83 FR 9550 - FirstEnergy Nuclear Operating Company; Beaver Valley Power Station; Unit Nos. 1 and 2; Use of Optimized ZIRLOTM
NUCLEAR REGULATORY COMMISSION Federal Register Volume 83, Issue 44 (March 6, 2018)
Federal Register Volume 83, Issue 44 (March 6, 2018)
| Page Range | 9550-9552 | |
| FR Document | 2018-04549 |
[Federal Register Volume 83, Number 44 (Tuesday, March 6, 2018)] [Notices] [Pages 9550-9552] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2018-04549] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-334 and 50-412; NRC-2018-0041] FirstEnergy Nuclear Operating Company; Beaver Valley Power Station; Unit Nos. 1 and 2; Use of Optimized ZIRLO\TM\ Fuel Rod Cladding AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to an April 9, 2017, request from FirstEnergy Nuclear Operating Company (FENOC), in order to use Optimized ZIRLO\TM\ fuel rod cladding at the Beaver Valley Power Station, Unit Nos. 1 and 2 (Beaver Valley). DATES: The exemption was issued on March 6, 2018. ADDRESSES: Please refer to Docket ID NRC-2018-0041 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods:Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0041. Address questions about NRC dockets to Jennifer Borges; telephone: 301-287- 9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain 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 pdr.resource@nrc.gov. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. In addition, for the convenience of the reader, the ADAMS accession numbers are provided in a table in the ``Availability of Documents'' section of this document. NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Tanya E. Hood, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1387, email: Tanya.Hood@nrc.gov. SUPPLEMENTARY INFORMATION: I. Background The FirstEnergy Nuclear Operating Company (FENOC) is the holder of Renewed Facility Operating License Nos. 50-334 and 50-412, which authorize operation of Beaver Valley. The licenses provide, among other things, that the facilities are subject to all rules, regulations, and orders of the NRC now or hereafter in effect. The facilities consist of pressurized-water reactors located in Shippingport Borough on the Ohio River in Beaver County, Pennsylvania. The ZIRLO[supreg] corrosion model was based on a model originally developed for zircaloy-4 cladding. As utilities moved to increased fuel thermal duty associated with higher peaking factors, uprated core power, and longer cycle lengths, cladding corrosion has become one of the important factors in assessing the potential for increased fuel thermal duty. II. Request/Action Pursuant to title 10 of the Code of Federal Regulations (10 CFR) section 50.12, ``Specific exemptions,'' the [[Page 9551]] licensee requested, by letter dated April 9, 2017 (ADAMS Accession No. ML17100A269), an exemption from Sec. 50.46, ``Acceptance criteria for emergency core cooling systems [ECCS] for light-water nuclear power reactors,'' and 10 CFR part 50, appendix K, ``ECCS Evaluation Models,'' to allow the use of Optimized ZIRLOTM fuel rod cladding for future core reload applications. The regulations in Sec. 50.46 contain acceptance criteria for the ECCS for reactors fueled with zircaloy or ZIRLO[supreg] fuel rod cladding material. In addition, 10 CFR part 50, appendix K, requires that the Baker-Just equation be used to predict the rates of energy release, hydrogen concentration, and cladding oxidation from the metal/water reaction. The Baker-Just equation assumes the use of a zirconium alloy different from Optimized ZIRLO\TM\ material. Therefore, an exemption to Sec. 50.46 and 10 CFR part 50, appendix K, is required to support the use of Optimized ZIRLO\TM\ fuel rod cladding at Beaver Valley. The exemption request relates solely to the specific types of cladding material specified in these regulations for use in light-water reactors (i.e., fuel rods with zircaloy or ZIRLO[supreg] cladding). This request will provide for the application of the acceptance criteria of Sec. 50.46 and 10 CFR, part 50, appendix K, to fuel assembly designs using Optimized ZIRLO\TM\ fuel rod cladding. III. Discussion Pursuant to Sec. 