81 FR 42756 - Duke Energy Carolinas, LLC and North Carolina Electric Membership Corporation; Acceptance Criteria for Emergency Core Cooling Systems, McGuire Nuclear Station, Units 1 and 2, Catawba Nuclear Station, Units 1 and 2
NUCLEAR REGULATORY COMMISSION Federal Register Volume 81, Issue 126 (June 30, 2016)
Federal Register Volume 81, Issue 126 (June 30, 2016)
| Page Range | 42756-42759 | |
| FR Document | 2016-15548 |
[Federal Register Volume 81, Number 126 (Thursday, June 30, 2016)] [Notices] [Pages 42756-42759] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2016-15548] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-369 and 50-370; NRC-2016-0128] Duke Energy Carolinas, LLC and North Carolina Electric Membership Corporation; Acceptance Criteria for Emergency Core Cooling Systems, McGuire Nuclear Station, Units 1 and 2, Catawba Nuclear Station, Units 1 and 2 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a license amendment request and exemption request dated August 20, 2015, from Duke Energy Carolinas, LLC (Duke Energy or the licensee) from portions of the regulations to support the use of fuel that is clad in Optimized ZIRLO\TM\. ADDRESSES: Please refer to Docket ID NRC-2016-0128 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods:Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2016-0128. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to [email protected]. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: G. Edward Miller, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-2481, email [email protected]. SUPPLEMENTARY INFORMATION: I. Background Duke Energy is the holder of Facility Operating License Nos. NPF-9, NPF-17, NPF-35, and NPF-52, which authorize operation of the McGuire Nuclear Station (MNS), Units 1 and 2, and Catawba Nuclear Station (CNS), Units 1 and 2. The licenses provide, among other things, that each facility is subject to all rules, regulations, and orders of the NRC now or hereafter in effect. The MNS and CNS units are pressurized-water reactor located in Mecklenburg County, North Carolina, and York County, South Carolina, respectively. II. Request/Action Pursuant to section 50.12 of title 10 of the Code of Federal Regulations (10 [[Page 42757]] CFR), ``Specific Exemptions,'' the licensee has, by letter dated August 20, 2015 (ADAMS Accession No. ML15295A016), requested an exemption from 10 CFR 50.46, ``Acceptance criteria for emergency core cooling systems [ECCS] for light-water nuclear power reactors,'' and appendix K to 10 CFR part 50, ``ECCS Evaluation Models'' to allow the use of fuel rods clad with Optimized ZIRLO\TM\. Section 50.46 requires that the calculated cooling performance following postulated loss-of-coolant accidents at reactors fueled with zircaloy or ZIRLO[supreg] cladding conforms to the criteria set forth in paragraph (b) of that section. In addition, appendix K to 10 CFR part 50, in part, 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 zircaloy or ZIRLO[supreg], materials that have different chemical compositions from Optimized ZIRLO\TM\. As written, these regulations presume only the use of zircaloy or ZIRLO[supreg] fuel rod cladding and do not contain provisions for use of fuel rods with other cladding materials. Therefore, an exemption from the requirements of 10 CFR 50.46 and part 50, appendix K, is needed to support the use of a different fuel rod cladding material. Accordingly, the licensee requested an exemption that would allow the use of Optimized ZIRLO\TM\ fuel rod cladding at MNS and CNS. 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 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. However, Sec. 50.12(a)(2) states that the Commission will not consider granting an exemption unless special circumstances are present as set forth in Sec. 50.12(a)(2). Under 10 CFR 50.12(a)(2)(ii), special circumstances are present when application of the regulation in the particular circumstances would not serve, or is not necessary to achieve, the underlying purpose of the rule. 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 to provide reassurance of safety in the event of a loss-of-coolant (LOCA) accident. Although the wording of the regulations in 10 CFR 50.46 and appendix K is not expressly applicable to Optimized ZIRLOTM, the evaluations described in the following sections of this exemption show that the purpose of the regulations are met by this exemption in that, subject to certain conditions, the acceptance criteria are valid for Optimized ZIRLO\TM\ fuel cladding material, Optimized ZIRLO\TM\ would maintain better post-quench ductility, and the Baker-Just equation conservatively bounds LOCA scenario metal-water reaction rates and is applicable to Optimized ZIRLO\TM\. Because the underlying purposes of 10 CFR 50.46 and appendix K can be achieved through the application of these requirements to 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. The Exemption Is Authorized by Law This exemption would allow the use of fuel rods clad with Optimized ZIRLO\TM\ in future core reload applications for MNS and CNS. Section 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR part 50 provided that the exemptions are authorized by law. The NRC staff determined that special circumstances exist to grant the proposed exemption and that granting the exemption would not result in a violation of the Atomic Energy Act of 1954, as amended. Therefore, the exemption is authorized by law. No Undue Risk to Public Health and Safety The provisions of 10 CFR 50.46 establish acceptance criteria for ECCS performance. Westinghouse topical reports WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, ``Optimized ZIRLO\TM\,'' dated July 2006, contain the justification to use Optimized ZIRLOTM fuel rod cladding material in addition to Zircaloy-4 and ZIRLO[supreg]. The complete topical reports are not publicly available because they contain proprietary information, however, a redacted version and the NRC safety evaluation are available under ADAMS Accession No. ML062080569. The NRC staff found that the Westinghouse topical reports demonstrated the applicability of