80 FR 15634 - Entergy Operations, Inc., Arkansas Nuclear One, Unit 1
NUCLEAR REGULATORY COMMISSION Federal Register Volume 80, Issue 56 (March 24, 2015)
Federal Register Volume 80, Issue 56 (March 24, 2015)
| Page Range | 15634-15638 | |
| FR Document | 2015-06700 |
[Federal Register Volume 80, Number 56 (Tuesday, March 24, 2015)] [Notices] [Pages 15634-15638] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2015-06700] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket No. 50-313; NRC-2015-0069] Entergy Operations, Inc., Arkansas Nuclear One, Unit 1 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a March 20, 2014, request from Entergy Operations, Inc. (Entergy or the licensee), from the requirements to use Charpy V-notch (CV ) and drop weight-based methodology to determine initial nil-ductility reference temperature (RTNDT ) for use in evaluating the integrity of Linde 80 weld materials in the reactor pressure vessel (RPV) beltline at Arkansas Nuclear One (ANO), Unit 1. This exemption would allow the licensee to use an alternate methodology to incorporate fracture toughness test data to determine RTNDT values for use in the evaluation of the RPV beltline weld material integrity in support of the development of updated pressure-temperature limit curves. DATES: March 24, 2015. ADDRESSES: Please refer to Docket ID NRC-2015-0069 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: [[Page 15635]]Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0069. 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 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: Andrea George, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1081, email: [email protected]. SUPPLEMENTARY INFORMATION: I. Background Entergy is the holder of renewed Facility Operating License No. DPR-51, that authorizes operation of ANO, Unit 1. 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. The ANO facility consists of two pressurized-water reactors, Units 1 and 2, located in Pope County, Arkansas. II. Request/Action Part 50 of title 10 of the Code of Federal Regulation (10 CFR), appendix G, ``Fracture Toughness Requirements,'' specifies fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary of light water reactors to provide adequate margins of safety during any condition of normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected to over its service lifetime. Section 50.61, ``Fracture toughness requirements for protection against pressurized thermal shock [PTS] events,'' provides fracture toughness requirements for protection against PTS events. A PTS event is an event or transient in pressurized water reactors (PWRs) causing severe overcooling (thermal shock) concurrent with or followed by significant pressure in the reactor vessel. Pursuant to 10 CFR 50.12, ``Specific exemptions,'' by letter dated March 20, 2014 (ADAMS Accession No. ML14083A640), as supplemented by letter dated June 26, 2014 (ADAMS Accession No. ML14177A302), the licensee requested an exemption from certain requirements of 10 CFR part 50, appendix G, and 10 CFR 50.61, to revise certain ANO, Unit 1 RPV initial (unirradiated) properties using AREVA Topical Report (TR) BAW-2308, Revisions 1-A and 2-A, ``Initial RTNDT [nil-ductility reference temperature] of Linde 80 Weld Materials.'' Specifically, the licensee requested an exemption from 10 CFR part 50, appendix G.II.D(i), which requires that licensees evaluate the pre- service or unirradiated RT NDT according to the procedures in the American Society of Mechanical Engineers (ASME) Code, Paragraph NB- 2331, ``Material for Vessels.'' The ASME Code Paragraph NB-2331 requires that licensees use Charpy V-notch (CV ) and drop weight-based methodology to derive the initial RTNDT values. In lieu of the existing methodology described above, the licensee requested to use the alternate methodology in TR BAW-2308, Revisions 1- A and 2-A, to incorporate the use of fracture toughness test data for evaluating the integrity of the ANO, Unit 1, Linde 80 weld materials in the RPV beltline. The methodology in TR BAW-2308, Revisions 1-A and 2- A, is based on the use of the 1997 and 2002 editions of the American Society for Testing and Materials (ASTM) Standard Test Method E1921 (ASTM E1921), ``Standard Test Method for Determination of Reference Temperature T0 for Ferritic Steels in the Transition Range,'' and ASME Code Case N-629, ``Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials, Section III, Division 1, Class 1.'' Since the licensee is proposing an alternate method to the CV and drop weight-based test data required by procedures in the ASME Code, Paragraph NB-2331, an exemption from portions of 10 CFR part 50, appendix G, is required. The licensee also requested an exemption from 10 CFR 50.61(a)(5), which defines the method for evaluating initial (unirradiated) RTNDT as one that uses the procedures in ASME Code, Paragraph NB-2331, which requires the use of CV and drop weight-based test data. 10 CFR 50.61(a)(5) alternatively defines the method for evaluating RTNDT as a method other than that of ASME Code, Paragraph NB-2331 approved by the Director, Office of Nuclear Reactor Regulation (NRR). The licensee proposes to use the alternate methodology described above, in AREVA TR BAW-2308,'' Revisions 1-A and 2-A, to determine the initial RTNDT values for the Linde 80 weld materials present in the ANO, Unit 1, RPV beltline region, which is not the procedure in ASME Code, Paragraph NB- 2331 or an alternative method approved by the Director of NRR. Therefore, an exemption from 10 CFR 50.61(a)(5) is required. 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 10 CFR 50.12(a)(2)(ii), 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 As stated above, 10 CFR 50.12(a) allows the NRC to grant exemptions from portions of the requirements of 10 CFR part 50, appendix G and 10 CFR 50.61. Moreover, Section 50.60(b) of 10 CFR part 50 specifically allows the use of alternative methods for determining the initial material properties to 10 CFR part 50, appendix G, or portions thereof, when an exemption is granted by the Commission under 10 CFR 50.12. Because the regulations contemplate exemptions, granting the licensee's proposed exemption will not result in a violation of the Atomic Energy Act of 1954, as amended, or the NRC's regulations. Finally, this exemption would allow the licensee to make use of fracture toughness test data for evaluating the integrity of the ANO, Unit 1 RPV Linde 80 beltline weld materials, and would not result in changes to the operation of the plant. Therefore, the exemption is authorized by law. [[Page 15636]] C. No Undue Risk to Public Health and Safety The underlying purpose of appendix G to 10 CFR part 50 is to set forth fracture toughness requirements for