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR part 50 when: (1) The exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. Under Sec. 50.12(a)(2), special circumstances include, among other things, when application of the specific regulation in the particular circumstance would not serve, or is not necessary to achieve, the underlying purpose of the rule. The Optimized ZIRLOTM fuel cladding is different from standard ZIRLO[supreg] in two respects: (1) The tin content is lower and (2) the microstructure is different. This difference in tin content and microstructure can lead to differences in some material properties. Westinghouse Electric Company (Westinghouse), the manufacturer of Optimized ZIRLO\TM\ fuel rod cladding, has committed to provide irradiated data and validate fuel performance models ahead of burnups achieved in batch application (i.e., a group of fuel assemblies). The NRC staff's safety evaluation of Optimized ZIRLO\TM\ (WCAP- 12610-P-A & CENPD-404-P-A) dated June 10, 2005 (ADAMS Package Accession No. ML051670395), included ten conditions and limitations. The NRC staff reviewed FENOC's April 9, 2017, application against these specific conditions and concluded that the licensee is in compliance with all of the applicable conditions, with the exception of Conditions 6 and 7. Conditions 6 and 7 relate to validating in-reactor performance and fuel performance models based on lead test assembly data obtained ahead of batch application. Westinghouse provided additional information from irradiation programs to comply with Conditions 6 and 7 of the NRC staff's safety evaluation, by letters dated February 25, 2013 (ADAMS Accession No. ML13070A188), and February 9, 2015 (ADAMS Accession No. ML15051A427), demonstrating compliance with these two conditions. One of the main objectives of the ongoing Westinghouse creep (growth) program was to confirm the adequacy of the Westinghouse Performance Analysis and Design Model creep models for Optimized ZIRLOTM and verify that the steady state irradiation creep rate is the same in tension and compression. Based upon the supporting data provided by Westinghouse in Figures 3 through 6 of WCAP-12610-P-A & CENPD-404-P-A Addendum 1-A (ADAMS Accession No. ML13070A189), the NRC staff determined that the creep models are adequate for the first operating cycle where the fuel rod cladding is predominately in compressive creep. The NRC staff performed its review of Conditions 6 and 7 in a letter dated August 3, 2016 (ADAMS Accession No. ML16173A354). The NRC staff determined that the data provided in Westinghouse letters dated February 25, 2013, and February 9, 2015, satisfy Conditions 6 and 7. Therefore, licensees no longer need to provide additional data when referencing WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, ``Optimized ZIRLO\TM\,'' July 2006, in future license amendment requests. The licensee provided documentation of its compliance with the Westinghouse topical report WCAP-12610-P-A & CENPD-404-P-A Addendum 1-A commitments in its application. Based on that documentation and the information contained in Westinghouse's revised compliance letters dated February 25, 2013, and February 9, 2015, the NRC staff finds the licensee's compliance with safety evaluation Conditions 6 and 7 is acceptable. A. The Exemption Is Authorized by Law This exemption would allow the use of Optimized ZIRLO\TM\ fuel rod cladding material at Beaver Valley. As stated above, Sec. 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR part 50. The fuel that will be irradiated at Beaver Valley contains cladding material that does not conform to the cladding material that is explicitly defined in 10 CFR 50.46 and implicitly defined in 10 CFR part 50, appendix K. However, the criteria of these regulations will continue to be satisfied for the operation of the Beaver Valley cores containing Optimized ZIRLOTM fuel cladding. The NRC staff has 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. B. The Exemption Presents No Undue Risk to Public Health and Safety The objectives of Sec. 50.46(b)(2) and (b)(3) and 10 CFR part 50, appendix K, section I.A.5, are to ensure that cladding oxidation and hydrogen generation are appropriately limited during loss-of-coolant accidents and conservatively accounted for in ECCS evaluation models. As previously documented in the NRC staff's safety evaluation of topical reports submitted by Westinghouse, dated June 10, 2005, 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 the ECCS acceptance criteria