these ECCS acceptance criteria to Optimized ZIRLO\TM\, subject to the compliance with the specific conditions of approval established therein. The NRC staff reviewed the August 20, 2015, application against these specific conditions and found that the licensee was in compliance with all of the applicable conditions. The NRC staff's review of these specific conditions for MNS and CNS can be found under ADAMS Accession No. ML16105A326. Ring compression tests performed by Westinghouse on Optimized ZIRLOTM were reviewed and approved by the NRC staff in topical report WCAP-14342-A & CENPD-404-NP-A, Addendum 1-A, and demonstrate an acceptable retention of post-quench ductility up to the 10 CFR 50.46 limits of 2,200 degrees Fahrenheit and 17 percent equivalent clad reacted. Furthermore, the NRC staff has concluded that oxidation measurements provided by Westinghouse illustrate that oxide thickness (and associated hydrogen pickup) for Optimized ZIRLO\TM\ at any given burnup would be less than that for both zircaloy and ZIRLOTM (ADAMS Package Accession No. ML073130555). Hence, the NRC staff concludes that Optimized ZIRLOTM would be expected to maintain acceptable post-quench ductility. The provisions of 10 CFR part 50, appendix K, paragraph I.A.5, ``Metal-Water Reaction Rate,'' serve to ensure that cladding oxidation and hydrogen generation are limited appropriately during a loss-of- coolant accident (LOCA) and conservatively accounted for in the ECCS evaluation model. That regulation requires that the Baker-Just equation be used in the ECCS evaluation model to determine the rate of energy release, cladding oxidation, and hydrogen generation. Since the use of 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 cladding for determining acceptable fuel performance. As concluded in the NRC staff safety evaluation for the associated topical report, Westinghouse demonstrated that the Baker- Just model is conservative in all post-LOCA scenarios with respect to the use of the Optimized ZIRLOTM as a fuel cladding material. The NRC-approved topical reports have demonstrated that predicted chemical, thermal, and mechanical characteristics of the Optimized ZIRLOTM alloy cladding are bounded by those approved for ZIRLO[supreg] under anticipated operational occurrences and postulated accidents. Reload cores are required to be operated in accordance with the operating limits specified in the technical specifications and the core operating limits report. [[Page 42758]] Based on the above, no new accident precursors are created by using Optimized ZIRLOTM; thus, the probability of postulated accidents is not increased. Also, based on the above, the consequences of postulated accidents are not increased. Therefore, there is no undue risk to public health and safety due to using Optimized ZIRLO\TM\. Consistent With Common Defense and Security The proposed exemption would allow the use of Optimized ZIRLO\TM\ fuel rod cladding material at MNS and CNS. This change to the plant configuration is adequately controlled by TS requirements and is not related to security issues. Because the common defense and security is not impacted by this exemption, the exemption is consistent with the common defense and security. 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 staff 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 proposed TS changes add flexibility in the selection of fuel rod cladding materials for use at CNS and MNS. The proposed change of adding a cladding material does not result in an increase to the probability or consequences of an accident previously evaluated. TS 4.2.1 addresses the fuel assembly design, and currently specifies that, ``Each assembly shall consist of a matrix of either ZIRLO[supreg] or Zircaloy fuel rods . . .'' The proposed change will add Optimized ZIRLO\TM\ to the approved fuel rod cladding materials listed in this TS. In addition, a reference to the Westinghouse VANTAGE+ fuel assembly core reference report, WCAP-12610-P-A, and the topical report for Optimized ZIRLO\TM\, WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, will be included in the listing of approved methods used to determine the core operating limits for CNS and MNS given in TS 5.6.5.b. Westinghouse topical report WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, Optimized ZIRLO\TM\, provides the details and results of material testing of Optimized ZIRLO\TM\ compared to standard ZIRLO[supreg], as well as the material properties to be used in various models and methodologies when analyzing Optimized ZIRLO\TM\. As the nuclear industry pursues longer operating cycles with increased fuel discharge burnup and fuel duty, the corrosion performance requirements for the nuclear fuel cladding become more demanding. Optimized ZIRLO\TM\ was developed to meet these industry needs by providing a reduced corrosion rate while maintaining the composition and physical properties, such as mechanical strength, similar to standard ZIRLO[supreg]. Fuel rod internal pressure has also become more limiting due to changes such as increased fuel duty and use of integral fuel burnable absorbers. Reducing the associated corrosion buildup by using Optimized ZIRLO\TM\ in turn reduces temperature feedback effects, providing additional margin to the fuel rod internal pressure design criterion. Fuel with Optimized ZIRLO\TM\ cladding will continue to satisfy the pertinent design basis operating limits, so cladding integrity is maintained. There are no changes that will adversely affect the ability of existing components and systems to mitigate the consequences of any accident. Therefore, addition of Optimized ZIRLO\TM\ to the allowable cladding materials for CNS and MNS does not result in an increase in the probability or consequences of an accident previously evaluated. The NRC has previously approved use of Optimized ZIRLO\TM\ fuel cladding material in Westinghouse fueled reactors provided that licensees ensure compliance with the Conditions and Limitations set forth in the NRC Safety Evaluation for the topical report. Confirmation that these Conditions are satisfied is performed as part of the normal core reload process. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed exemption create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed TS changes add flexibility in the selection of fuel rod cladding materials for use at CNS and MNS. Optimized ZIRLO\TM\ was developed to provide a reduced cladding corrosion rate while maintaining the benefits of mechanical strength and resistance to accelerated corrosion from potential abnormal chemistry conditions. The fuel rod design bases are established to satisfy the general and specific safety criteria addressed in the CNS and MNS UFSAR [Updated Final Safety Analysis Report], Chapter 15 (Accident Analyses). The fuel rods are designed to prevent excessive fuel temperatures, excessive fuel rod internal gas pressures due to fission gas releases, and excessive cladding stresses and strains. Westinghouse topical report WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, Optimized ZIRLO\TM\, provides the details and results of material testing of Optimized ZIRLO\TM\ compared to standard ZIRLO[supreg], as well as the material properties to be used in various models and methodologies when analyzing Optimized ZIRLO\TM\. The original fuel design basis requirements have been maintained. No new single failure mechanisms will be created, and there are no alterations to plant equipment or procedures that would introduce any new or unique operational modes or accident precursors. Therefore, addition of another approved cladding material of similar composition and properties as the current approved cladding materials to the CNS and MNS TS does not create the possibility of a new or different kind of accident or malfunction from those previously evaluated within the UFSAR. 3. Does the proposed exemption involve a significant reduction in a margin of safety? Response: No. The proposed change will not involve a significant reduction in the 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[supreg]. Optimized ZIRLO\TM\ is expected to perform similarly to [[Page 42759]] standard ZIRLO[supreg] for all normal operating and accident scenarios, including both loss of coolant accident (LOCA) and non-LOCA scenarios. For LOCA scenarios, where the slight difference in Optimized ZIRLO\TM\ material properties relative to standard ZIRLO[supreg] could have some impact on the overall accident scenario, plant-specific LOCA analyses using Optimized ZIRLO\TM\ properties demonstrates that the acceptance criteria of 10 CFR 50.46 has been satisfied, therefore, the proposed change does not involve a significant reduction in a margin of safety. Based on the above, the NRC staff concludes that the proposed exemption 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) 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 material properties and performance characteristics as the currently licensed ZIRLO[supreg] cladding. Thus, the use of 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 requirements of 10 CFR 51.22(c)(9)(ii) are met. Requirements in 10 CFR 51.22(c)(9)(iii) 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 material properties and performance characteristics as the currently licensed ZIRLO[supreg] cladding. Thus, the use of Optimized ZIRLO\TM\ fuel rod cladding material will not significantly increase individual occupational radiation exposure, or significantly increase cumulative occupational radiation exposure. Therefore, the requirements of 10 CFR 51.22(c)(9)(iii) are met. 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, is consistent with the common defense and security, and that special circumstances are present to warrant issuance of the exemption. Therefore, the Commission hereby grants Duke Energy an exemption from the requirements of 10 CFR 50.46 and Appendix K, paragraph I.A.5 to 10 CFR part 50, to allow the application of these criteria to, and the use of, Optimized ZIRLO\TM\ fuel rod cladding material at MNS and CNS. This exemption is effective upon issuance. Dated at Rockville, Maryland, this 21st day of June 2016. For the Nuclear Regulatory Commission. Anne T. Boland, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2016-15548 Filed 6-29-16; 8:45 am] BILLING CODE 7590-01-P
![42756 Federal Register / Vol. 81, No. 126 / Thursday, June 30, 2016 / Notices
Limitations and Expiration or consequences from radiological request dated August 20, 2015, from
The facility licensee requested the accidents. Finally, the requirements to Duke Energy Carolinas, LLC (Duke
exemption from the regulation that which the exemption applies involve Energy or the licensee) from portions of
requires the operating test to be qualification requirements. Accordingly, the regulations to support the use of fuel
administered in a plant walk-through the exemption meets the eligibility that is clad in Optimized ZIRLOTM.
because of the incomplete construction criteria for categorical exclusion set ADDRESSES: Please refer to Docket ID
of the plant. As construction of different forth in 10 CFR 51.22(c)(25). Pursuant to NRC–2016–0128 when contacting the
sections of the facility becomes 10 CFR 51.22(b), no environmental NRC about the availability of
substantially complete and in-plant impact statement or environmental information regarding this document.
assessment need be prepared in You may obtain publicly-available
systems, components, and structures
connection with the issuance of the information related to this document
(SSCs) near completion, usage of this
exemption. using any of the following methods:
exemption will become unnecessary for
those areas and SSCs. Accordingly, on IV. Conclusion • Federal Rulemaking Web site: Go to
a case-by-case basis, for those tasks that http://www.regulations.gov and search
Accordingly, the Commission has for Docket ID NRC–2016–0128. Address
are selected to be part of an operating determined that, pursuant to 10 CFR
task in accordance with NUREG–1021, questions about NRC dockets to Carol
55.11, issuing this exemption from the Gallagher; telephone: 301–415–3463;
ES–301, Section D.4.a and Section requirement in 55.45(b) to administer a email: Carol.Gallagher@nrc.gov.