ferritic materials of pressure-retaining components of the reactor coolant pressure boundary of light-water nuclear power reactors to provide adequate margins of safety during any conditions of normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected over its service lifetime. The methodology underlying the requirements of appendix G to 10 CFR part 50 is based on the use of CV and drop weight test data because of the reference to the ASME Code, Section III, Paragraph NB-2331. The licensee proposes to replace the use of existing CV and drop weight-based methodology with an alternate methodology that uses fracture toughness test data to demonstrate compliance with appendix G to 10 CFR part 50. The alternate method, described in AREVA TR BAW- 2308, Revisions 1-A and 2-A, utilizes fracture toughness data to determine the initial RTNDT of the Linde 80 weld materials present in the ANO, Unit 1 RPV beltline. The NRC staff has concluded that the requested exemption to Appendix G to 10 CFR part 50 is justified because the licensee will utilize the fracture toughness methodology specified in BAW-2308, Revisions 1-A and 2-A, within the conditions and limitations delineated in the NRC staff's safety evaluations (SEs) dated August 4, 2005, and March 24, 2008 (ADAMS Accession Nos. ML052070408 and ML080770349, respectively). The use of the methodology specified in the NRC staff's SEs will ensure that pressure-temperature limits developed for the ANO, Unit 1 RPV will continue to be based on an adequately conservative estimate of RPV material properties and ensure that the pressure- retaining components of the reactor coolant pressure boundary retain adequate margins of safety during any condition of normal operation, including anticipated operational occurrences. This exemption only modifies the methodology to be used by the licensee under 10 CFR part 50, appendix G.II.D(i) and does not exempt the licensee from meeting any other requirement of appendix G to 10 CFR part 50. Based on the above information, no new accident precursors are created by allowing an exemption from the use of the existing CV and drop weight-based methodology and the use of an alternative fracture toughness-based methodology to demonstrate compliance with appendix G to 10 CFR part 50; thus, the probability of postulated accidents is not increased. Also, based on the above information, the consequences of postulated accidents are not increased. Therefore, there is no undue risk to public health and safety associated with the proposed exemption to appendix G to 10 CFR part 50. The underlying purpose of 10 CFR 50.61 is to establish requirements for evaluating the fracture toughness of RPV materials to ensure that a licensee's RPV will be protected from failure during a PTS event. The licensee seeks an exemption from portions of 10 CFR 50.61 to use a methodology for the determination of adjusted/indexing PTS reference temperature (RTPTS ) values. The licensee proposes to use the methodology of TR BAW-2308, Revisions 1-A and 2-A as an alternative to the CV and drop weight-based methodology required by 10 CFR 50.61 for determining the initial, unirradiated properties when calculating RTPTS . The NRC has concluded that the exemption is justified because the licensee will utilize the methodology specified in the NRC staff's SEs regarding TR BAW-2308, Revisions 1-A and 2-A. In TR BAW-2308, Revision 1-A, the Babcock and Wilcox Owners Group proposed to perform fracture toughness testing based on the application of the Master Curve evaluation procedure, which permits data obtained from sample sets tested at different temperatures to be combined, as the basis for defining the initial material properties of Linde 80 welds based on T0 (initial temperature). The NRC staff evaluated this methodology for determining Linde 80 weld initial material properties and uncertainty in those properties, as well as the overall method for combining initial material property measurements based on T0 values (i.e. initial unirradiated nil-ductility reference temperature (IRTT0 ) in the BAW-2308 terminology), with property shifts from models in Regulatory Guide (RG) 1.99, Revision 2, ``Radiation Embrittlement of Reactor Vessel Materials,'' which are based on CV testing and defined margin term to account for uncertainties in the NRC staff's SE for TR BAW-2308, Revision 1-A. In the same NRC staff SE., Table 3, ``NRC Staff-Accepted IRTT0 and [Initial Margin] [sigma]i Values for Linde 80 Weld Wire Heats,'' contains the NRC staff's accepted IRTT0 and initial margin (denoted as [sigma]i ) for specific Linde 80 weld wire heat numbers. In accordance with the limitations and conditions outlined in the NRC staff's SE for TR BAW-2308, Revision 1-A, for utilizing the values in Table 3: The licensee has (1) utilized the appropriate NRC staff- accepted IRTT0 and [sigma]i values for applicable Linde 80 weld wire heat numbers; (2) applied a minimum chemistry factor of 167 degrees Fahrenheit ([deg]F) (values greater than 167[emsp14][deg]F were used for certain Linde 80 weld wire heat numbers if RG 1.99, Revision 2 indicated higher chemistry factors); (3) applied a value of 28 [deg]F for [sigma][Delta] (i.e., shift margin) in the margin term; and (4) submitted values for [Delta]RTNDT and the margin term for each Linde 80 weld in the RPV though the end of the current operating license. Additionally, the NRC's SE for TR BAW-2308, Revision 2-A concludes that the revised IRTT0 and [sigma]i values for Linde 80 weld materials are acceptable for referencing in plant-specific licensing applications as delineated in TR BAW-2308, Revision 2-A and to the extent specified under Section 4.0, ``Limitations and Conditions,'' of the SE. Incidentally, although Section 4.0 of the NRC staff SE states ``Future plant-specific applications for RPVs containing weld heat 72105, and weld heat 299L44, of Linde 80 must use the revised IRTT0 and [sigma]i values in TR BAW-2308, Revision 2,'' the NRC notes that neither of these weld heats is used at ANO, Unit 1. Therefore, this condition does not apply to ANO, Unit 1. During review of the licensee's exemption request, the NRC staff noted that additional information was required in order to complete its review regarding the chemistry factors used by the licensee for calculating [Delta]RTNDT values. The NRC staff requested this additional information via letter dated June 4, 2014 (ADAMS Accession No. ML14148A382). In the licensee's supplement dated June 26, 2014, the licensee provided the chemistry factors in Table 1, ``10 CFR 50.61 Chemistry Factors for the ANO-1 RV [Reactor Vessel] Materials.'' The NRC staff confirmed that the chemistry factors used by the licensee in calculating the RTNDT values were determined using the methodology of RG 1.99, Revision 