to Optimized ZIRLOTM. The NRC staff concluded that oxidation measurements provided by the licensee in the letter from Westinghouse to the NRC, dated November 2007 (ADAMS Accession No. ML073130560), illustrate that oxide thickness and associated hydrogen pickup for Optimized ZIRLOTM at any given burnup would be less than those of both zircaloy-4 and ZIRLO[supreg]. The NRC staff previously found that metal-water reaction tests performed by Westinghouse on Optimized ZIRLOTM (see appendix B of WCAP-12610-P-A & CENPD-404-P-A Addendum 1-A) demonstrate conservative reaction rates relative to the Baker-Just equation. Thus, the NRC staff determined that the application of appendix K, section I.A.5, is not necessary to achieve the underlying purpose of the rule in these circumstances. Since these evaluations demonstrate that the underlying [[Page 9552]] purpose of the rule will be met, there will be no undue risk to the public health and safety. The facility operating licenses require that reload cores be operated in accordance with the operating limits specified in the technical specifications and core operating limits report. Thus, the granting of this exemption request will not pose an undue risk to public health and safety. C. The Exemption Is Consistent With the Common Defense and Security The exemption request would allow the licensee to use an improved fuel rod cladding material. In its letter dated April 9, 2017, 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. Use of Optimized ZIRLOTM fuel rod cladding in the Beaver Valley cores will not adversely affect plant operations. Therefore, the NRC staff has determined that this exemption does not adversely impact common defense and security. D. Special Circumstances Special circumstances, in accordance with Sec. 50.12(a)(2)(ii), are present whenever application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule. The underlying purpose of Sec. 50.46 and 10 CFR part 50, appendix K, is to establish acceptance criteria for ECCS performance. The regulations ensure that nuclear power reactors fueled with uranium oxide pellets within zircaloy or ZIRLO[supreg] cladding must be provided with an ECCS designed to provide core cooling following postulated loss-of-coolant accidents. Westinghouse demonstrated in its NRC-approved topical report WCAP-12610-P-A & CENPD-404-P-A Addendum 1-A that ECCS effectiveness will not be adversely affected by a change from zircaloy or ZIRLO[supreg] clad fuel to Optimized ZIRLOTM clad fuel. Normal safety analyses performed prior to core reload will confirm that there is no adverse impact on ECCS performance. Therefore, since the underlying purposes of Sec. 50.46 and 10 CFR part 50, appendix K, are achieved through the use of Optimized ZIRLO\TM\ fuel rod cladding material, the special circumstances required by Sec. 50.12(a)(2)(ii) for the granting of an exemption exist. E. Environmental Considerations The NRC staff determined that the exemption discussed herein meets the eligibility criteria for the categorical exclusion set forth in Sec. 51.22(c)(9) because it is related to a requirement concerning the installation or use of a facility component located within the restricted area, as defined in 10 CFR part 20, and the granting of this exemption involves: (1) No significant hazards consideration, (2) no significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, and (3) no significant increase in individual or cumulative occupational radiation exposure. Therefore, in accordance with Sec. 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the NRC staff's consideration of this exemption request. The basis for the NRC staff's determination is discussed in an evaluation of the requirements of Sec. 51.22(c)(9) in the proposed no significant hazards consideration determination for the associated amendment as published in the Federal Register on July 18, 2017 (82 FR 32881). IV. Availability of Documents The NRC is making the documents identified below available to interested persons through one or more of the following methods, as indicated. To access documents related to this action, see ADDRESSES Section of this document. ------------------------------------------------------------------------ Document ADAMS accession No. ------------------------------------------------------------------------ Beaver