D.4.b, where it is possible to both portion of the operating test in a plant • NRC’s Agencywide Documents
perform on-the-job training in the plant walk-through is authorized by law and Access and Management System
and administer part of an operating test will not endanger life or property and is (ADAMS): You may obtain publicly-
in a plant walk-through, as determined otherwise in the public interest. The available documents online in the
by the NRC examiners, this exemption Commission also has approved the ADAMS Public Documents collection at
may not be used. Furthermore, this facility licensee’s proposed alternative http://www.nrc.gov/reading-rm/
exemption will finally expire and may to the examination criteria in NUREG– adams.html. To begin the search, select
no longer be used upon the 1021, ES–301, Section D.4.a and Section ‘‘ADAMS Public Documents’’ and then
Commission’s finding for VEGP Unit 3 D.4.b and therefore will allow one, two, select ‘‘Begin Web-based ADAMS
in accordance with 10 CFR 52.103(g) or three of the required in-plant system Search.’’ For problems with ADAMS,
(‘‘The licensee shall not operate the JPMs to be performed using discussion please contact the NRC’s Public
facility until the Commission makes a and performance methods in Document Room (PDR) reference staff at
finding that the acceptance criteria in combination with plant layout 1–800–397–4209, 301–415–4737, or by
the combined license are met, except for diagrams, maps, equipment diagrams, email to pdr.resource@nrc.gov. The
those acceptance criteria that the pictures, and mock-ups in lieu of plant ADAMS accession number for each
Commission found were met under equipment until the Commission makes document referenced (if it is available in
§ 52.97(a)(2).’’). a finding for VEGP Unit 3 that ADAMS) is provided the first time that
Environmental Consideration acceptance criteria in the combined it is mentioned in this document.
license are met in accordance with 10 • NRC’s PDR: You may examine and
This exemption allows one, two, or CFR 52.103(g). purchase copies of public documents at
three of the required in-plant system the NRC’s PDR, Room O1–F21, One
Dated at Rockville, Maryland, this 24th day
JPMs to be performed using discussion White Flint North, 11555 Rockville
of June, 2016.
and performance methods in Pike, Rockville, Maryland 20852.
For the Nuclear Regulatory Commission.
combination with plant layout FOR FURTHER INFORMATION CONTACT: G.
diagrams, maps, equipment diagrams, Samuel S. Lee,
Acting Deputy Director, Division of New Edward Miller, Office of Nuclear
pictures, and mock-ups in lieu of plant Reactor Regulation, U.S. Nuclear
equipment. The NRC staff evaluated Reactor Licensing, Office of New Reactors.
[FR Doc. 2016–15547 Filed 6–29–16; 8:45 am] Regulatory Commission, Washington DC
whether there would be significant 20555–0001; telephone: 301–415–2481,
environmental impacts associated with BILLING CODE 7590–01–P
email Ed.Miller@nrc.gov.
the issuance of the requested
SUPPLEMENTARY INFORMATION:
exemptions. The NRC staff determined
the proposed action fits a category of NUCLEAR REGULATORY I. Background
actions that do not require an COMMISSION
Duke Energy is the holder of Facility
environmental assessment or [Docket Nos. 50–369 and 50–370; NRC– Operating License Nos. NPF–9, NPF–17,
environmental impact statement. 2016–0128] NPF–35, and NPF–52, which authorize
For the following reasons, this operation of the McGuire Nuclear
exemption meets the eligibility criteria Duke Energy Carolinas, LLC and North
Station (MNS), Units 1 and 2, and
of 10 CFR 51.22(c)(25) for a categorical Carolina Electric Membership
Catawba Nuclear Station (CNS), Units 1
exclusion. There is no significant Corporation; Acceptance Criteria for
and 2. The licenses provide, among
hazards consideration related to this Emergency Core Cooling Systems,
other things, that each facility is subject
exemption. The NRC staff has also McGuire Nuclear Station, Units 1 and 2,
to all rules, regulations, and orders of
determined that the exemption involves Catawba Nuclear Station, Units 1 and
the NRC now or hereafter in effect.
no significant increase in the amounts, 2
The MNS and CNS units are
and no significant change in the types,
mstockstill on DSK3G9T082PROD with NOTICES
AGENCY: Nuclear Regulatory pressurized-water reactor located in
of any effluents that may be released Commission. Mecklenburg County, North Carolina,
offsite; that there is no significant ACTION: Exemption; issuance. and York County, South Carolina,
increase in individual or cumulative respectively.