2, and that 167 [deg]F is the minimum chemistry factor for Linde 80 materials. The use of the methodology in TR BAW-2308, Revisions 1-A and 2-A, will ensure the PTS evaluation developed for the ANO, Unit 1 RPV will continue to be based on an adequately conservative estimate of RPV material properties and ensure that the RPV will be protected from failure during a PTS event. Based on the evaluations above, the NRC staff has concluded that all [[Page 15637]] conditions and limitations outlined in the NRC staff's SEs for TR BAW- 2308, Revisions 1-A and 2-A, have been met for ANO Unit 1. Based on the above information, no new accident precursors are created by allowing an exemption to the alternate methodology to comply with the requirements of 10 CFR 50.61 in determining adjusted/indexing reference temperatures; thus, the probability of postulated accidents is not increased. Also, based on the above information, the consequences of postulated accidents are not increased. Therefore there is no undue risk to public health and safety. D. Consistent With the Common Defense and Security The licensee requested an exemption in order to utilize an alternative methodology from that specified in portions of 10 CFR part 50, appendix G, and 10 CFR 50.61, to allow the use of fracture toughness test data for evaluating the integrity of the ANO, Unit 1 RPV beltline Linde 80 weld materials. This exemption request is not related to, and does not impact, any security issues at ANO, Unit 1. Therefore, the NRC has determined that this exemption does not impact, and is consistent with, the common defense and security. E. Special Circumstances Special circumstances, in accordance with 10 CFR 50.12(a)(2)(ii), are present whenever application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule. The underlying purpose of 10 CFR 50.61(a)(5) and 10 CFR part 50, appendix G.II.D(i) is to set forth fracture toughness requirements (e.g., initial RTNDT values) for ferritic materials of pressure- retaining components of the reactor coolant pressure boundary of light water nuclear power reactors, in order to provide adequate margins of safety during any conditions of normal operation, including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary may be subjected over its service lifetime. The underlying purpose of 10 CFR 50.61 is to establish requirements for evaluating the fracture toughness of RPV materials to ensure that a licensee's RPV will be protected from failure during a PTS event. Entergy's exemption request proposes an alternate methodology to evaluate the RTNDT of Linde 80 weld materials in the RPV beltline region at ANO, Unit 1, based on fracture toughness test data found in AREVA TR BAW-2308, Revision 1-A and 2-A (in accordance with ASTM Standard E1921 and ASME Code Case N-629). This proposed alternate methodology achieves the underlying purpose of 10 CFR part 50 appendix G.II.D(i) because it provides an adequate conservative estimate of RPV materials properties and ensures that the pressure-retaining components of the RPV retain adequate margins for safety during any condition of normal operation. The alternate methodology also achieves the underlying purpose of 10 CFR 50.61(a)(5) because it will ensure that the PTS evaluation developed for the ANO, Unit 1 RPV will continue to be based on an adequately conservative estimate of RPV material properties and ensure that the RPV will be protected from failure during a PTS event. Accordingly, the NRC has concluded that using the procedures in the ASME Code, Paragraph NB-2331 is not necessary to achieve the underlying purpose of 10 CFR 50.61(a)(5) and 10 CFR part 50 appendix G.II.D(i). Therefore, the special circumstances required by 10 CFR 50.12(a)(2)(ii) for the granting of an exemption exist. F. Environmental Considerations The NRC staff determined that the exemption discussed herein meets the eligibility criteria for the categorical exclusion set forth in 10 CFR 51. 22(c)(9) because it is related to a requirement concerning the installation or use of a facility component located within the restricted area, as defined in 10 CFR part 20, and issuance 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 10 CFR 51.22(b), no environmental impact statement or environmental assessment need 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 10 CFR 51. 22(c)(9)(i)-(iii). Requirements in 10 CFR 51.22(c)(9)(i) The NRC evaluated whether the exemption involves no significant hazards consideration using the standards described in 10 CFR 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 exemption would allow the use of alternate methodologies from those specified in appendix G to 10 CFR part 50, and 10 CFR 50.61, to allow the use of fracture toughness test data for evaluating the integrity of RPV beltline welds. Use of the alternate methodology for determining the initial, unirradiated material reference temperatures of the Linde 80 weld materials present in the RPV beltline region will not result in changes in operation of configuration of the facility. The change in reactor vessel material initial properties will continue to satisfy the intent of 10 CFR 50, Appendix G, and 10 CFR 50.61. The change does not adversely affect accident initiators or pre-cursors, nor alter the design assumptions, conditions, or the manner in which the plant is operated and maintained. The change does not alter or prevent the ability of structures, systems or components from performing their intended function to mitigate the consequences of an initiating event with the assumed acceptance limits. There will be no adverse change to normal plant operating parameters, engineered safety feature actuation setpoints, accident mitigation capabilities, or accident analysis assumptions or inputs. The change does not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of an accident previously evaluated. Further, the change does not increase the types of amounts of radioactive effluent that may be released offsite, nor significantly increase individual or cumulative occupational/public radiation exposures. Therefore, the proposed exemption 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 exemption would allow the use of alternate methodologies from those specified in appendix G to 10 CFR part 50, and 10 CFR 50.61, to allow the use of fracture toughness test data for evaluating the integrity of RPV beltline welds. Use of the alternate methodology for determining the initial, unirradiated material reference temperatures of the Linde 80 weld materials present in the [[Page 15638]] RPV beltline region will not result in changes in operation or configuration of the facility. The change does not impose any new or different requirements or eliminate any existing requirements. The change is consistent with the current safety analysis assumptions and current plant operating practice. No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures are introduced as a result of the proposed change. Equipment important to safety will continue to operate as designed. The change does not result in any event previously deemed incredible being more credible. The change does not result in any adverse conditions or result in any increase in the challenges to safety systems. Therefore, this change does not create the possibility of a new or different kind of accident from an accident previously evaluated. 