License Exemption Request for Florida Power & Light Company Turkey Point Nuclear Generating Unit Nos. 3 and 4, 11469-11472 [2014-04409]

Download as PDF tkelley on DSK3SPTVN1PROD with NOTICES Federal Register / Vol. 79, No. 40 / Friday, February 28, 2014 / Notices rankings of personal income and gross domestic product by state. 3. Department of Defense, Office of the Secretary of Defense (DAA–0330– 2013–0006, 2 items, 1 temporary item). Master files of an electronic information system containing tracking information on military suicides and suicide attempts. Proposed for permanent retention are annual statistical reports on suicide events. 4. Department of Defense, Office of the Secretary of Defense (DAA–0330– 2013–0008, 1 item, 1 temporary item). Master files of an electronic information system containing eye injury and eye disease data on military service members and veterans. 5. Department of Defense, Office of the Secretary of Defense (DAA–0330– 2013–0016, 1 item, 1 temporary item). Master files of an electronic information system used to track vehicle tow appeals. 6. Department of Homeland Security, Transportation Security Administration (N1–560–12–15, 9 items, 9 temporary items). Budget records related to planning, estimates, and appropriations including reports, working papers, and correspondence files. 7. Administrative Office of the United States Courts, United States District Courts (DAA–0021–2013–0006, 15 items, 14 temporary items). Records of the Federal Public Defenders Organization including routine audits, administrative records, and web postings. Proposed for permanent retention are annual reports. 8. Consumer Financial Protection Bureau, Office of Consumer Response (N1–587–12–4, 4 items, 3 temporary items). Master files of an electronic information system containing consumer complaints and quality control records. Proposed for permanent retention are reports and financial trend analysis records. 9. National Archives and Records Administration, Government-wide (DAA–GRS–2013–0006, 8 items, 8 temporary items). General Records Schedule for records related to system and data security and access, reports on computer security incidents, and backup tapes and files. 10. National Archives and Records Administration, Government-wide (DAA–GRS–2013–0008, 5 items, 5 temporary items). General Records Schedule for grant and cooperative agreement program management records, grant and cooperative agreement case files, and final grant and VerDate Mar<15>2010 17:47 Feb 27, 2014 Jkt 232001 11469 cooperative agreement products or deliverables. NUCLEAR REGULATORY COMMISSION Paul M. Wester, Jr., Chief Records Officer for the U.S. Government. [Docket Nos. 50–250 and 50–251; NRC– 2014–0035] [FR Doc. 2014–04417 Filed 2–27–14; 8:45 am] BILLING CODE 7515–01–P NATIONAL SCIENCE FOUNDATION License Exemption Request for Florida Power & Light Company Turkey Point Nuclear Generating Unit Nos. 3 and 4 Nuclear Regulatory Commission. AGENCY: Exemption; issuance. Sunshine Act Meetings ACTION: The National Science Board, pursuant to NSF regulations (45 CFR part 614), the National Science Foundation Act, as amended (42 U.S.C. 1862n–5), and the Government in the Sunshine Act (5 U.S.C. 552b), hereby gives notice of a CHANGE in the scheduling of two meetings for the transaction of National Science Board business, as noted below. The original notice was published in the Federal Register on February 20, 2014 (79 FR 9770). ORIGINAL DATE AND TIME: Plenary Board Meeting Executive Closed Session: 11:00– 11:30 a.m. Plenary Board Meeting Closed Session: 11:30 a.m.–12:15 p.m. CHANGED DATE AND TIME: Plenary Board Meeting Executive Closed Session: 8:30–9:00 a.m. Plenary Board Meeting Closed Session: 11:00 a.m.–12:15 p.m. PLACE: These meetings will be held at the National Science Foundation, 4201Wilson Blvd., Rooms 1235, Arlington, VA 22230. All visitors must contact the Board Office (call 703–292– 7000 or send an email message to nationalsciencebrd@nsf.gov) at least 24 hours prior to the meeting and provide name and organizational affiliation. Visitors must report to the NSF visitor desk located in the lobby at the 9th and N. Stuart Streets entrance to receive a visitor’s badge. UPDATES: Please refer to the National Science Board Web site for additional information. Meeting information and schedule updates (time, place, subject matter or status of meeting) may be found at http://www.nsf.gov/nsb/ notices/. AGENCY CONTACT: Jennie L. Moehlmann, jmoehlma@nsf.gov, (703) 292–7000. PUBLIC AFFAIRS CONTACT: Dana Topousis, dtopousi@nsf.gov, (703) 292–7750. SUMMARY: Ann Bushmiller, Senior Counsel to the National Science Board. [FR Doc. 2014–04569 Filed 2–26–14; 11:15 am] BILLING CODE 7555–01–P PO 00000 Frm 00080 Fmt 4703 Sfmt 4703 The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption in response to a March 22, 2013, request from Florida Power & Light Company for an exemption for the use of a different fuel rod cladding material (Optimized ZIRLOTM). ADDRESSES: Please refer to Docket ID NRC–2014–0035 when contacting the NRC about the availability of information regarding this document. You may access 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–2014–0035. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC Library at http://www.nrc.gov/readingrm/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 pdr.resource@nrc.gov. The ADAMS accession number for each document referenced in this document (if that document 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: Audrey L. Klett, Office of Nuclear Reactor Regulation, telephone: 301– 415–0489, email: Audrey.Klett@nrc.gov, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. E:\FR\FM\28FEN1.SGM 28FEN1 11470 Federal Register / Vol. 79, No. 40 / Friday, February 28, 2014 / Notices I. Background Florida Power & Light Company (the licensee) is the holder of Renewed Facility Operating License Nos. DPR–31 and DPR–41, which authorize operation of the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point 3 and 4), respectively. The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC) now or hereafter in effect. The facility consists of two pressurized water reactors located in Miami-Dade County, Florida. tkelley on DSK3SPTVN1PROD with NOTICES II. Request/Action Pursuant to Section 50.12, ‘‘Specific exemptions,’’ of Title 10 of the Code of Federal Regulations (10 CFR), the licensee has, by letter dated March 22, 2013 (ADAMS Accession No. ML13100A131), requested an exemption from the requirements of 10 CFR 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 rods clad with Optimized ZIRLOTM alloy for future reload applications. The regulations in 10 CFR 50.46 contain acceptance criteria for the ECCS for reactors fueled with zircaloy or ZIRLO fuel rod cladding material. In addition, Appendix K to 10 CFR Part 50 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 Optimized ZIRLOTM. The licensee requested the exemption because these regulations do not have provisions for the use of fuel rods clad in a material other than zircaloy or ZIRLOTM. Because the material specifications of Optimized ZIRLOTM differ from the specification for zircaloy or ZIRLOTM, a plant-specific exemption is required to support the reload applications for Turkey Point 3 and 4. 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 provide for the application of the acceptance criteria of 10 CFR 50.46 and Appendix K to 10 CFR Part 50 to fuel assembly designs using Optimized ZIRLOTM fuel rod cladding material. In its letter dated March 22, 2013, the licensee clarified that it was not seeking an exemption from the acceptance and analytical criteria of these regulations. The intent of the request is to allow the use of VerDate Mar<15>2010 17:47 Feb 27, 2014 Jkt 232001 criteria set forth in these regulations for application to the Optimized ZIRLOTM fuel rod cladding material. III. Discussion Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person, grant exemptions from the requirements of 10 CFR Part 50, which are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. Paragraph (a)(2)(ii) of 10 CFR 50.12 states that the Commission will not consider granting an exemption unless special circumstances are present, such as when application of the regulation in the particular circumstance is not necessary to achieve the underlying purpose of the rule. A. 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 is not necessary to achieve the underlying purpose of the rule. The underlying purpose of 10 CFR 50.46 and Appendix K to 10 CFR Part 50 is to establish acceptance criteria for ECCS performance. The regulations in 10 CFR 50.46 and Appendix K are not directly applicable to Optimized ZIRLOTM, even though the evaluations described in the following sections of this exemption show that the intent of the regulation is met. Therefore, because the underlying purposes of 10 CFR 50.46 and Appendix K of 10 CFR Part 50 are achieved through the use of Optimized ZIRLOTM fuel rod cladding material, the special circumstances required by 10 CFR 50.12(a)(2)(ii) for the granting of an exemption exist. B. Authorized by Law This exemption would allow the use of Optimized ZIRLOTM fuel rod cladding material for future reload applications at Turkey Point 3 and 4. Section 10 CFR 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR Part 50. The NRC staff determined that granting the licensee’s proposed 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. C. No Undue Risk to Public Health and Safety Section 10 CFR 50.46 requires that each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical zircaloy or ZIRLO cladding PO 00000 Frm 00081 Fmt 4703 Sfmt 4703 must be provided with an ECCS that must be designed so that its calculated cooling performance following postulated loss-of-coolant accidents (LOCAs) conforms to the criteria set forth in paragraph (b) of this section. The underlying purpose of 10 CFR 50.46 is to establish acceptance criteria for adequate ECCS performance. As previously documented in the NRC staff’s safety evaluation dated June 10, 2005 (ADAMS Accession No. ML051670395), of topical reports submitted by Westinghouse, and subject to compliance with the specific conditions of approval established in the safety evaluation, the NRC staff found that Westinghouse demonstrated the applicability of these ECCS acceptance criteria to Optimized ZIRLOTM. Ring compression tests performed by Westinghouse on Optimized ZIRLOTM (see WCAP– 14342–A & CENPD–404–NP–A at ADAMS Accession No. ML062080569) demonstrate an acceptable retention of postquench ductility up to 10 CFR 50.46 limits of 2200 degrees Fahrenheit and 17 percent equivalent clad reacted. Furthermore, the NRC staff concluded that oxidation measurements provided by the licensee by letter LTR–NRC–07– 58 from Westinghouse to the NRC, ‘‘SER Compliance with WCAP–12610–P–A & CENPD–404–P–A, Addendum 1–A, ‘Optimized ZIRLOTM,’’’ dated November 6, 2007 (public version is at ADAMS Accession No. ML073130560), illustrate that oxide thickness and associated hydrogen pickup for Optimized ZIRLOTM at any given burnup would be less than both zircaloy-4 and ZIRLOTM. Hence, the NRC staff concludes that Optimized ZIRLOTM would be expected to maintain better postquench ductility than ZIRLOTM. This finding is further supported by an ongoing LOCA research program at Argonne National Laboratory, which has identified a strong correlation between cladding hydrogen content (caused by in-service corrosion) and postquench ductility. In its letter dated March 22, 2013, the licensee stated that its reload evaluations will ensure that acceptance criteria are met for the insertion of assemblies with fuel rods clad with Optimized ZILROTM. The licensee stated that it will evaluate fuel assemblies using Optimized ZIRLOTM fuel rod cladding material using NRCapproved analytical methods and plantspecific models to address the changes in the cladding material properties. The licensee stated that Westinghouse will perform an evaluation of the Turkey Point 3 and 4 cores using LOCA E:\FR\FM\28FEN1.SGM 28FEN1 Federal Register / Vol. 79, No. 40 / Friday, February 28, 2014 / Notices tkelley on DSK3SPTVN1PROD with NOTICES methods approved for the site to ensure that assemblies with Optimized ZIRLOTM fuel rod cladding material meet all LOCA safety criteria. For these reasons, the NRC staff determined that the underlying purpose of 10 CFR 50.46 would be achieved if the NRC granted this exemption for Turkey Point 3 and 4. Paragraph I.A.5 of 10 CFR Part 50, Appendix K requires that the rate of energy release, hydrogen generation, and cladding oxidation from the metal/ water reaction shall be calculated using the Baker-Just equation. Because the Baker-Just equation presumes the use of zircaloy clad fuel, strict application of the rule would not permit use of the equation for Optimized ZIRLOTM fuel rod cladding material for determining acceptable fuel performance. However, the NRC staff found that metal-water reaction tests performed by Westinghouse on Optimized ZIRLOTM, which were NRC-reviewed, approved, and documented in Appendix B of Addendum 1–A to WCAP–12610–P–A & CENPD–404–P–A, demonstrate conservative reaction rates relative to the Baker-Just equation. Thus, the NRC staff determined that application of Appendix K, Paragraph I.A.5 is not necessary to achieve the underlying purpose of the rule in these circumstances. Because these evaluations demonstrate that the underlying purpose of the regulations will be met, there will be no undue risk to public health and safety. D. Consistent With the Common Defense and Security The licensee’s exemption request is only to allow the application of the aforementioned regulations to an improved fuel rod cladding material. In its letter dated March 22, 2013, 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 licensee stated that use of full regions of Optimized ZIRLOTM fuel rod cladding material in the Turkey Point 3 and 4 cores will not affect plant operations. This change to the plant configuration is not related to security issues. Therefore, the NRC staff determined that this exemption does not impact common defense and security. E. 