public or occupational radiation SUMMARY: The U.S. Nuclear Regulatory
exposure; that there is no significant Commission (NRC) is issuing an II. Request/Action
construction impact; and that there is no exemption in response to a license Pursuant to section 50.12 of title 10 of
significant increase in the potential for amendment request and exemption the Code of Federal Regulations (10
VerDate Sep<11>2014 20:01 Jun 29, 2016 Jkt 238001 PO 00000 Frm 00128 Fmt 4703 Sfmt 4703 E:\FR\FM\30JNN1.SGM 30JNN1](https://thefederalregister.org/doc/81_FR_42882/page/1.svg)
![Federal Register / Vol. 81, No. 126 / Thursday, June 30, 2016 / Notices 42757
CFR), ‘‘Specific Exemptions,’’ the purpose of 10 CFR 50.46 and appendix established therein. The NRC staff
licensee has, by letter dated August 20, K to 10 CFR part 50 is to establish reviewed the August 20, 2015,
2015 (ADAMS Accession No. acceptance criteria for ECCS application against these specific
ML15295A016), requested an exemption performance to provide reassurance of conditions and found that the licensee
from 10 CFR 50.46, ‘‘Acceptance criteria safety in the event of a loss-of-coolant was in compliance with all of the
for emergency core cooling systems (LOCA) accident. Although the wording applicable conditions. The NRC staff’s
[ECCS] for light-water nuclear power of the regulations in 10 CFR 50.46 and review of these specific conditions for
reactors,’’ and appendix K to 10 CFR appendix K is not expressly applicable MNS and CNS can be found under
part 50, ‘‘ECCS Evaluation Models’’ to to Optimized ZIRLOTM, the evaluations ADAMS Accession No. ML16105A326.
allow the use of fuel rods clad with described in the following sections of Ring compression tests performed by
Optimized ZIRLOTM. Section 50.46 this exemption show that the purpose of Westinghouse on Optimized ZIRLOTM
requires that the calculated cooling the regulations are met by this were reviewed and approved by the
performance following postulated loss- exemption in that, subject to certain NRC staff in topical report WCAP–
of-coolant accidents at reactors fueled conditions, the acceptance criteria are 14342–A & CENPD–404–NP–A,
with zircaloy or ZIRLO® cladding valid for Optimized ZIRLOTM fuel Addendum 1–A, and demonstrate an
conforms to the criteria set forth in cladding material, Optimized ZIRLOTM acceptable retention of post-quench
paragraph (b) of that section. In would maintain better post-quench ductility up to the 10 CFR 50.46 limits
addition, appendix K to 10 CFR part 50, ductility, and the Baker-Just equation of 2,200 degrees Fahrenheit and 17
in part, requires that the Baker-Just conservatively bounds LOCA scenario percent equivalent clad reacted.
equation be used to predict the rates of metal-water reaction rates and is Furthermore, the NRC staff has
energy release, hydrogen concentration, applicable to Optimized ZIRLOTM. concluded that oxidation measurements
and cladding oxidation from the metal/ Because the underlying purposes of 10 provided by Westinghouse illustrate
water reaction. The Baker-Just equation CFR 50.46 and appendix K can be that oxide thickness (and associated
assumes the use of zircaloy or ZIRLO®, achieved through the application of hydrogen pickup) for Optimized
materials that have different chemical these requirements to the use of ZIRLOTM at any given burnup would be
compositions from Optimized ZIRLOTM. Optimized ZIRLOTM fuel rod cladding less than that for both zircaloy and
As written, these regulations presume material, the special circumstances ZIRLOTM (ADAMS Package Accession
only the use of zircaloy or ZIRLO® fuel required by 10 CFR 50.12(a)(2)(ii) for the No. ML073130555). Hence, the NRC
rod cladding and do not contain granting of an exemption exist. staff concludes that Optimized ZIRLOTM
provisions for use of fuel rods with would be expected to maintain
The Exemption Is Authorized by Law acceptable post-quench ductility.
other cladding materials. Therefore, an
exemption from the requirements of 10 This exemption would allow the use The provisions of 10 CFR part 50,
CFR 50.46 and part 50, appendix K, is of fuel rods clad with Optimized appendix K, paragraph I.A.5, ‘‘Metal-
needed to support the use of a different ZIRLOTM in future core reload Water Reaction Rate,’’ serve to ensure
fuel rod cladding material. Accordingly, applications for MNS and CNS. Section that cladding oxidation and hydrogen
the licensee requested an exemption 50.12 allows the NRC to grant generation are limited appropriately
that would allow the use of Optimized exemptions from the requirements of 10 during a loss-of-coolant accident
ZIRLOTM fuel rod cladding at MNS and CFR part 50 provided that the (LOCA) and conservatively accounted
CNS. exemptions are authorized by law. The for in the ECCS evaluation model. That
NRC staff determined that special regulation requires that the Baker-Just
III. Discussion circumstances exist to grant the equation be used in the ECCS evaluation
Pursuant to 10 CFR 50.12, the proposed exemption and that granting model to determine the rate of energy
Commission may, upon application by the exemption would not result in a release, cladding oxidation, and
any interested person or upon its own violation of the Atomic Energy Act of hydrogen generation. Since the use of
initiative, grant exemptions from the 1954, as amended. Therefore, the the Baker-Just equation presumes the
requirements of 10 CFR part 50, when exemption is authorized by law. use of zircaloy-clad fuel, strict
the exemptions are authorized by law, application of the rule would not permit
No Undue Risk to Public Health and
will not present an undue risk to public use of the equation for Optimized
Safety
health or safety, and are consistent with ZIRLOTM cladding for determining
the common defense and security. The provisions of 10 CFR 50.46 acceptable fuel performance. As
However, § 50.12(a)(2) states that the establish acceptance criteria for ECCS concluded in the NRC staff safety
Commission will not consider granting performance. Westinghouse topical evaluation for the associated topical
an exemption unless special reports WCAP–12610–P–A and CENPD– report, Westinghouse demonstrated that
circumstances are present as set forth in 404–P–A, Addendum 1–A, ‘‘Optimized the Baker-Just model is conservative in
§ 50.12(a)(2). Under 10 CFR ZIRLOTM,’’ dated July 2006, contain the all post-LOCA scenarios with respect to
50.12(a)(2)(ii), special circumstances are justification to use Optimized ZIRLOTM the use of the Optimized ZIRLOTM as a
present when application of the fuel rod cladding material in addition to fuel cladding material.