3. Does the proposed exemption involve a significant reduction in a margin of safety? Response: No. The proposed exemption does not alter safety limits, limiting safety system settings, or limiting conditions for operation. The setpoints at which protective actions are initiated are not altered by the change. There are no new or significant changes to initial conditions contributing to accident severity or consequences. The exemption will not otherwise affect plant protective boundaries, will not cause a release of fission products to the public, nor will it degrade the performance of any other structures, systems or components important to safety. Therefore, the proposed exemption does not involve a significant reduction in a margin of safety. Based on the above evaluation of the standards set forth in 10 CFR 50.92(c), the NRC concludes that the proposed exemption involves no significant hazards consideration. Accordingly, the requirements of 10 CFR 51.22(c)(9)(i) are met. Requirements in 10 CFR 51.22(c)(9)(ii-iii) The proposed exemption does not make any changes to the facility, equipment at the facility, or to fuel or core design. The proposed alternate methodology serves the same purpose as the requirements set forth in 10 CFR 50.61 and 10 CFR part 50, appendix G. Therefore, the NRC concludes that the exemption involves no significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative public or occupational radiation exposure. Therefore, the requirements of 10 CFR 51.22(c)(9)(ii-iii) are met. Conclusion Based on the above, the NRC concludes that the proposed exemption meets the eligibility criteria for the categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the NRC's issuance of this exemption. IV. Conclusions Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), 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 the licensee an exemption from 10 CFR part 50, appendix G.II.D(i) and 10 CFR 50.61(a)(5) requirements, in order to use the alternate methodology specified in AREVA TR BAW- 2308, Revisions 1-A and 2-A, in lieu of the existing requirement to use CV and drop weight-based methodologies to evaluate the initial (unirradiated) RTNDT of the Linde 80 weld materials in the RPV beltline region at ANO, Unit 1. This exemption is effective upon issuance. Dated at Rockville, Maryland, this 16th day of March 2015. For the Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2015-06700 Filed 3-23-15; 8:45 am] BILLING CODE 7590-01-P
![15634 Federal Register / Vol. 80, No. 56 / Tuesday, March 24, 2015 / Notices
NATIONAL SCIENCE FOUNDATION unless it displays a currently valid OMB Need and Use of the Information: The
control number. Federal government, universities,
Agency Information Collection SUPPLEMENTARY INFORMATION: researchers, and others use the
Activities: Comment Request Title: Survey of Earned Doctorates. information extensively. NSF, as the
OMB Control Number: 3145–0019. lead agency, publishes statistics from
AGENCY:National Science Foundation.
Summary of Collection: The authority the survey in several reports, but
Submission for OMB review;
ACTION:
primarily in the annual publication
comment request. to collect information for the Survey of
Earned Doctorates (SED) is established series, ‘‘Doctorate Recipients from U.S.
SUMMARY: The National Science under the National Science Foundation Universities.’’ These reports are
Foundation (NSF) has submitted the Act of 1950, as amended, Public Law available on the Web. NSF uses this
following information collection 507 (42 U.S.C. 1862), Section 3(a) (6), information to prepare congressionally
requirements to OMB for review and which directs the NSF ‘‘. . . to provide mandated reports such as Science and
clearance under the Paperwork a central clearinghouse for the Engineering Indicators and Women,
Reduction Act of 1995, Public Law 104– collection, interpretation, and analysis Minorities and Persons with Disabilities
13. This is the second notice for public of data on scientific and engineering in Science and Engineering.
comment; the first was published in the resources and to provide a source of Description of Respondents:
Federal Register at 79 FR 69883, and no information for policy formation by Individuals.
comments were received. NSF is other agencies of the federal Number of Respondents: 52,000.
government.’’ More recently, the Frequency of Responses: Annually.
forwarding the proposed renewal Total Burden Hours: 28,800.
submission to the Office of Management National Center for Science and
and Budget (OMB) for clearance Engineering Statistics (NCSES) was Dated: March 19, 2015.
simultaneously with the publication of established within NSF by Section 505 Suzanne H. Plimpton,
this second notice. The full submission of the America COMPETES Reports Clearance Officer, National Science
may be found at: http:// Reauthorization Act of 2010 and given Foundation.
www.reginfo.gov/public/do/PRAMain. a broader mandate to collect data related [FR Doc. 2015–06672 Filed 3–23–15; 8:45 am]
Comments: Comments regarding (a) to STEM education, the science and BILLING CODE 7555–01–P
whether the collection of information is engineering workforce, and U.S.
necessary for the proper performance of competitiveness in science, engineering,
the functions of the agency, including technology, and R&D. The SED is part NUCLEAR REGULATORY
whether the information will have of an integrated survey system that COMMISSION
practical utility; (b) the accuracy of the fulfills the education and workforce
components of this mission. [Docket No. 50–313; NRC–2015–0069]
agency’s estimate of burden including
the validity of the methodology and The SED has been conducted Entergy Operations, Inc., Arkansas
assumptions used; (c) ways to enhance annually since 1958 and is jointly Nuclear One, Unit 1
the quality, utility and clarity of the sponsored by six Federal agencies (NSF,
information to be collected; (d) ways to National Institutes of Health, U.S. AGENCY: Nuclear Regulatory
minimize the burden of the collection of Department of Education, U.S. Commission.
information on those who are to Department of Agriculture, National ACTION: Exemption; issuance.
