rule. Power Station, Unit No. 3 (MPS–3). approximately 2.3 miles southwest of
Accordingly, the Commission has DATES: The exemption was issued on New London, Connecticut. This
determined that, pursuant to 10 CFR May 10, 2017. exemption applies to MSP–3 only. The
50.12, the exemption is authorized by ADDRESSES: Please refer to Docket ID other Millstone Power Station units, No.
law, will not present an undue risk to NRC–2017–0118 when contacting the 1 and No. 2, are not covered by this
the public health and safety, and is NRC about the availability of exemption.
consistent with the common defense information regarding this document. II. Request/Action
and security, and that special You may obtain publicly-available
circumstances are present. Therefore, information related to this document Pursuant to § 50.12 of title 10 of the
the Commission hereby grants Pacific using any of the following methods: Code of Federal Regulations (10 CFR),
Gas and Electric Company a one-time • Federal Rulemaking Web site: Go to ‘‘Specific exemptions,’’ the licensee
partial exemption from the record http://www.regulations.gov and search requested, by letter dated June 30, 2016
keeping requirements of 10 CFR for Docket ID NRC–2017–0118. Address (ADAMS Accession No. ML16189A104),
50.71(c); 10 CFR part 50, appendix B, questions about NRC dockets to Carol as supplemented by letter dated March
Criterion XVII; and 10 CFR 50.59(d)(3) Gallagher; telephone: 301–415–3463; 27, 2017 (ADAMS Accession No.
for the Humboldt Bay Power Plant, Unit email: Carol.Gallagher@nrc.gov. For ML17090A428), an exemption from
3, to allow removal of records associated technical questions, contact the § 50.46, ‘‘Acceptance criteria for
with the HBPP–3 licensing basis individual listed in the FOR FURTHER emergency core cooling systems [ECCS]
requirements previously applicable to INFORMATION CONTACT section of this for light-water nuclear power reactors,’’
the nuclear power unit, safe storage of document. and 10 CFR part 50, appendix K, ‘‘ECCS
fuel in the SFP and associated SSCs that • NRC’s Agencywide Documents Evaluation Models,’’ to allow the use of
no longer remain on site. Access and Management System fuel rod cladding with AXIOM alloy for
(ADAMS): You may obtain publicly- future reload applications. The
Records associated with residual available documents online in the regulations in § 50.46 contain
radiological activity and with ADAMS Public Documents collection at acceptance criteria for the ECCS for
programmatic controls necessary to http://www.nrc.gov/reading-rm/ reactors fueled with Zircaloy or
support decommissioning, such as adams.html. To begin the search, select ZIRLOTM fuel rod cladding material. In
security, emergency planning, spent fuel ‘‘ADAMS Public Documents’’ and then addition, 10 CFR part 50, appendix K,
management and quality assurance are select ‘‘Begin Web-based ADAMS requires that the Baker-Just equation be
jstallworth on DSK7TPTVN1PROD with NOTICES
not affected by the exemption request Search.’’ For problems with ADAMS, used to predict the rates of energy
and are required to be retained please contact the NRC’s Public release, hydrogen concentration, and
consistent with existing requirements as Document Room (PDR) reference staff at cladding oxidation from the metal/water
decommissioning records until the 1–800–397–4209, 301–415–4737, or by reaction. The Baker-Just equation
termination of the HBPP–3 license. email to pdr.resource@nrc.gov. The assumes the use of a zirconium alloy,
This exemption is effective upon ADAMS accession number for each which is a material different from
issuance. document referenced (if it is available in AXIOM. Therefore, the strict application
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![Federal Register / Vol. 82, No. 95 / Thursday, May 18, 2017 / Notices 22865
Conclusion • Federal Rulemaking Web site: Go to • NRC’s PDR: You may examine and
Based on the above, the NRC staff http://www.regulations.gov and search purchase copies of public documents at
concludes that the proposed exemption for Docket ID NRC–2016–0156. Address the NRC’s PDR, Room O1–F21, One
meets the eligibility criteria for the questions about NRC dockets to Carol White Flint North, 11555 Rockville
categorical exclusion set forth in Gallagher; telephone: 301–415–3463; Pike, Rockville, Maryland 20852.
§ 51.22(c)(9). Therefore, in accordance email: Carol.Gallagher@nrc.gov. For • NRC’s Clearance Officer: A copy of
with § 51.22(b), no environmental technical questions, contact the the collection of information and related
impact statement or environmental individual listed in the FOR FURTHER instructions may be obtained without
assessment need to be prepared in INFORMATION CONTACT section of this charge by contacting NRC’s Clearance
connection with the NRC’s proposed document. Officer, David Cullison, Office of the
issuance of this exemption. • Mail comments to: David Cullison, Chief Information Officer, U.S. Nuclear
Office of the Chief Information Officer, Regulatory Commission, Washington,
IV. Conclusion Mail Stop: T–5 F53, U.S. Nuclear DC 20555–0001; telephone: 301–415–
Accordingly, the Commission has Regulatory Commission, Washington, 2084; email: INFOCOLLECTS.Resource@
determined that pursuant to 10 CFR DC 20555–0001. nrc.gov.