regulation in the particular Zircaloy-4 and ZIRLO®. The complete The NRC-approved topical reports
circumstances would not serve, or is not topical reports are not publicly available have demonstrated that predicted
necessary to achieve, the underlying because they contain proprietary chemical, thermal, and mechanical
purpose of the rule. information, however, a redacted characteristics of the Optimized
version and the NRC safety evaluation ZIRLOTM alloy cladding are bounded by
mstockstill on DSK3G9T082PROD with NOTICES
Special Circumstances are available under ADAMS Accession those approved for ZIRLO® under
Special circumstances, in accordance No. ML062080569. The NRC staff found anticipated operational occurrences and
with 10 CFR 50.12(a)(2)(ii), are present that the Westinghouse topical reports postulated accidents. Reload cores are
whenever application of the regulation demonstrated the applicability of these required to be operated in accordance
in the particular circumstances is not ECCS acceptance criteria to Optimized with the operating limits specified in
necessary to achieve the underlying ZIRLOTM, subject to the compliance the technical specifications and the core
purpose of the rule. The underlying with the specific conditions of approval operating limits report.
VerDate Sep<11>2014 20:01 Jun 29, 2016 Jkt 238001 PO 00000 Frm 00129 Fmt 4703 Sfmt 4703 E:\FR\FM\30JNN1.SGM 30JNN1](https://thefederalregister.org/doc/81_FR_42882/page/2.svg)
![42758 Federal Register / Vol. 81, No. 126 / Thursday, June 30, 2016 / Notices
Based on the above, no new accident increase to the probability or Evaluation for the topical report.
precursors are created by using consequences of an accident previously Confirmation that these Conditions are
Optimized ZIRLOTM; thus, the evaluated. TS 4.2.1 addresses the fuel satisfied is performed as part of the
probability of postulated accidents is assembly design, and currently specifies normal core reload process.
not increased. Also, based on the above, that, ‘‘Each assembly shall consist of a Therefore, the proposed change does
the consequences of postulated matrix of either ZIRLO® or Zircaloy fuel not involve a significant increase in the
accidents are not increased. Therefore, rods . . .’’ The proposed change will probability or consequences of an
there is no undue risk to public health add Optimized ZIRLOTM to the accident previously evaluated.
and safety due to using Optimized approved fuel rod cladding materials 2. Does the proposed exemption
ZIRLOTM. listed in this TS. In addition, a reference create the possibility of a new or
to the Westinghouse VANTAGE+ fuel different kind of accident from any
Consistent With Common Defense and accident previously evaluated?
assembly core reference report, WCAP–
Security Response: No.
12610–P–A, and the topical report for
The proposed exemption would allow Optimized ZIRLOTM, WCAP–12610–P– The proposed TS changes add
the use of Optimized ZIRLOTM fuel rod A and CENPD–404–P–A, Addendum 1– flexibility in the selection of fuel rod
cladding material at MNS and CNS. A, will be included in the listing of cladding materials for use at CNS and
This change to the plant configuration is approved methods used to determine MNS. Optimized ZIRLOTM was
adequately controlled by TS the core operating limits for CNS and developed to provide a reduced
requirements and is not related to cladding corrosion rate while
MNS given in TS 5.6.5.b. Westinghouse
security issues. Because the common maintaining the benefits of mechanical
topical report WCAP–12610–P–A and
defense and security is not impacted by strength and resistance to accelerated
CENPD–404–P–A, Addendum 1–A,
this exemption, the exemption is corrosion from potential abnormal
Optimized ZIRLOTM, provides the
consistent with the common defense chemistry conditions. The fuel rod
details and results of material testing of
and security. design bases are established to satisfy
Optimized ZIRLOTM compared to
the general and specific safety criteria
Environmental Considerations standard ZIRLO®, as well as the
addressed in the CNS and MNS UFSAR
material properties to be used in various
The NRC staff determined that the [Updated Final Safety Analysis Report],
models and methodologies when
exemption discussed herein meets the Chapter 15 (Accident Analyses). The
analyzing Optimized ZIRLOTM. As the fuel rods are designed to prevent
eligibility criteria for the categorical nuclear industry pursues longer
exclusion set forth in 10 CFR 51.22(c)(9) excessive fuel temperatures, excessive
operating cycles with increased fuel fuel rod internal gas pressures due to
because it is related to a requirement discharge burnup and fuel duty, the
concerning the installation or use of a fission gas releases, and excessive
corrosion performance requirements for cladding stresses and strains.