Valley Power Station, Unit Nos. 1 ML17100A269 and 2, ``License Amendment Request to Modify Technical Specifications 4.2.1 and 5.6.3 and a 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO\TM\ Fuel Rod Cladding'' (April 9, 2017). Westinghouse--Final Safety Evaluation ML051670395 for Addendum 1 to Topical Report WCAP- 12610-P-A & CENPD-404-P-A Addendum 1-A, ``Optimized ZIRLO\TM\'' (June 10, 2005). Westinghouse--LTR-NRC-13-6, NP- ML13070A188 Attachment--SER Compliance with WCAP[dash]12610-P-A & CENPD-404-P-A Addendum 1-A ``Optimized ZIRLO\TM\'' (February 25, 2013). Westinghouse--LTR-NRC-15-7, Submittal of ML15051A427 Responses to Draft RAIs and Revisions to Select Figures in LTR-NRC-13-6 to Fulfill Conditions 6 and 7 of the Safety Evaluation for WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A (February 9, 2015). Westinghouse--LTR-NRC-13-6, NP- ML13070A189 Attachment, SER Compliance of WCAP- 12610-P-A & CENPD-404-P-A Addendum 1-A (Non-Proprietary) ``Optimized ZIRLO\TM\''(February 2013). Satisfaction of Conditions 6 & 7 of the ML16173A354 Safety Evaluation for WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A ``Optimized ZIRLO\TM\'' Topical Report. SER Compliance with WCAP-12610-P-A & ML073130560 CENPD-404-P-A Addendum 1-A, ``Optimized ZIRLO\TM\'' (Non-Proprietary) (November 2007). ------------------------------------------------------------------------ V. Conclusion Accordingly, the Commission has determined that pursuant to Sec. 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 FENOC an exemption from the requirements of Sec. 50.46 and 10 CFR part 50, appendix K, to allow the use of Optimized ZIRLO\TM\ fuel rod cladding material at Beaver Valley. Dated at Rockville, Maryland, this 1st day of March 2018. For the Nuclear Regulatory Commission. Joseph G. Giitter, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2018-04549 Filed 3-5-18; 8:45 am] BILLING CODE 7590-01-P
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FOR FURTHER INFORMATION CONTACT: stakeholders. Sharing information on the Hub individual listed in the FOR FURTHER
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2. Make the following conforming changes:
Access and Management System
Value Engineering (VE) is a (ADAMS): You may obtain publicly-
a. Delete paragraph f. from section 7, which
management technique that is used to refers to reporting. available documents online in the
analyze activities and identify b. Delete the Attachment to the Circular, ADAMS Public Documents collection at
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are set forth in OMB Circular A–131 at email to pdr.resource@nrc.gov. The
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Administration’s efforts to emphasize the Circular.
addition, for the convenience of the
critical thinking and analysis instead of Lesley A. Field, reader, the ADAMS accession numbers
compliance activity and documentation. Deputy Administrator for Federal are provided in a table in the
Although several Federal agencies have Procurement Policy. ‘‘Availability of Documents’’ section of
reported life-cycle savings in a broad [FR Doc. 2018–04445 Filed 3–5–18; 8:45 am] this document.
range of acquisition programs, including
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purchase copies of public documents at
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VE by federal agencies has been limited.
NUCLEAR REGULATORY White Flint North, 11555 Rockville
OFPP believes agency workforce
COMMISSION Pike, Rockville, Maryland 20852.
awareness and consideration of VE can
be improved by redirecting agency [Docket Nos. 50–334 and 50–412; NRC– FOR FURTHER INFORMATION CONTACT:
resources away from compliance 2018–0041] Tanya E. Hood, Office of Nuclear
reporting and towards information Reactor Regulation, U.S. Nuclear
sharing with other agencies on use of FirstEnergy Nuclear Operating Regulatory Commission, Washington,
the tool through the Acquisition Company; Beaver Valley Power DC 20555–0001; telephone: 301–415–
Gateway (https://hallways.cap.gsa.gov/ Station; Unit Nos. 1 and 2; Use of 1387, email: Tanya.Hood@nrc.gov.
login-information). The Gateway Optimized ZIRLOTM Fuel Rod Cladding SUPPLEMENTARY INFORMATION:
provides federal buyers with a forum for AGENCY: Nuclear Regulatory I. Background
improving government acquisition. The Commission.