50.12, the exemption is authorized by For additional direction on obtaining B. Submitting Comments
law, will not present an undue risk to information and submitting comments,
the public health and safety, and is see ‘‘Obtaining Information and Please include Docket ID NRC–2016–
consistent with the common defense Submitting Comments’’ in the 0156 in the subject line of your
and security. Also, special SUPPLEMENTARY INFORMATION section of comment submission, in order to ensure
circumstances are present. Therefore, this document. that the NRC is able to make your
the Commission hereby grants DNC an FOR FURTHER INFORMATION CONTACT:
comment submission available to the
exemption from the requirements of 10 David Cullison, Office of the Chief public in this docket.
CFR 50.46 and appendix K of 10 CFR Information Officer, U.S. Nuclear The NRC cautions you not to include
part 50, to allow the use of AXIOM fuel Regulatory Commission, Washington, identifying or contact information in
rod cladding material at MPS–3. As DC 20555–0001; telephone: 301–415– comment submissions that you do not
stated above, this exemption relates 2084; email: INFOCOLLECTS.Resource@ want to be publicly disclosed in your
solely to the cladding material specified nrc.gov. comment submission. All comment
in these regulations. submissions are posted at http://
SUPPLEMENTARY INFORMATION:
Dated at Rockville, Maryland, this 10th day
www.regulations.gov and entered into
of May 2017. I. Obtaining Information and ADAMS. Comment submissions are not
For the Nuclear Regulatory Commission. Submitting Comments routinely edited to remove identifying
or contact information.
MaryJane Ross-Lee, A. Obtaining Information If you are requesting or aggregating
Acting Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor Please refer to Docket ID NRC–2016– comments from other persons for
Regulation. 0156 when contacting the NRC about submission to the NRC, then you should
[FR Doc. 2017–10073 Filed 5–17–17; 8:45 am]
the availability of information for this inform those persons not to include
action. You may obtain publicly- identifying or contact information that
BILLING CODE 7590–01–P
available information related to this they do not want to be publicly
action by any of the following methods: disclosed in their comment submission.
NUCLEAR REGULATORY • Federal Rulemaking Web site: Go to Your request should state that comment
COMMISSION http://www.regulations.gov and search submissions are not routinely edited to
for Docket ID NRC–2016–0156. A copy remove such information before making
[NRC–2016–0156] of the collection of information and the comment submissions available to
related instructions may be obtained the public or entering the comment into
Information Collection: Solicitation of ADAMS.
without charge by accessing Docket ID
Non-Power Reactor Operator
NRC–2016–0156 on this Web site. II. Background
Licensing Examination Data
• NRC’s Agencywide Documents
AGENCY: Nuclear Regulatory Access and Management System In accordance with the Paperwork
Commission. (ADAMS): You may obtain publicly- Reduction Act of 1995 (44 U.S.C.
ACTION: Proposed information available documents online in the Chapter 35), the NRC is requesting
collection; request for comment. ADAMS Public Documents collection at public comment on its intention to
http://www.nrc.gov/reading-rm/ request the OMB’s approval for the
SUMMARY: The U.S. Nuclear Regulatory adams.html. To begin the search, select information collection summarized
Commission (NRC) invites public ‘‘ADAMS Public Documents’’ and then below.
comment on this proposed collection of select ‘‘Begin Web-based ADAMS 1. The title of the information
information. The information collection Search.’’ For problems with ADAMS, collection: Solicitation of Non-Power
is entitled, ‘‘Solicitation of Non-Power please contact the NRC’s Public Reactor Operator Licensing Examination
Reactor Operator Licensing Examination Document Room (PDR) reference staff at Data.
Data.’’ 1–800–397–4209, 301–415–4737, or by 2. OMB approval number: An OMB
DATES: Submit comments by July 17, email to pdr.resource@nrc.gov. A copy control number has not yet been
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2017. Comments received after this date of the collection of information and assigned to this proposed information
will be considered if it is practical to do related instructions may be obtained collection.
so, but the Commission is able to ensure without charge by accessing ADAMS 3. Type of submission: New.
consideration only for comments Accession No. ML17011A068. The 4. The form number, if applicable:
received on or before this date. supporting statement is available in Not applicable.
ADDRESSES: You may submit comments ADAMS under Accession No. 5. How often the collection is required
by any of the following methods: ML17011A063. or requested: Annually.
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Document Created: 2017-05-18 01:20:33
Document Modified: 2017-05-18 01:20:33
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| 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 May 10, 2017. | |
| Contact | Richard V. Guzman, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-1030, email: [email protected] | |
| FR Citation | 82 FR 22862 |
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