facility component located within the the nuclear fuel cladding become more
restricted area, as defined in 10 CFR Westinghouse topical report WCAP–
demanding. Optimized ZIRLOTM was 12610–P–A and CENPD–404–P–A,
part 20, and issuance of this exemption developed to meet these industry needs
involves: (i) No significant hazards Addendum 1–A, Optimized ZIRLOTM,
by providing a reduced corrosion rate provides the details and results of
consideration, (ii) no significant change while maintaining the composition and
in the types or a significant increase in material testing of Optimized ZIRLOTM
physical properties, such as mechanical compared to standard ZIRLO®, as well
the amounts of any effluents that may be strength, similar to standard ZIRLO®.
released offsite, and (iii) no significant as the material properties to be used in
Fuel rod internal pressure has also various models and methodologies
increase in individual or cumulative become more limiting due to changes
occupational radiation exposure. when analyzing Optimized ZIRLOTM.
such as increased fuel duty and use of The original fuel design basis
Therefore, in accordance with 10 CFR integral fuel burnable absorbers.
51.22(b), no environmental impact requirements have been maintained. No
Reducing the associated corrosion new single failure mechanisms will be
statement or environmental assessment buildup by using Optimized ZIRLOTM
need be prepared in connection with the created, and there are no alterations to
in turn reduces temperature feedback plant equipment or procedures that
NRC’s consideration of this exemption effects, providing additional margin to
request. The basis for the NRC staff’s would introduce any new or unique
the fuel rod internal pressure design operational modes or accident
determination is discussed as follows criterion. Fuel with Optimized
with an evaluation against each of the precursors. Therefore, addition of
ZIRLOTM cladding will continue to another approved cladding material of
requirements in 10 CFR 51.22(c)(9)(i)– satisfy the pertinent design basis
(iii). similar composition and properties as
operating limits, so cladding integrity is the current approved cladding materials
Requirements in 10 CFR 51.22(c)(9)(i) maintained. There are no changes that to the CNS and MNS TS does not create
The NRC staff evaluated whether the will adversely affect the ability of the possibility of a new or different kind
exemption involves no significant existing components and systems to of accident or malfunction from those
hazards consideration using the mitigate the consequences of any previously evaluated within the UFSAR.
standards described in 10 CFR 50.92(c), accident. Therefore, addition of 3. Does the proposed exemption
as presented below: Optimized ZIRLOTM to the allowable involve a significant reduction in a
1. Does the proposed exemption cladding materials for CNS and MNS margin of safety?
involve a significant increase in the does not result in an increase in the Response: No.
probability or consequences of an The proposed change will not involve
mstockstill on DSK3G9T082PROD with NOTICES
probability or consequences of an
accident previously evaluated? accident previously evaluated. a significant reduction in the margin of
Response: No. The NRC has previously approved use safety because it has been demonstrated
The proposed TS changes add of Optimized ZIRLOTM fuel cladding that the material properties of the
flexibility in the selection of fuel rod material in Westinghouse fueled Optimized ZIRLOTM are not
cladding materials for use at CNS and reactors provided that licensees ensure significantly different from those of
MNS. The proposed change of adding a compliance with the Conditions and standard ZIRLO®. Optimized ZIRLOTM
cladding material does not result in an Limitations set forth in the NRC Safety is expected to perform similarly to
VerDate Sep<11>2014 20:01 Jun 29, 2016 Jkt 238001 PO 00000 Frm 00130 Fmt 4703 Sfmt 4703 E:\FR\FM\30JNN1.SGM 30JNN1](https://thefederalregister.org/doc/81_FR_42882/page/3.svg)
![Federal Register / Vol. 81, No. 126 / Thursday, June 30, 2016 / Notices 42759
standard ZIRLO® for all normal requirements of 10 CFR 50.46 and participate in these public meetings, or
operating and accident scenarios, Appendix K, paragraph I.A.5 to 10 CFR need this meeting notice or the
including both loss of coolant accident part 50, to allow the application of these transcript or other information from the
(LOCA) and non-LOCA scenarios. For criteria to, and the use of, Optimized public meetings in another format (e.g.
LOCA scenarios, where the slight ZIRLOTM fuel rod cladding material at braille, large print), please notify
difference in Optimized ZIRLOTM MNS and CNS. Kimberly Meyer, NRC Disability
material properties relative to standard This exemption is effective upon Program Manager, at 301–287–0739, by
ZIRLO® could have some impact on the issuance. videophone at 240–428–3217, or by
overall accident scenario, plant-specific Dated at Rockville, Maryland, this 21st day email at Kimberly.Meyer-Chambers@
LOCA analyses using Optimized of June 2016. nrc.gov. Determinations on requests for
ZIRLOTM properties demonstrates that For the Nuclear Regulatory Commission. reasonable accommodation will be
the acceptance criteria of 10 CFR 50.46 made on a case-by-case basis.