Acquisition Innovation Hub within the The FirstEnergy Nuclear Operating
ACTION: Exemption; issuance. Company (FENOC) is the holder of
Gateway facilitates information sharing
with tools and resources for acquisition SUMMARY: The U.S. Nuclear Regulatory Renewed Facility Operating License
professionals and other stakeholders. Commission (NRC) is issuing an Nos. 50–334 and 50–412, which
These actions are called for by OMB exemption in response to an April 9, authorize operation of Beaver Valley.
Memorandum M–17–26, ‘‘Reducing 2017, request from FirstEnergy Nuclear The licenses provide, among other
Burden for Federal Agencies by Operating Company (FENOC), in order things, that the facilities are subject to
Rescinding and Modifying OMB to use Optimized ZIRLOTM fuel rod all rules, regulations, and orders of the
Memoranda.’’ Memorandum M–17–26 cladding at the Beaver Valley Power NRC now or hereafter in effect. The
was designed to eliminate inefficiencies Station, Unit Nos. 1 and 2 (Beaver facilities consist of pressurized-water
created by past OMB direction and Valley). reactors located in Shippingport
improve the efficiency of government Borough on the Ohio River in Beaver
operations. DATES: The exemption was issued on County, Pennsylvania. The ZIRLO®
Accordingly, OFPP proposes the March 6, 2018. corrosion model was based on a model
following changes to Circular A–131, as ADDRESSES: Please refer to Docket ID originally developed for zircaloy-4
revised in December 2013: NRC–2018–0041 when contacting the cladding. As utilities moved to
1. Replace section 8, entitled ‘‘Reports to
NRC about the availability of increased fuel thermal duty associated
OMB’’ with the following new section 8: information regarding this document. with higher peaking factors, uprated
Information Sharing. Agencies are You may obtain publicly-available core power, and longer cycle lengths,
encouraged to share best practices, case information related to this document cladding corrosion has become one of
using any of the following methods:
sradovich on DSK3GMQ082PROD with NOTICES
studies and other information about their the important factors in assessing the
experience using VE on the Acquisition • Federal Rulemaking website: Go to potential for increased fuel thermal
Gateway (https://hallways.cap.gsa.gov/login- http://www.regulations.gov and search duty.
information). The Gateway connects federal for Docket ID NRC–2018–0041. Address
buyers with resources and tools to improve II. Request/Action
acquisition throughout the government. The questions about NRC dockets to Jennifer
Acquisition Innovation Hub within the Borges; telephone: 301–287–9127; Pursuant to title 10 of the Code of
Gateway facilitates information sharing email: Jennifer.Borges@nrc.gov. For Federal Regulations (10 CFR) section
between acquisition professionals and other technical questions, contact the 50.12, ‘‘Specific exemptions,’’ the
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licensee requested, by letter dated April achieved in batch application (i.e., a with safety evaluation Conditions 6 and
9, 2017 (ADAMS Accession No. group of fuel assemblies). 7 is acceptable.
