81 FR 52910 - Wolf Creek Generating Station; Use of Optimized ZIRLOTM
NUCLEAR REGULATORY COMMISSION Federal Register Volume 81, Issue 154 (August 10, 2016)
Federal Register Volume 81, Issue 154 (August 10, 2016)
| Page Range | 52910-52912 | |
| FR Document | 2016-18979 |
[Federal Register Volume 81, Number 154 (Wednesday, August 10, 2016)] [Notices] [Pages 52910-52912] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2016-18979] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-482; NRC-2016-0162] Wolf Creek Generating Station; Use of Optimized ZIRLOTM Fuel Rod Cladding Material AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a January 27, 2016, request, as supplemented on May 19, 2016, from Wolf Creek Nuclear Operating Corporation (WCNOC or the licensee) in order to use Optimized ZIRLOTM fuel rod cladding material at Wolf Creek Generating Station (WCGS). DATES: The exemption was issued on August 2, 2016. ADDRESSES: Please refer to Docket ID NRC-2016-0162 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-2016-0162. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to [email protected]. The ADAMS accession number for each document referenced 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: Carl F. Lyon, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-2296, email: [email protected]. SUPPLEMENTARY INFORMATION: I. Background The licensee is the holder of Renewed Facility Operating License No. NPF-42, which authorizes operation of WCGS. The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the NRC now or hereafter in effect. The facility consists of a pressurized-water reactor located in Coffey County, Kansas. II. Request/Action Pursuant to Sec. 50.12 of title 10 of the Code of Federal Regulations (10 CFR), ``Specific exemptions,'' the licensee requested by letter dated January 27, 2016, as supplemented by letter dated May 19, 2016 (ADAMS Accession Nos. ML16033A470 and ML16161A509, respectively), an exemption from specific 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 rod cladding 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 ZIRLOTM fuel rod cladding material. In addition, 10 CFR part 50, appendix K, requires that the Baker-Just equation be used to predict the rates of energy release, hydrogen concentration, and cladding oxidation from the metal/ water reaction. The Baker-Just equation assumes the use of a zirconium alloy, which is a material different from Optimized ZIRLOTM. The licensee requested the exemption because these regulations do not have provisions for the use of fuel rod cladding material other than zircaloy or ZIRLOTM. Because the material specifications of Optimized ZIRLOTM differ from the specifications for zircaloy or ZIRLOTM, a plant-specific exemption is required to support the reload applications for WCGS. 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 10 CFR part 50, appendix K, to fuel assembly designs using Optimized ZIRLOTM fuel rod cladding material. In its letter dated January 27, 2016, as supplemented by letter dated May 19, 2016, the licensee indicated 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 the criteria set forth in these regulations for application of the Optimized ZIRLOTM fuel rod cladding material. III. Discussion Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR part 50 when: (1) The exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. Under 10 CFR 50.12(a)(2), special circumstances include, among other things, when application of the specific regulation in the particular circumstance would not serve, or is not necessary to achieve, the underlying purpose of the rule. A. 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 10 CFR part 50, appendix K, is to establish acceptance criteria for ECCS performance. The regulations in 10 CFR 50.46 and 10 CFR part 50, 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, since the underlying purposes of 10 CFR 50.46 and 10 CFR part 50, appendix K, [[Page 52911]] 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 WCGS. As stated above, 10 CFR 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR part 50. The NRC staff has determined that 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 50.46 requires that each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical zircaloy or ZIRLOTM cladding must be provided with an ECCS that must be designed so that its calculated cooling performance following postulated loss-of-coolant accidents (LOCAs) conforms to the criteria set forth in 10 CFR 50.46(b). 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 Package Accession No. ML051670395), of topical reports submitted by Westinghouse Electric Company (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. The NRC staff found that the Westinghouse topical report demonstrates 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 licensee's January 27, 2016, application, as supplemented by letter dated May 9, 2016, 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 WCGS can be found in ADAMS under Accession No. ML16179A293. Ring compression tests performed by Westinghouse on Optimized ZIRLOTM (see WCAP-14342-A & CENPD-404-NP-A, dated July 2006 (ADAMS Accession No. ML062080569), demonstrate an acceptable retention of post-quench 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 in ADAMS under 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 post- quench 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 post-quench ductility. In addition, the provisions of 10 CFR 50.46 require the licensee to periodically evaluate the performance of the ECCS, using currently approved LOCA models and methods, to ensure that the fuel rods will continue to satisfy the 10 CFR 50.46 acceptance criteria. In its letter dated January 27, 2016, the licensee stated that 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. Granting the exemption to allow the licensee to use Optimized ZIRLOTM fuel rod cladding material in addition to the current mix of fuel rods does not diminish this requirement of periodic evaluation of ECCS performance. Therefore, the underlying purpose of the rule will continue to be achieved for WCGS. Paragraph I.A.5 of 10 CFR part 50, appendix K, states that the rates of energy release, hydrogen concentration, and cladding oxidation from the metal-water reaction shall be calculated using the Baker-Just equation. Since the Baker-Just equation presumes the use of zircaloy clad fuel, strict application of this provision of the rule would not permit use of the equation for the Optimized ZIRLOTM fuel rod cladding material for determining acceptable fuel performance. However, 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. Therefore, the NRC staff determined that the application of Paragraph I.A.5 of 10 CFR part 50, appendix K, is not necessary to achieve the underlying purpose of the rule in these circumstances. Since these evaluations demonstrate that the underlying purpose of the rule will be met, there will be no undue risk to the public health and safety. 