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 VerDate Mar<15>2010 17:47 Feb 27, 2014 Jkt 232001 concerning the installation or use of a facility component located within the 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 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). Requirements in 10 CFR 51.22(c)(9)(i) The NRC staff evaluated the issue of no significant hazards consideration, using the standards described in 10 CFR 50.92(c), as presented as follows: 1. Does the proposed exemption involve a significant increase in the probability or consequences of an accident previously evaluated? The proposed exemption would allow the use of Optimized ZIRLOTM fuel rod cladding material in the reactors. The NRC-approved topical report, WCAP– 12610–P–A & CENPD–404–P–A, Addendum 1–A, addresses Optimized ZIRLOTM and demonstrates that Optimized ZIRLOTM has essentially the same properties as currently licensed ZIRLO®. The fuel cladding itself is not an accident initiator and does not affect accident probability. Use of Optimized ZIRLOTM fuel rod cladding material will continue to meet all 10 CFR 50.46 acceptance criteria and, therefore, will not increase the consequences of an accident. 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? The use of Optimized ZIRLOTM fuel rod cladding material will not result in changes in the operation or configuration of the facility. Topical report WCAP–12610–P–A & CENPD– 404–P–A demonstrated that the material properties of Optimized ZIRLOTM are similar to those of standard ZIRLOTM. Therefore, Optimized ZIRLOTM fuel rod cladding material will perform similarly to those fabricated from standard ZIRLOTM, thus precluding the possibility of the fuel cladding PO 00000 Frm 00082 Fmt 4703 Sfmt 4703 11471 becoming an accident initiator and causing a new or different type of accident. Therefore, the proposed exemption 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? The proposed exemption does not involve a significant reduction in a margin of safety because it has been demonstrated that the material properties of the Optimized ZIRLOTM are not significantly different from those of standard ZIRLOTM. Optimized ZIRLOTM is expected to perform similarly to standard ZIRLOTM for all normal operating and accident scenarios, including both LOCA and non-LOCA scenarios. For LOCA scenarios, where the slight difference in Optimized ZIRLOTM material properties relative to standard ZIRLOTM could have some impact on the overall accident scenario, plant-specific LOCA analyses using Optimized ZIRLOTM properties will demonstrate that the acceptance criteria of 10 CFR 50.46 have been satisfied. Therefore, the proposed exemption 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 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified. Requirements in 10 CFR 51.22(c)(9)(ii) The proposed exemption would allow the use of Optimized ZIRLOTM fuel rod cladding material in the reactors. Optimized ZIRLOTM has essentially the same properties as the currently licensed ZIRLO®. The use of the Optimized ZIRLOTM 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 provision of 10 CFR 51.22(c)(9)(ii) is satisfied. Requirements in 10 CFR 51.22(c)(9)(iii) The proposed exemption would allow the use of the Optimized ZIRLOTM fuel rod cladding material in the reactors. Optimized ZIRLOTM has essentially the same properties as the currently licensed ZIRLO®. The use of the Optimized ZIRLOTM fuel rod cladding material will not significantly increase individual occupational radiation exposure, or significantly increase cumulative occupational radiation exposure. Therefore, the provision of 10 CFR 51.22(c)(9)(iii) is satisfied. E:\FR\FM\28FEN1.SGM 28FEN1 11472 Federal Register / Vol. 79, No. 40 / Friday, February 28, 2014 / Notices IV. Conclusions 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 the licensee an exemption from the requirements of 10 CFR 50.46 and Appendix K to 10 CFR Part 50, to allow the use of Optimized ZIRLOTM fuel rod cladding material at Turkey Point 3 and 4. This exemption is effective upon issuance. Dated at Rockville, Maryland, this 20th day of February 2014. For The Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2014–04409 Filed 2–27–14; 8:45 am] BILLING CODE 7590–01–P PEACE CORPS Information Collection Request; Submission for OMB Review Peace Corps. 