respond, including through the use of Endowment for the Humanities, and
appropriate automated, electronic, National Aeronautics and Space SUMMARY: The U.S. Nuclear Regulatory
mechanical, or other technological Administration) in order to avoid Commission (NRC) is issuing an
collection techniques or other forms of duplication of effort in collecting such exemption in response to a March 20,
information technology should be data. It is an accurate, timely source of 2014, request from Entergy Operations,
addressed to: Office of Information and information on an important national Inc. (Entergy or the licensee), from the
Regulatory Affairs of OMB, Attention: resource—highly educated individuals. requirements to use Charpy V-notch
Desk Officer for National Science Data are obtained via Web survey or (CV) and drop weight-based
Foundation, 725—17th Street NW., paper questionnaire from each person methodology to determine initial nil-
Room 10235, Washington, DC 20503, earning a research doctorate at the time ductility reference temperature (RTNDT)
and to Suzanne H. Plimpton, Reports they receive the degree. Graduate for use in evaluating the integrity of
Clearance Officer, National Science schools help distribute the SED to their Linde 80 weld materials in the reactor
Foundation, 4201 Wilson Boulevard, graduating doctorate recipients. Data are pressure vessel (RPV) beltline at
Suite 1265, Arlington, Virginia 22230 or collected on the doctorate recipient’s Arkansas Nuclear One (ANO), Unit 1.
send email to splimpto@nsf.gov. field of specialty, educational This exemption would allow the
Comments regarding these information background, sources of financial licensee to use an alternate methodology
collections are best assured of having support in graduate school, debt level, to incorporate fracture toughness test
their full effect if received within 30 postgraduation plans for employment, data to determine RTNDT values for use
days of this notification. Copies of the and demographic characteristics. in the evaluation of the RPV beltline
submission(s) may be obtained by The survey will be collected in weld material integrity in support of the
calling 703–292–7556. conformance with the National Science development of updated pressure-
It is not permissible for NSF to Foundation Act of 1950, as amended, temperature limit curves.
DATES: March 24, 2015.
mstockstill on DSK4VPTVN1PROD with NOTICES
conduct or sponsor a collection of and the Privacy Act of 1974. Responses
information unless the collection of from individuals are voluntary. NSF ADDRESSES: Please refer to Docket ID
information displays a currently valid will ensure that all individually NRC–2015–0069 when contacting the
OMB control number and the agency identifiable information collected will NRC about the availability of
informs potential persons who are to be kept strictly confidential and will be information regarding this document.
respond to the collection of information used for research or statistical purposes, You may obtain publicly-available
that such persons are not required to analyzing data, and preparing scientific information related to this document
respond to the collection of information reports and articles. using any of the following methods:
VerDate Sep<11>2014 01:09 Mar 24, 2015 Jkt 235001 PO 00000 Frm 00087 Fmt 4703 Sfmt 4703 E:\FR\FM\24MRN1.SGM 24MRN1](https://thefederalregister.org/doc/80_FR_15690/page/1.svg)
![Federal Register / Vol. 80, No. 56 / Tuesday, March 24, 2015 / Notices 15635
• Federal Rulemaking Web site: Go to ‘‘Fracture toughness requirements for initial (unirradiated) RTNDT as one that
http://www.regulations.gov and search protection against pressurized thermal uses the procedures in ASME Code,
for Docket ID NRC–2015–0069. Address shock [PTS] events,’’ provides fracture Paragraph NB–2331, which requires the
questions about NRC dockets to Carol toughness requirements for protection use of CV and drop weight-based test
Gallagher; telephone: 301–415–3463; against PTS events. A PTS event is an data. 10 CFR 50.61(a)(5) alternatively
email: Carol.Gallagher@nrc.gov. For event or transient in pressurized water defines the method for evaluating RTNDT
technical questions, contact the reactors (PWRs) causing severe as a method other than that of ASME
individual listed in the FOR FURTHER overcooling (thermal shock) concurrent Code, Paragraph NB–2331 approved by
INFORMATION CONTACT section of this with or followed by significant pressure the Director, Office of Nuclear Reactor
document. in the reactor vessel. Pursuant to 10 CFR Regulation (NRR). The licensee
• NRC’s Agencywide Documents 50.12, ‘‘Specific exemptions,’’ by letter proposes to use the alternate
Access and Management System dated March 20, 2014 (ADAMS methodology described above, in
(ADAMS): You may obtain publicly- Accession No. ML14083A640), as AREVA TR BAW–2308,’’ Revisions 1–A
available documents online in the supplemented by letter dated June 26, and 2–A, to determine the initial RTNDT
ADAMS Public Documents collection at 2014 (ADAMS Accession No. values for the Linde 80 weld materials
http://www.nrc.gov/reading-rm/ ML14177A302), the licensee requested present in the ANO, Unit 1, RPV
adams.html. To begin the search, select an exemption from certain requirements beltline region, which is not the
‘‘ADAMS Public Documents’’ and then of 10 CFR part 50, appendix G, and 10 procedure in ASME Code, Paragraph
select ‘‘Begin Web-based ADAMS CFR 50.61, to revise certain ANO, Unit NB–2331 or an alternative method
Search.’’ For problems with ADAMS, 1 RPV initial (unirradiated) properties approved by the Director of NRR.
please contact the NRC’s Public using AREVA Topical Report (TR) Therefore, an exemption from 10 CFR
Document Room (PDR) reference staff at BAW–2308, Revisions 1–A and 2–A, 50.61(a)(5) is required.
1–800–397–4209, 301–415–4737, or by ‘‘Initial RTNDT [nil-ductility reference
III. Discussion
email to pdr.resource@nrc.gov. The temperature] of Linde 80 Weld
ADAMS accession number for each Materials.’’ Pursuant to 10 CFR 50.12, the
document referenced (if it is available in Specifically, the licensee requested an Commission may, upon application by
ADAMS) is provided the first time that exemption from 10 CFR part 50, any interested person or upon its own
a document is referenced. appendix G.II.D(i), which requires that initiative, grant exemptions from the
• NRC’s PDR: You may examine and licensees evaluate the pre-service or requirements of 10 CFR part 50 when:
unirradiated RTNDT according to the (1) The exemptions are authorized by
purchase copies of public documents at
procedures in the American Society of law, will not present an undue risk to
the NRC’s PDR, Room O1–F21, One
Mechanical Engineers (ASME) Code, public health or safety, and are
White Flint North, 11555 Rockville
Paragraph NB–2331, ‘‘Material for consistent with the common defense
Pike, Rockville, Maryland 20852.