ML17100A269), an exemption from The NRC staff’s safety evaluation of
Optimized ZIRLOTM (WCAP–12610–P– A. The Exemption Is Authorized by Law
§ 50.46, ‘‘Acceptance criteria for
emergency core cooling systems [ECCS] A & CENPD–404–P–A) dated June 10, This exemption would allow the use
for light-water nuclear power reactors,’’ 2005 (ADAMS Package Accession No. of Optimized ZIRLOTM fuel rod
and 10 CFR part 50, appendix K, ‘‘ECCS ML051670395), included ten conditions cladding material at Beaver Valley. As
Evaluation Models,’’ to allow the use of and limitations. The NRC staff reviewed stated above, § 50.12 allows the NRC to
Optimized ZIRLOTM fuel rod cladding FENOC’s April 9, 2017, application grant exemptions from the requirements
for future core reload applications. The against these specific conditions and of 10 CFR part 50. The fuel that will be
regulations in § 50.46 contain concluded that the licensee is in irradiated at Beaver Valley contains
acceptance criteria for the ECCS for compliance with all of the applicable cladding material that does not conform
reactors fueled with zircaloy or ZIRLO® conditions, with the exception of to the cladding material that is
fuel rod cladding material. In addition, Conditions 6 and 7. explicitly defined in 10 CFR 50.46 and
10 CFR part 50, appendix K, requires Conditions 6 and 7 relate to validating implicitly defined in 10 CFR part 50,
that the Baker-Just equation be used to in-reactor performance and fuel appendix K. However, the criteria of
predict the rates of energy release, performance models based on lead test these regulations will continue to be
hydrogen concentration, and cladding assembly data obtained ahead of batch satisfied for the operation of the Beaver
oxidation from the metal/water reaction. application. Westinghouse provided Valley cores containing Optimized
The Baker-Just equation assumes the use additional information from irradiation ZIRLOTM fuel cladding. The NRC staff
of a zirconium alloy different from programs to comply with Conditions 6 has determined that granting the
Optimized ZIRLOTM material. and 7 of the NRC staff’s safety licensee’s proposed exemption would
Therefore, an exemption to § 50.46 and evaluation, by letters dated February 25, not result in a violation of the Atomic
10 CFR part 50, appendix K, is required 2013 (ADAMS Accession No. Energy Act of 1954, as amended, or the
to support the use of Optimized ML13070A188), and February 9, 2015 Commission’s regulations. Therefore,
ZIRLOTM fuel rod cladding at Beaver (ADAMS Accession No. ML15051A427), the exemption is authorized by law.
Valley. demonstrating compliance with these
B. The Exemption Presents No Undue
The exemption request relates solely two conditions.
Risk to Public Health and Safety
to the specific types of cladding material One of the main objectives of the
specified in these regulations for use in ongoing Westinghouse creep (growth) The objectives of § 50.46(b)(2) and
light-water reactors (i.e., fuel rods with program was to confirm the adequacy of (b)(3) and 10 CFR part 50, appendix K,
zircaloy or ZIRLO® cladding). This the Westinghouse Performance Analysis section I.A.5, are to ensure that cladding
request will provide for the application and Design Model creep models for oxidation and hydrogen generation are
of the acceptance criteria of § 50.46 and Optimized ZIRLOTM and verify that the appropriately limited during loss-of-
10 CFR, part 50, appendix K, to fuel steady state irradiation creep rate is the coolant accidents and conservatively
assembly designs using Optimized same in tension and compression. Based accounted for in ECCS evaluation
ZIRLOTM fuel rod cladding. upon the supporting data provided by models. As previously documented in
Westinghouse in Figures 3 through 6 of the NRC staff’s safety evaluation of
III. Discussion WCAP–12610–P–A & CENPD–404–P–A topical reports submitted by
Pursuant to § 50.12, the Commission Addendum 1–A (ADAMS Accession No. Westinghouse, dated June 10, 2005, and
may, upon application by any interested ML13070A189), the NRC staff subject to compliance with the specific
person or upon its own initiative, grant determined that the creep models are conditions of approval established in
exemptions from the requirements of 10 adequate for the first operating cycle the safety evaluation, the NRC staff
CFR part 50 when: (1) The exemptions where the fuel rod cladding is found that Westinghouse demonstrated
are authorized by law, will not present predominately in compressive creep. the applicability of the ECCS acceptance
an undue risk to public health or safety, The NRC staff performed its review of criteria to Optimized ZIRLOTM. The
and are consistent with the common Conditions 6 and 7 in a letter dated NRC staff concluded that oxidation
defense and security; and (2) when August 3, 2016 (ADAMS Accession No. measurements provided by the licensee
special circumstances are present. ML16173A354). The NRC staff in the letter from Westinghouse to the
Under § 50.12(a)(2), special determined that the data provided in NRC, dated November 2007 (ADAMS
circumstances include, among other Westinghouse letters dated February 25, Accession No. ML073130560), illustrate
things, when application of the specific 2013, and February 9, 2015, satisfy that oxide thickness and associated
regulation in the particular Conditions 6 and 7. Therefore, licensees hydrogen pickup for Optimized
circumstance would not serve, or is not no longer need to provide additional ZIRLOTM at any given burnup would be
necessary to achieve, the underlying data when referencing WCAP–12610–P– less than those of both zircaloy-4 and
purpose of the rule. A & CENPD–404–P–A, Addendum 1–A, ZIRLO®.