60-Day notice and request for comments. AGENCY: ACTION: The Peace Corps will be submitting the following information collection request to the Office of Management and Budget (OMB) for review and approval. The purpose of this notice is to allow 60 days for public comment in the Federal Register preceding submission to OMB. We are conducting this process in accordance with the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35). DATES: Submit comments on or before April 29, 2014. ADDRESSES: Comments should be addressed to Denora Miller, FOIA/ Privacy Act Officer. Denora Miller can be contacted by telephone at 202–692– 1236 or email at pcfr@peacecorps.gov. Email comments must be made in text and not in attachments. FOR FURTHER INFORMATION CONTACT: Denora Miller at the Peace Corps address above. SUPPLEMENTARY INFORMATION: Peace Corps uses the confidential reference form in order to learn from someone, who knows a volunteer applicant and his or her background, whether the applicant possesses the necessary tkelley on DSK3SPTVN1PROD with NOTICES SUMMARY: VerDate Mar<15>2010 17:47 Feb 27, 2014 Jkt 232001 characteristics and skills to serve as a Volunteer. OMB Control Number: 0420–0006. Title: Peace Corps Confidential Reference Form. Type Of Review: Revision of a currently approved collection. Affected Public: Individuals. Respondents’ Obligation To Reply: Voluntary. Burden To The Public: a. Average Number of Annual Applicants (complete the application process): 20,000. b. Number of reference required per applicant: 2. c. Estimated Number of reference forms received: 40,000. d. Frequency of response: One time. e. Completion time: 10 minutes. f. Annual burden hours: 6,667. General Description Of Collection: The Peace Corps Confidential Reference Form provides information concerning an applicant’s skills and character from people who are familiar with the applicant. Such information exists nowhere else. The Placement team in the Office of Volunteer Recruitment and Selection uses the Peace Corps Confidential Reference Form as an integral part of the selection process to determine whether an applicant is likely to succeed as a Peace Corps volunteer. Request For Comment: Peace Corps invites comments on whether the proposed collection of information is necessary for proper performance of the functions of the Peace Corps, including whether the information will have practical use; the accuracy of the agency’s estimate of the burden of the proposed collection of information, including the validity of the information to be collected; and ways to minimize the burden of the collection of information on those who are to respond, including through the use of automated collection techniques, when appropriate, and other forms of information technology. This notice issued in Washington, DC, on: February 25, 2014. Denora Miller, FOIA/Privacy Act Officer, Management. [FR Doc. 2014–04489 Filed 2–27–14; 8:45 am] BILLING CODE 6051–01–P PEACE CORPS Information Collection Request; Submission for OMB Review Peace Corps. 60-Day notice and request for comments. AGENCY: ACTION: The Peace Corps will be submitting the following information SUMMARY: PO 00000 Frm 00083 Fmt 4703 Sfmt 4703 collection request to the Office of Management and Budget (OMB) for review and approval. The purpose of this notice is to allow 60 days for public comment in the Federal Register preceding submission to OMB. We are conducting this process in accordance with the Paperwork Reduction Act of 1995 (44 USC Chapter 35). DATES: Submit comments on or before April 29, 2014. ADDRESSES: Comments should be addressed to Denora Miller, FOIA/ Privacy Act Officer. Denora Miller can be contacted by telephone at 202–692– 1236 or email at pcfr@peacecorps.gov. Email comments must be made in text and not in attachments. FOR FURTHER INFORMATION CONTACT: Denora Miller at Peace Corps address above. The Peace Corps Questionnaire for Peace Corps Volunteer Background Investigation Form is used to conduct a formal background check. The information obtained on the form is provided to the Office of Personnel Management or other contract investigator to obtain the necessary information as to an applicant’s legal suitability for service. OMB Control Number: 0420–0001. Title: Peace Corps Questionnaire for Peace Corps Volunteer Background Investigation Form Type of Review: Revision of a currently approved collection Affected Public: Individuals Respondents’ Obligation To Reply: Voluntary. Burden to the Public: a. Number of Average Applicants: 20,000. b. Number of Applicants who submit NAC form: 20,000. c. Frequency of response: One time. d. Completion time: 15 minutes. e. Annual burden hours: 5,000. General Description Of Collection: The Peace Corps Questionnaire for Peace Corps Volunteer Background Investigation form is used to screen Peace Corps applicants for legal and/or criminal history and other involvement with the judicial system. The information obtained on the form is provided to the Office of Personnel Management or other contract investigator to obtain the necessary information as to an applicant’s legal suitability for service. All applicants who complete the initial Peace Corps Application Form are then sent a ‘‘legal kit’’ to complete, which includes this form among others related to the applicants’ suitability and a postagepaid return envelope. This form is only requested to be filled once and currently SUPPLEMENTARY INFORMATION: E:\FR\FM\28FEN1.SGM 28FEN1