Vessels.’’ The ASME Code Paragraph and security; and (2) when special
FOR FURTHER INFORMATION CONTACT: circumstances are present. Under 10
NB–2331 requires that licensees use
Andrea George, Office of Nuclear Charpy V-notch (CV) and drop weight- CFR 50.12(a)(2)(ii), special
Reactor Regulation, U.S. Nuclear based methodology to derive the initial circumstances include, among other
Regulatory Commission, Washington, RTNDT values. In lieu of the existing things, when application of the specific
DC 20555–0001; telephone: 301–415– methodology described above, the regulation in the particular
1081, email: Andrea.George@nrc.gov. licensee requested to use the alternate circumstance would not serve, or is not
SUPPLEMENTARY INFORMATION: methodology in TR BAW–2308, necessary to achieve, the underlying
Revisions 1–A and 2–A, to incorporate purpose of the rule.
I. Background
the use of fracture toughness test data A. Authorized by Law
Entergy is the holder of renewed for evaluating the integrity of the ANO,
Facility Operating License No. DPR–51, Unit 1, Linde 80 weld materials in the As stated above, 10 CFR 50.12(a)
that authorizes operation of ANO, Unit RPV beltline. The methodology in TR allows the NRC to grant exemptions
1. The license provides, among other BAW–2308, Revisions 1–A and 2–A, is from portions of the requirements of 10
things, that the facility is subject to all based on the use of the 1997 and 2002 CFR part 50, appendix G and 10 CFR
rules, regulations, and orders of the NRC editions of the American Society for 50.61. Moreover, Section 50.60(b) of 10
now or hereafter in effect. Testing and Materials (ASTM) Standard CFR part 50 specifically allows the use
The ANO facility consists of two Test Method E1921 (ASTM E1921), of alternative methods for determining
pressurized-water reactors, Units 1 and ‘‘Standard Test Method for the initial material properties to 10 CFR
2, located in Pope County, Arkansas. Determination of Reference part 50, appendix G, or portions thereof,
Temperature T0 for Ferritic Steels in the when an exemption is granted by the
II. Request/Action Commission under 10 CFR 50.12.
Transition Range,’’ and ASME Code
Part 50 of title 10 of the Code of Case N–629, ‘‘Use of Fracture Because the regulations contemplate
Federal Regulation (10 CFR), appendix Toughness Test Data to Establish exemptions, granting the licensee’s
G, ‘‘Fracture Toughness Requirements,’’ Reference Temperature for Pressure proposed exemption will not result in a
specifies fracture toughness Retaining Materials, Section III, Division violation of the Atomic Energy Act of
requirements for ferritic materials of 1, Class 1.’’ Since the licensee is 1954, as amended, or the NRC’s
pressure-retaining components of the proposing an alternate method to the CV regulations. Finally, this exemption
mstockstill on DSK4VPTVN1PROD with NOTICES
reactor coolant pressure boundary of and drop weight-based test data would allow the licensee to make use of
light water reactors to provide adequate required by procedures in the ASME fracture toughness test data for
margins of safety during any condition Code, Paragraph NB–2331, an evaluating the integrity of the ANO,
of normal operation, including exemption from portions of 10 CFR part Unit 1 RPV Linde 80 beltline weld
anticipated operational occurrences and 50, appendix G, is required. materials, and would not result in
system hydrostatic tests, to which the The licensee also requested an changes to the operation of the plant.
pressure boundary may be subjected to exemption from 10 CFR 50.61(a)(5), Therefore, the exemption is authorized
over its service lifetime. Section 50.61, which defines the method for evaluating by law.
VerDate Sep<11>2014 01:09 Mar 24, 2015 Jkt 235001 PO 00000 Frm 00088 Fmt 4703 Sfmt 4703 E:\FR\FM\24MRN1.SGM 24MRN1](https://thefederalregister.org/doc/80_FR_15690/page/2.svg)
![15636 Federal Register / Vol. 80, No. 56 / Tuesday, March 24, 2015 / Notices
C. No Undue Risk to Public Health and alternative fracture toughness-based In accordance with the limitations
Safety methodology to demonstrate and conditions outlined in the NRC
The underlying purpose of appendix compliance with appendix G to 10 CFR staff’s SE for TR BAW–2308, Revision
G to 10 CFR part 50 is to set forth part 50; thus, the probability of 1–A, for utilizing the values in Table 3:
fracture toughness requirements for postulated accidents is not increased. The licensee has (1) utilized the
ferritic materials of pressure-retaining Also, based on the above information, appropriate NRC staff-accepted IRTT0
components of the reactor coolant the consequences of postulated and si values for applicable Linde 80
pressure boundary of light-water accidents are not increased. Therefore, weld wire heat numbers; (2) applied a
nuclear power reactors to provide there is no undue risk to public health minimum chemistry factor of 167
adequate margins of safety during any and safety associated with the proposed degrees Fahrenheit (°F) (values greater
conditions of normal operation, exemption to appendix G to 10 CFR part than 167 °F were used for certain Linde
including anticipated operational 50. 80 weld wire heat numbers if RG 1.99,
occurrences and system hydrostatic The underlying purpose of 10 CFR Revision 2 indicated higher chemistry
50.61 is to establish requirements for factors); (3) applied a value of 28 °F for
tests, to which the pressure boundary
evaluating the fracture toughness of RPV sΔ (i.e., shift margin) in the margin term;
may be subjected over its service
materials to ensure that a licensee’s RPV and (4) submitted values for DRTNDT
lifetime. The methodology underlying
will be protected from failure during a and the margin term for each Linde 80
the requirements of appendix G to 10
PTS event. The licensee seeks an weld in the RPV though the end of the
CFR part 50 is based on the use of CV
exemption from portions of 10 CFR current operating license. Additionally,
and drop weight test data because of the
50.61 to use a methodology for the the NRC’s SE for TR BAW–2308,
reference to the ASME Code, Section III,
determination of adjusted/indexing PTS Revision 2–A concludes that the revised
Paragraph NB–2331. The licensee
reference temperature (RTPTS) values. IRTT0 and si values for Linde 80 weld
proposes to replace the use of existing
The licensee proposes to use the materials are acceptable for referencing
CV and drop weight-based methodology in plant-specific licensing applications
with an alternate methodology that uses methodology of TR BAW–2308,
Revisions 1–A and 2–A as an alternative as delineated in TR BAW–2308,
fracture toughness test data to Revision 2–A and to the extent specified
demonstrate compliance with appendix to the CV and drop weight-based
methodology required by 10 CFR 50.61 under Section 4.0, ‘‘Limitations and
G to 10 CFR part 50. The alternate Conditions,’’ of the SE. Incidentally,
method, described in AREVA TR BAW– for determining the initial, unirradiated
properties when calculating RTPTS. The although Section 4.0 of the NRC staff SE
2308, Revisions 1–A and 2–A, utilizes states ‘‘Future plant-specific
fracture toughness data to determine the NRC has concluded that the exemption
is justified because the licensee will applications for RPVs containing weld
initial RTNDT of the Linde 80 weld heat 72105, and weld heat 299L44, of
materials present in the ANO, Unit 1 utilize the methodology specified in the
NRC staff’s SEs regarding TR BAW– Linde 80 must use the revised IRTT0 and
RPV beltline. si values in TR BAW–2308, Revision 2,’’
The NRC staff has concluded that the 2308, Revisions 1–A and 2–A.