The Optimized ZIRLOTM fuel ‘‘Optimized ZIRLOTM,’’ July 2006, in The NRC staff previously found that
cladding is different from standard future license amendment requests. metal-water reaction tests performed by
ZIRLO® in two respects: (1) The tin The licensee provided documentation Westinghouse on Optimized ZIRLOTM
content is lower and (2) the of its compliance with the (see appendix B of WCAP–12610–P–A &
microstructure is different. This Westinghouse topical report WCAP– CENPD–404–P–A Addendum 1–A)
difference in tin content and 12610–P–A & CENPD–404–P–A demonstrate conservative reaction rates
sradovich on DSK3GMQ082PROD with NOTICES
microstructure can lead to differences in Addendum 1–A commitments in its relative to the Baker-Just equation.
some material properties. Westinghouse application. Based on that Thus, the NRC staff determined that the
Electric Company (Westinghouse), the documentation and the information application of appendix K, section I.A.5,
manufacturer of Optimized ZIRLOTM contained in Westinghouse’s revised is not necessary to achieve the
fuel rod cladding, has committed to compliance letters dated February 25, underlying purpose of the rule in these
provide irradiated data and validate fuel 2013, and February 9, 2015, the NRC circumstances. Since these evaluations
performance models ahead of burnups staff finds the licensee’s compliance demonstrate that the underlying
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purpose of the rule will be met, there in the particular circumstances is not exclusion set forth in § 51.22(c)(9)
will be no undue risk to the public necessary to achieve the underlying because it is related to a requirement
health and safety. The facility operating purpose of the rule. The underlying concerning the installation or use of a
licenses require that reload cores be purpose of § 50.46 and 10 CFR part 50, facility component located within the
operated in accordance with the appendix K, is to establish acceptance restricted area, as defined in 10 CFR
operating limits specified in the criteria for ECCS performance. The part 20, and the granting of this
technical specifications and core regulations ensure that nuclear power exemption involves: (1) No significant
operating limits report. Thus, the reactors fueled with uranium oxide hazards consideration, (2) no significant
granting of this exemption request will pellets within zircaloy or ZIRLO® change in the types or a significant
not pose an undue risk to public health cladding must be provided with an increase in the amounts of any effluents
and safety. ECCS designed to provide core cooling that may be released offsite, and (3) no
following postulated loss-of-coolant significant increase in individual or
C. The Exemption Is Consistent With the
accidents. Westinghouse demonstrated cumulative occupational radiation
Common Defense and Security
in its NRC-approved topical report exposure. Therefore, in accordance with
The exemption request would allow WCAP–12610–P–A & CENPD–404–P–A § 51.22(b), no environmental impact
the licensee to use an improved fuel rod Addendum 1–A that ECCS effectiveness statement or environmental assessment
cladding material. In its letter dated will not be adversely affected by a need be prepared in connection with the
April 9, 2017, the licensee stated that all change from zircaloy or ZIRLO® clad NRC staff’s consideration of this
the requirements and acceptance criteria fuel to Optimized ZIRLOTM clad fuel. exemption request. The basis for the
will be maintained. The licensee is Normal safety analyses performed prior NRC staff’s determination is discussed
required to handle and control special to core reload will confirm that there is in an evaluation of the requirements of
nuclear material in these assemblies in no adverse impact on ECCS § 51.22(c)(9) in the proposed no
accordance with its approved performance. Therefore, since the significant hazards consideration
procedures. Use of Optimized ZIRLOTM underlying purposes of § 50.46 and 10 determination for the associated
fuel rod cladding in the Beaver Valley CFR part 50, appendix K, are achieved amendment as published in the Federal
cores will not adversely affect plant through the use of Optimized ZIRLOTM Register on July 18, 2017 (82 FR 32881).