Agencies

[Federal Register Volume 79, Number 40 (Friday, February 28, 2014)]
[Notices]
[Pages 11469-11472]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-04409]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-250 and 50-251; NRC-2014-0035]


License Exemption Request for Florida Power & Light Company 
Turkey Point Nuclear Generating Unit Nos. 3 and 4

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption; issuance.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is granting an 
exemption in response to a March 22, 2013, request from Florida Power & 
Light Company for an exemption for the use of a different fuel rod 
cladding material (Optimized ZIRLO\TM\).

ADDRESSES: Please refer to Docket ID NRC-2014-0035 when contacting the 
NRC about the availability of information regarding this document. You 
may access 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-2014-0035. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may access publicly available documents online in the NRC 
Library 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 pdr.resource@nrc.gov. The ADAMS accession number 
for each document referenced in this document (if that document 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: Audrey L. Klett, Office of Nuclear 
Reactor Regulation, telephone: 301-415-0489, email: 
Audrey.Klett@nrc.gov, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.

[[Page 11470]]

I. Background

    Florida Power & Light Company (the licensee) is the holder of 
Renewed Facility Operating License Nos. DPR-31 and DPR-41, which 
authorize operation of the Turkey Point Nuclear Generating Unit Nos. 3 
and 4 (Turkey Point 3 and 4), respectively. The license provides, among 
other things, that the facility is subject to all rules, regulations, 
and orders of the U.S. Nuclear Regulatory Commission (NRC) now or 
hereafter in effect. The facility consists of two pressurized water 
reactors located in Miami-Dade County, Florida.

II. Request/Action

    Pursuant to Section 50.12, ``Specific exemptions,'' of Title 10 of 
the Code of Federal Regulations (10 CFR), the licensee has, by letter 
dated March 22, 2013 (ADAMS Accession No. ML13100A131), requested an 
exemption from the requirements of 10 CFR 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 rods clad with Optimized ZIRLO\TM\ alloy for 
future reload applications. The regulations in 10 CFR 50.46 contain 
acceptance criteria for the ECCS for reactors fueled with zircaloy or 
ZIRLO fuel rod cladding material. In addition, Appendix K to 10 CFR 
Part 50 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 Optimized 
ZIRLO\TM\. The licensee requested the exemption because these 
regulations do not have provisions for the use of fuel rods clad in a 
material other than zircaloy or ZIRLO\TM\. Because the material 
specifications of Optimized ZIRLO\TM\ differ from the specification for 
zircaloy or ZIRLO\TM\, a plant-specific exemption is required to 
support the reload applications for Turkey Point 3 and 4.
    The exemption request relates solely to the cladding material 
specified in these regulations (i.e., fuel rods with Zircaloy or 
ZIRLO\TM\ cladding material). This exemption would provide for the 
application of the acceptance criteria of 10 CFR 50.46 and Appendix K 
to 10 CFR Part 50 to fuel assembly designs using Optimized ZIRLO\TM\ 
fuel rod cladding material. In its letter dated March 22, 2013, the 
licensee clarified that it was not seeking an exemption from the 
acceptance and analytical criteria of these regulations. The intent of 
the request is to allow the use of criteria set forth in these 
regulations for application to the Optimized ZIRLO\TM\ fuel rod 
cladding material.

III. Discussion

    Pursuant to 10 CFR 50.12, the Commission may, upon application by 
any interested person, grant exemptions from the requirements of 10 CFR 
Part 50, which are authorized by law, will not present an undue risk to 
the public health and safety, and are consistent with the common 
defense and security. Paragraph (a)(2)(ii) of 10 CFR 50.12 states that 
the Commission will not consider granting an exemption unless special 
circumstances are present, such as when application of the regulation 
in the particular circumstance is not necessary to achieve the 
underlying purpose of the rule.

A. 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 is not necessary to achieve the underlying purpose of the 
rule. The underlying purpose of 10 CFR 50.46 and Appendix K to 10 CFR 
Part 50 is to establish acceptance criteria for ECCS performance. The 
regulations in 10 CFR 50.46 and Appendix K are not directly applicable 
to Optimized ZIRLO\TM\, even though the evaluations described in the 
following sections of this exemption show that the intent of the 
regulation is met. Therefore, because the underlying purposes of 10 CFR 
50.46 and Appendix K of 10 CFR Part 50 are achieved through the use of 
Optimized ZIRLO\TM\ fuel rod cladding material, the special 
circumstances required by 10 CFR 50.12(a)(2)(ii) for the granting of an 
exemption exist.