Anne T. Boland,
has been satisfied, therefore, the * * * * *
proposed change does not involve a Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor Members of the public may request to
significant reduction in a margin of Regulation. receive this information electronically.
safety. If you would like to be added to the
[FR Doc. 2016–15548 Filed 6–29–16; 8:45 am]
Based on the above, the NRC staff distribution, please contact the Nuclear
concludes that the proposed exemption BILLING CODE 7590–01–P
Regulatory Commission, Office of the
involves no significant hazards Secretary, Washington, DC 20555 (301–
consideration. Accordingly, the 415–1969), or email
NUCLEAR REGULATORY
requirements of 10 CFR 51.22(c)(9)(i) are Brenda.Akstulewicz@nrc.gov or
COMMISSION
met. Patricia.Jimenez@nrc.gov.
[NRC–2016–0001]
Requirements in 10 CFR 51.22(c)(9)(ii) Dated: June 28, 2016.
The proposed exemption would allow Sunshine Act Meeting Glenn Ellmers,
the use of Optimized ZIRLOTM fuel rod Policy Coordinator, Office of the Secretary.
cladding material in the reactors. DATE:June 28, 2016. [FR Doc. 2016–15650 Filed 6–28–16; 11:15 am]
Optimized ZIRLOTM has essentially the PLACE:Commissioners’ Conference BILLING CODE 7590–01–P
same material properties and Room, 11555 Rockville Pike, Rockville,
performance characteristics as the Maryland.
currently licensed ZIRLO® cladding. STATUS: Public. OFFICE OF PERSONNEL
Thus, the use of Optimized ZIRLOTM MANAGEMENT
fuel rod cladding material will not Week of June 27, 2016
significantly change the types of Wednesday, June 29, 2016 Submission for Review:
effluents that may be released offsite, or Reemployment of Annuitants
significantly increase the amount of 9:55 a.m. Affirmation Session (Public
effluents that may be released offsite. Meeting) (Tentative) AGENCY: U.S. Office of Personnel
Therefore, the requirements of 10 CFR Strata Energy Inc. (Ross in Situ Management.
51.22(c)(9)(ii) are met. Uranium Recovery Project)—Joint ACTION: 30-Day Notice and request for
Intervenors’ Petition for Review of comments.
Requirements in 10 CFR 51.22(c)(9)(iii) Initial Decision, LBP–15–3, and Related
The proposed exemption would allow Interlocutory Decisions. (Tentative) SUMMARY: As required by the Paperwork
the use of Optimized ZIRLOTM fuel rod * * * * * Reduction Act of 1995 (Pub. L. 104–13,
cladding material in the reactors. 44 U.S.C. chapter 35) as amended by the
ADDITIONAL INFORMATION: By a vote of 4– Clinger-Cohen Act (Pub. L. 104–106),
Optimized ZIRLOTM has essentially the 0 on June 27, 2016, the Commission
same material properties and the Retirement Services, Office of
determined pursuant to U.S.C. 552b(e) Personnel Management (OPM) offers the
performance characteristics as the and 9.107(a) of the Commission’s rules
currently licensed ZIRLO® cladding. general public and other federal
that the item in the above referenced agencies the opportunity to comment on
Thus, the use of Optimized ZIRLOTM Affirmation Session be held with less
fuel rod cladding material will not an existing information collection
than one week notice to the public. The request (ICR) 3206–0211,
significantly increase individual meeting is scheduled on June 29, 2016.
occupational radiation exposure, or Reemployment of Annuitants. Notice of
* * * * * the information collection was
significantly increase cumulative The schedule for Commission
occupational radiation exposure. previously published in the Federal
meetings is subject to change on short Register [Vol. 81, No. 56, Page 15580]
Therefore, the requirements of 10 CFR notice. For more information or to verify
51.22(c)(9)(iii) are met. on March 23, 2016, allowing for a 60-
the status of meetings, contact Denise day public comment period. No
IV. Conclusions McGovern at 301–415–0681 or via email comments were received for this
Accordingly, the Commission has at Denise.McGovern@nrc.gov. information collection.
determined that pursuant to 10 CFR * * * * * DATES: Comments are encouraged and
50.12(a), the exemption is authorized by The NRC Commission Meeting will be accepted until August 1, 2016.
law, will not present an undue risk to Schedule can be found on the Internet This process is conducted in accordance
mstockstill on DSK3G9T082PROD with NOTICES
the public health and safety, is at: http://www.nrc.gov/public-involve/ with 5 CFR 1320.1.
consistent with the common defense public-meetings/schedule.html. ADDRESSES: Interested persons are
and security, and that special * * * * * invited to submit written comments on
circumstances are present to warrant The NRC provides reasonable the proposed information collection to
issuance of the exemption. Therefore, accommodation to individuals with the Office of Information and Regulatory
the Commission hereby grants Duke disabilities where appropriate. If you Affairs, Office of Management and
Energy an exemption from the need a reasonable accommodation to Budget, 725 17th Street NW.,
VerDate Sep<11>2014 20:01 Jun 29, 2016 Jkt 238001 PO 00000 Frm 00131 Fmt 4703 Sfmt 4703 E:\FR\FM\30JNN1.SGM 30JNN1](https://thefederalregister.org/doc/81_FR_42882/page/4.svg)
Document Created: 2018-02-08 07:45:08
Document Modified: 2018-02-08 07:45:08
| 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. | |
| Contact | G. Edward Miller, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-2481, email [email protected] | |
| FR Citation | 81 FR 42756 |
2025 Federal Register | Disclaimer | Privacy Policy
USC | CFR | eCFR