the NRC notes that neither of these weld
requested exemption to Appendix G to In TR BAW–2308, Revision 1–A, the
heats is used at ANO, Unit 1. Therefore,
10 CFR part 50 is justified because the Babcock and Wilcox Owners Group this condition does not apply to ANO,
licensee will utilize the fracture proposed to perform fracture toughness Unit 1.
toughness methodology specified in testing based on the application of the During review of the licensee’s
BAW–2308, Revisions 1–A and 2–A, Master Curve evaluation procedure, exemption request, the NRC staff noted
within the conditions and limitations which permits data obtained from that additional information was
delineated in the NRC staff’s safety sample sets tested at different required in order to complete its review
evaluations (SEs) dated August 4, 2005, temperatures to be combined, as the regarding the chemistry factors used by
and March 24, 2008 (ADAMS Accession basis for defining the initial material the licensee for calculating DRTNDT
Nos. ML052070408 and ML080770349, properties of Linde 80 welds based on values. The NRC staff requested this
respectively). The use of the T0 (initial temperature). The NRC staff additional information via letter dated
methodology specified in the NRC evaluated this methodology for June 4, 2014 (ADAMS Accession No.
staff’s SEs will ensure that pressure- determining Linde 80 weld initial ML14148A382). In the licensee’s
temperature limits developed for the material properties and uncertainty in supplement dated June 26, 2014, the
ANO, Unit 1 RPV will continue to be those properties, as well as the overall licensee provided the chemistry factors
based on an adequately conservative method for combining initial material in Table 1, ‘‘10 CFR 50.61 Chemistry
estimate of RPV material properties and property measurements based on T0 Factors for the ANO–1 RV [Reactor
ensure that the pressure-retaining values (i.e. initial unirradiated nil- Vessel] Materials.’’ The NRC staff
components of the reactor coolant ductility reference temperature (IRTT0) confirmed that the chemistry factors
pressure boundary retain adequate in the BAW–2308 terminology), with used by the licensee in calculating the
margins of safety during any condition property shifts from models in RTNDT values were determined using
of normal operation, including Regulatory Guide (RG) 1.99, Revision 2, the methodology of RG 1.99, Revision 2,
anticipated operational occurrences. ‘‘Radiation Embrittlement of Reactor and that 167 °F is the minimum
This exemption only modifies the Vessel Materials,’’ which are based on chemistry factor for Linde 80 materials.
methodology to be used by the licensee CV testing and defined margin term to The use of the methodology in TR
under 10 CFR part 50, appendix G.II.D(i) account for uncertainties in the NRC BAW–2308, Revisions 1–A and 2–A,
mstockstill on DSK4VPTVN1PROD with NOTICES
and does not exempt the licensee from staff’s SE for TR BAW–2308, Revision will ensure the PTS evaluation
meeting any other requirement of 1–A. In the same NRC staff SE., Table developed for the ANO, Unit 1 RPV will
appendix G to 10 CFR part 50. 3, ‘‘NRC Staff-Accepted IRTT0 and continue to be based on an adequately
Based on the above information, no [Initial Margin] si Values for Linde 80 conservative estimate of RPV material
new accident precursors are created by Weld Wire Heats,’’ contains the NRC properties and ensure that the RPV will
allowing an exemption from the use of staff’s accepted IRTT0 and initial margin be protected from failure during a PTS
the existing CV and drop weight-based (denoted as si) for specific Linde 80 event. Based on the evaluations above,
methodology and the use of an weld wire heat numbers. the NRC staff has concluded that all
VerDate Sep<11>2014 01:09 Mar 24, 2015 Jkt 235001 PO 00000 Frm 00089 Fmt 4703 Sfmt 4703 E:\FR\FM\24MRN1.SGM 24MRN1](https://thefederalregister.org/doc/80_FR_15690/page/3.svg)
![15638 Federal Register / Vol. 80, No. 56 / Tuesday, March 24, 2015 / Notices
RPV beltline region will not result in there is no significant increase in licensee) dated March 20, 2014. This
changes in operation or configuration of individual or cumulative public or exemption would permit the licensee to
the facility. The change does not impose occupational radiation exposure. reduce its primary offsite liability
any new or different requirements or Therefore, the requirements of 10 CFR insurance and withdraw from
eliminate any existing requirements. 51.22(c)(9)(ii–iii) are met. participation in the secondary
The change is consistent with the Conclusion retrospective rating pool for deferred
current safety analysis assumptions and premium charges.
current plant operating practice. No new Based on the above, the NRC
DATES: March 24, 2015.
accident scenarios, transient precursors, concludes that the proposed exemption
meets the eligibility criteria for the ADDRESSES: Please refer to Docket ID
failure mechanisms, or limiting single
failures are introduced as a result of the categorical exclusion set forth in 10 CFR NRC–2015–0068 when contacting the
proposed change. Equipment important 51.22(c)(9). Therefore, in accordance NRC about the availability of
to safety will continue to operate as with 10 CFR 51.22(b), no environmental information regarding this document.
designed. The change does not result in impact statement or environmental You may obtain publicly-available
any event previously deemed incredible assessment need be prepared in information related to this document
being more credible. The change does connection with the NRC’s issuance of using any of the following methods:
not result in any adverse conditions or this exemption. • Federal Rulemaking Web site: Go to
result in any increase in the challenges http://www.regulations.gov and search
IV. Conclusions for Docket ID NRC–2015–0068. Address
to safety systems.