B. Authorized by Law

    This exemption would allow the use of Optimized ZIRLO\TM\ fuel rod 
cladding material for future reload applications at Turkey Point 3 and 
4. Section 10 CFR 50.12 allows the NRC to grant exemptions from the 
requirements of 10 CFR Part 50. The NRC staff determined that granting 
the licensee's proposed 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.

C. No Undue Risk to Public Health and Safety

    Section 10 CFR 50.46 requires that each boiling or pressurized 
light-water nuclear power reactor fueled with uranium oxide pellets 
within cylindrical zircaloy or ZIRLO cladding must be provided with an 
ECCS that must be designed so that its calculated cooling performance 
following postulated loss-of-coolant accidents (LOCAs) conforms to the 
criteria set forth in paragraph (b) of this section. The underlying 
purpose of 10 CFR 50.46 is to establish acceptance criteria for 
adequate ECCS performance. As previously documented in the NRC staff's 
safety evaluation dated June 10, 2005 (ADAMS Accession No. 
ML051670395), of topical reports submitted by Westinghouse, and subject 
to compliance with the specific conditions of approval established in 
the safety evaluation, the NRC staff found that Westinghouse 
demonstrated the applicability of these ECCS acceptance criteria to 
Optimized ZIRLO\TM\. Ring compression tests performed by Westinghouse 
on Optimized ZIRLO\TM\ (see WCAP-14342-A & CENPD-404-NP-A at ADAMS 
Accession No. ML062080569) demonstrate an acceptable retention of 
postquench ductility up to 10 CFR 50.46 limits of 2200 degrees 
Fahrenheit and 17 percent equivalent clad reacted. Furthermore, the NRC 
staff concluded that oxidation measurements provided by the licensee by 
letter LTR-NRC-07-58 from Westinghouse to the NRC, ``SER Compliance 
with WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, `Optimized 
ZIRLO\TM\,''' dated November 6, 2007 (public version is at ADAMS 
Accession No. ML073130560), illustrate that oxide thickness and 
associated hydrogen pickup for Optimized ZIRLO\TM\ at any given burnup 
would be less than both zircaloy-4 and ZIRLO\TM\. Hence, the NRC staff 
concludes that Optimized ZIRLO\TM\ would be expected to maintain better 
postquench ductility than ZIRLO\TM\. This finding is further supported 
by an ongoing LOCA research program at Argonne National Laboratory, 
which has identified a strong correlation between cladding hydrogen 
content (caused by in-service corrosion) and postquench ductility.
    In its letter dated March 22, 2013, the licensee stated that its 
reload evaluations will ensure that acceptance criteria are met for the 
insertion of assemblies with fuel rods clad with Optimized ZILRO\TM\. 
The licensee stated that it will evaluate fuel assemblies using 
Optimized ZIRLO\TM\ fuel rod cladding material using NRC-approved 
analytical methods and plant-specific models to address the changes in 
the cladding material properties. The licensee stated that Westinghouse 
will perform an evaluation of the Turkey Point 3 and 4 cores using LOCA

[[Page 11471]]

methods approved for the site to ensure that assemblies with Optimized 
ZIRLO\TM\ fuel rod cladding material meet all LOCA safety criteria. For 
these reasons, the NRC staff determined that the underlying purpose of 
10 CFR 50.46 would be achieved if the NRC granted this exemption for 
Turkey Point 3 and 4.
    Paragraph I.A.5 of 10 CFR Part 50, Appendix K requires that the 
rate of energy release, hydrogen generation, and cladding oxidation 
from the metal/water reaction shall be calculated using the Baker-Just 
equation. Because the Baker-Just equation presumes the use of zircaloy 
clad fuel, strict application of the rule would not permit use of the 
equation for Optimized ZIRLOTM fuel rod cladding material 
for determining acceptable fuel performance. However, the NRC staff 
found that metal-water reaction tests performed by Westinghouse on 
Optimized ZIRLO\TM\, which were NRC-reviewed, approved, and documented 
in Appendix B of Addendum 1-A to WCAP-12610-P-A & CENPD-404-P-A, 
demonstrate conservative reaction rates relative to the Baker-Just 
equation. Thus, the NRC staff determined that application of Appendix 
K, Paragraph I.A.5 is not necessary to achieve the underlying purpose 
of the rule in these circumstances. Because these evaluations 
demonstrate that the underlying purpose of the regulations will be met, 
there will be no undue risk to public health and safety.