operations. Therefore, the NRC staff has fuel rod cladding material, the special
IV. Availability of Documents
determined that this exemption does not circumstances required by
adversely impact common defense and § 50.12(a)(2)(ii) for the granting of an The NRC is making the documents
security. exemption exist. identified below available to interested
persons through one or more of the
D. Special Circumstances E. Environmental Considerations following methods, as indicated. To
Special circumstances, in accordance The NRC staff determined that the access documents related to this action,
with § 50.12(a)(2)(ii), are present exemption discussed herein meets the see ADDRESSES Section of this
whenever application of the regulation eligibility criteria for the categorical document.
ADAMS
Document accession No.
Beaver Valley Power Station, Unit Nos. 1 and 2, ‘‘License Amendment Request to Modify Technical Specifications 4.2.1 and ML17100A269
5.6.3 and a 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLOTM Fuel Rod Cladding’’ (April 9, 2017).
Westinghouse—Final Safety Evaluation for Addendum 1 to Topical Report WCAP–12610–P–A & CENPD–404–P–A Adden- ML051670395
dum 1–A, ‘‘Optimized ZIRLOTM’’ (June 10, 2005).
Westinghouse—LTR–NRC–13–6, NP-Attachment—SER Compliance with WCAP-12610–P–A & CENPD–404–P–A Addendum ML13070A188
1–A ‘‘Optimized ZIRLOTM’’ (February 25, 2013).
Westinghouse—LTR–NRC–15–7, Submittal of Responses to Draft RAIs and Revisions to Select Figures in LTR–NRC–13–6 ML15051A427
to Fulfill Conditions 6 and 7 of the Safety Evaluation for WCAP–12610–P–A & CENPD–404–P–A, Addendum 1–A (Feb-
ruary 9, 2015).
Westinghouse—LTR–NRC–13–6, NP-Attachment, SER Compliance of WCAP–12610–P–A & CENPD–404–P–A Addendum ML13070A189
1–A (Non-Proprietary) ‘‘Optimized ZIRLOTM’’(February 2013).
Satisfaction of Conditions 6 & 7 of the Safety Evaluation for WCAP–12610–P–A and CENPD–404–P–A, Addendum 1–A ‘‘Op- ML16173A354
timized ZIRLOTM’’ Topical Report.
SER Compliance with WCAP–12610–P–A & CENPD–404–P–A Addendum 1–A, ‘‘Optimized ZIRLOTM’’ (Non-Proprietary) (No- ML073130560
vember 2007).
V. Conclusion Therefore, the Commission hereby For the Nuclear Regulatory Commission.
Accordingly, the Commission has grants FENOC an exemption from the Joseph G. Giitter,
determined that pursuant to § 50.12, the requirements of § 50.46 and 10 CFR part Director, Division of Operating Reactor
exemption is authorized by law, will not 50, appendix K, to allow the use of Licensing, Office of Nuclear Reactor
Optimized ZIRLOTM fuel rod cladding Regulation.
present an undue risk to the public
health and safety, and is consistent with material at Beaver Valley. [FR Doc. 2018–04549 Filed 3–5–18; 8:45 am]
sradovich on DSK3GMQ082PROD with NOTICES
the common defense and security. Also, Dated at Rockville, Maryland, this 1st day BILLING CODE 7590–01–P
special circumstances are present. of March 2018.
VerDate Sep<11>2014 21:39 Mar 05, 2018 Jkt 244001 PO 00000 Frm 00079 Fmt 4703 Sfmt 9990 E:\FR\FM\06MRN1.SGM 06MRN1](https://thefederalregister.org/doc/83_FR_9594/page/3.svg)
Document Created: 2018-11-01 08:48:56
Document Modified: 2018-11-01 08:48:56
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Exemption; issuance. | |
| Dates | The exemption was issued on March 6, 2018. | |
| Contact | Tanya E. Hood, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1387, email: [email protected] | |
| FR Citation | 83 FR 9550 |
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