Therefore, this change does not create Accordingly, the Commission has questions about NRC dockets to Carol
the possibility of a new or different kind determined that, pursuant to 10 CFR Gallagher; telephone: 301–415–3463;
of accident from an accident previously 50.12(a), the exemption is authorized by email: Carol.Gallagher@nrc.gov. For
evaluated. law, will not present an undue risk to technical questions, contact the
the public health and safety, and is individual listed in the FOR FURTHER
3. Does the proposed exemption involve consistent with the common defense INFORMATION CONTACT section of this
a significant reduction in a margin of and security. Also, special document.
safety? circumstances are present. Therefore, • NRC’s Agencywide Documents
Response: No. the Commission hereby grants the Access and Management System
The proposed exemption does not licensee an exemption from 10 CFR part (ADAMS): You may obtain publicly-
alter safety limits, limiting safety system 50, appendix G.II.D(i) and 10 CFR available documents online in the
settings, or limiting conditions for 50.61(a)(5) requirements, in order to use ADAMS Public Documents collection at
operation. The setpoints at which the alternate methodology specified in http://www.nrc.gov/reading-rm/
protective actions are initiated are not AREVA TR BAW–2308, Revisions 1–A adams.html. To begin the search, select
altered by the change. There are no new and 2–A, in lieu of the existing ‘‘ADAMS Public Documents’’ and then
or significant changes to initial requirement to use CV and drop weight- select ‘‘Begin Web-based ADAMS
conditions contributing to accident based methodologies to evaluate the Search.’’ For problems with ADAMS,
severity or consequences. The initial (unirradiated) RTNDT of the Linde please contact the NRC’s Public
exemption will not otherwise affect 80 weld materials in the RPV beltline Document Room (PDR) reference staff at
plant protective boundaries, will not region at ANO, Unit 1. 1–800–397–4209, 301–415–4737, or by
cause a release of fission products to the This exemption is effective upon email to pdr.resource@nrc.gov. The
public, nor will it degrade the issuance. ADAMS accession number for each
performance of any other structures, Dated at Rockville, Maryland, this 16th day document referenced (if it available in
systems or components important to of March 2015. ADAMS) is provided the first time that
safety. For the Nuclear Regulatory Commission. a document is referenced.
Therefore, the proposed exemption Michele G. Evans, • NRC’s PDR: You may examine and
does not involve a significant reduction Director, Division of Operating Reactor purchase copies of public documents at
in a margin of safety. Licensing, Office of Nuclear Reactor the NRC’s PDR, Room O1–F21, One
Based on the above evaluation of the Regulation. White Flint North, 11555 Rockville
standards set forth in 10 CFR 50.92(c), [FR Doc. 2015–06700 Filed 3–23–15; 8:45 am] Pike, Rockville, Maryland 20852.
the NRC concludes that the proposed
BILLING CODE 7590–01–P FOR FURTHER INFORMATION CONTACT:
exemption involves no significant
hazards consideration. Accordingly, the William Huffman, Office of Nuclear
requirements of 10 CFR 51.22(c)(9)(i) are Reactor Regulation, U.S. Nuclear
NUCLEAR REGULATORY Regulatory Commission, Washington,
met. COMMISSION DC 20555–0001; telephone: 301–415–
Requirements in 10 CFR 51.22(c)(9)(ii– [Docket No. 50–305; NRC–2015–0068] 2046; email: William.Huffman@nrc.gov.
iii) SUPPLEMENTARY INFORMATION:
The proposed exemption does not Dominion Energy Kewaunee, Inc.;
Kewaunee Power Station I. Background
make any changes to the facility,
equipment at the facility, or to fuel or AGENCY: Nuclear Regulatory The Kewaunee Power Station (KPS)
core design. The proposed alternate Commission. facility is a decommissioning power
mstockstill on DSK4VPTVN1PROD with NOTICES
methodology serves the same purpose as ACTION: Exemption; issuance. reactor located on approximately 900
the requirements set forth in 10 CFR acres in Carlton (Kewaunee County),
50.61 and 10 CFR part 50, appendix G. SUMMARY: The U.S. Nuclear Regulatory Wisconsin, 27 miles southeast of Green
Therefore, the NRC concludes that the Commission (NRC) is issuing an Bay, Wisconsin. The licensee, DEK, is
exemption involves no significant exemption from certain power reactor the holder of the KPS Renewed Facility
change in the types or a significant liability insurance requirements in Operating License No. DPR–43. The
increase in the amounts of any effluents response to a request from Dominion license provides, among other things,
that may be released offsite, and that Energy Kewaunee, Inc. (DEK or the that the facility is subject to all rules,
VerDate Sep<11>2014 01:09 Mar 24, 2015 Jkt 235001 PO 00000 Frm 00091 Fmt 4703 Sfmt 4703 E:\FR\FM\24MRN1.SGM 24MRN1](https://thefederalregister.org/doc/80_FR_15690/page/5.svg)
Document Created: 2015-12-18 11:44:41
Document Modified: 2015-12-18 11:44:41
| 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 | March 24, 2015. | |
| Contact | Andrea George, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1081, email: [email protected] | |
| FR Citation | 80 FR 15634 |
2025 Federal Register | Disclaimer | Privacy Policy
USC | CFR | eCFR