D. Consistent With the Common Defense and Security

    The licensee's exemption request is only to allow the application 
of the aforementioned regulations to an improved fuel rod cladding 
material. In its letter dated March 22, 2013, 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 
licensee stated that use of full regions of Optimized ZIRLO\TM\ fuel 
rod cladding material in the Turkey Point 3 and 4 cores will not affect 
plant operations. This change to the plant configuration is not related 
to security issues. Therefore, the NRC staff determined that this 
exemption does not impact common defense and security.

E. 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 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 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).
Requirements in 10 CFR 51.22(c)(9)(i)
    The NRC staff evaluated the issue of no significant hazards 
consideration, using the standards described in 10 CFR 50.92(c), as 
presented as follows:
    1. Does the proposed exemption involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    The proposed exemption would allow the use of Optimized ZIRLO\TM\ 
fuel rod cladding material in the reactors. The NRC-approved topical 
report, WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, addresses 
Optimized ZIRLO\TM\ and demonstrates that Optimized ZIRLO\TM\ has 
essentially the same properties as currently licensed ZIRLO[supreg]. 
The fuel cladding itself is not an accident initiator and does not 
affect accident probability. Use of Optimized ZIRLO\TM\ fuel rod 
cladding material will continue to meet all 10 CFR 50.46 acceptance 
criteria and, therefore, will not increase the consequences of an 
accident. 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?
    The use of Optimized ZIRLO\TM\ fuel rod cladding material will not 
result in changes in the operation or configuration of the facility. 
Topical report WCAP-12610-P-A & CENPD-404-P-A demonstrated that the 
material properties of Optimized ZIRLO\TM\ are similar to those of 
standard ZIRLO\TM\. Therefore, Optimized ZIRLO\TM\ fuel rod cladding 
material will perform similarly to those fabricated from standard 
ZIRLO\TM\, thus precluding the possibility of the fuel cladding 
becoming an accident initiator and causing a new or different type of 
accident. Therefore, the proposed exemption 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?
    The proposed exemption does not involve a significant reduction in 
a margin of safety because it has been demonstrated that the material 
properties of the Optimized ZIRLO\TM\ are not significantly different 
from those of standard ZIRLO\TM\. Optimized ZIRLO\TM\ is expected to 
perform similarly to standard ZIRLO\TM\ for all normal operating and 
accident scenarios, including both LOCA and non-LOCA scenarios. For 
LOCA scenarios, where the slight difference in Optimized ZIRLO\TM\ 
material properties relative to standard ZIRLO\TM\ could have some 
impact on the overall accident scenario, plant-specific LOCA analyses 
using Optimized ZIRLO\TM\ properties will demonstrate that the 
acceptance criteria of 10 CFR 50.46 have been satisfied. Therefore, the 
proposed exemption 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 10 CFR 50.92(c), and, accordingly, a finding of 
no significant hazards consideration is justified.
Requirements in 10 CFR 51.22(c)(9)(ii)
    The proposed exemption would allow the use of Optimized ZIRLO\TM\ 
fuel rod cladding material in the reactors. Optimized ZIRLO\TM\ has 
essentially the same properties as the currently licensed 
ZIRLO[supreg]. The use of the Optimized ZIRLO\TM\ 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 provision of 10 CFR 
51.22(c)(9)(ii) is satisfied.
Requirements in 10 CFR 51.22(c)(9)(iii)
    The proposed exemption would allow the use of the Optimized 
ZIRLO\TM\ fuel rod cladding material in the reactors. Optimized 
ZIRLO\TM\ has essentially the same properties as the currently licensed 
ZIRLO[supreg]. The use of the Optimized ZIRLO\TM\ fuel rod cladding 
material will not significantly increase individual occupational 
radiation exposure, or significantly increase cumulative occupational 
radiation exposure. Therefore, the provision of 10 CFR 51.22(c)(9)(iii) 
is satisfied.

[[Page 11472]]

IV. Conclusions

    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 the licensee an exemption from 
the requirements of 10 CFR 50.46 and Appendix K to 10 CFR Part 50, to 
allow the use of Optimized ZIRLO\TM\ fuel rod cladding material at 
Turkey Point 3 and 4.
    This exemption is effective upon issuance.

    Dated at Rockville, Maryland, this 20th day of February 2014.

    For The Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2014-04409 Filed 2-27-14; 8:45 am]
BILLING CODE 7590-01-P