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 January 27, 2016, as supplemented by letter dated May 19, 2016, the licensee stated that all the requirements and acceptance criteria will be maintained. The licensee is required to handle and control special nuclear material in these assemblies in accordance with its approved procedures. 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, [[Page 52912]] 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 change 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, ``Optimized ZIRLOTM,'' prepared by Westinghouse, addresses Optimized ZIRLOTM and demonstrates that Optimized ZIRLOTM has essentially the same properties as the currently licensed ZIRLOTM. 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 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 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, the Optimized ZIRLOTM fuel rod cladding material will perform similarly to those fabricated from standard ZIRLOTM, therefore precluding the possibility of the fuel cladding becoming an accident initiator and causing a new or different type of accident. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed exemption involve a significant reduction in a margin of safety? Response: No. The proposed change will not involve a significant reduction in the 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 the Optimized ZIRLOTM material properties, relative to standard ZIRLOTM could have some impact on the overall accident scenario, plant-specific LOCA analyses using the Optimized ZIRLOTM properties demonstrate that the acceptance criteria of 10 CFR 50.46 have 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 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 (i.e., satisfies the provision of 10 CFR 51.22(c)(9)(i)). 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 ZIRLOTM. 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 ZIRLOTM. 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. Conclusion Based on the above, the NRC staff concludes that the proposed exemption meets the eligibility criteria for the categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the NRC's proposed issuance of this exemption. 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 WCNOC an exemption from the requirements of 10 CFR 50.46 and 10 CFR part 50, appendix K, to allow the use of Optimized ZIRLOTM fuel rod cladding material at WCGS. As stated above, this exemption relates solely to the cladding material specified in these regulations. Dated at Rockville, Maryland, this 2nd day of August 2016. For the Nuclear Regulatory Commission. Anne T. Boland, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2016-18979 Filed 8-9-16; 8:45 am] BILLING CODE 7590-01-P
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During the public comment period, ADAMS Public Documents collection at Optimized ZIRLOTM. The licensee
the Consent Decree may be examined http://www.nrc.gov/reading-rm/ requested the exemption because these
and downloaded at this Justice adams.html. To begin the search, select regulations do not have provisions for
Department Web site: https:// ‘‘ADAMS Public Documents’’ and then the use of fuel rod cladding material
www.justice.gov/enrd/consent-decrees. select ‘‘Begin Web-based ADAMS other than zircaloy or ZIRLOTM. Because
We will provide a paper copy of the Search.’’ For problems with ADAMS, the material specifications of Optimized
Consent Decree upon written request please contact the NRC’s Public ZIRLOTM differ from the specifications
and payment of reproduction costs. Document Room (PDR) reference staff at for zircaloy or ZIRLOTM, a plant-specific
Please mail your request and payment 1–800–397–4209, 301–415–4737, or by exemption is required to support the
to: Consent Decree Library, U.S. DOJ— email to pdr.resource@nrc.gov. The reload applications for WCGS.
ENRD, P.O. Box 7611, Washington, DC ADAMS accession number for each The exemption request relates solely
20044–7611. document referenced in this document to the cladding material specified in
Please enclose a check or money order (if that document is available in these regulations (i.e., fuel rods with
for $15.25 (25 cents per page ADAMS) is provided the first time that Zircaloy or ZIRLOTM cladding material).
reproduction cost) payable to the United a document is referenced. This exemption would provide for the
States Treasury. • NRC’s PDR: You may examine and application of the acceptance criteria of
purchase copies of public documents at 10 CFR 50.46 and 10 CFR part 50,
Jeffrey Sands, appendix K, to fuel assembly designs
the NRC’s PDR, Room O1–F21, One
Assistant Section Chief, Environmental using Optimized ZIRLOTM fuel rod
Enforcement Section, Environment and
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852. cladding material. In its letter dated
Natural Resources Division.
January 27, 2016, as supplemented by
[FR Doc. 2016–18931 Filed 8–9–16; 8:45 am] FOR FURTHER INFORMATION CONTACT: Carl
letter dated May 19, 2016, the licensee
F. Lyon, Office of Nuclear Reactor
BILLING CODE 4410–15–P indicated that it was not seeking an
Regulation, U.S. Nuclear Regulatory
exemption from the acceptance and
Commission, Washington, DC 20555–
analytical criteria of these regulations.
NUCLEAR REGULATORY 0001; telephone: 301–415–2296, email:
The intent of the request is to allow the
COMMISSION Fred.Lyon@nrc.gov.
use of the criteria set forth in these
SUPPLEMENTARY INFORMATION: regulations for application of the
[Docket Nos. 50–482; NRC–2016–0162]
I. Background Optimized ZIRLOTM fuel rod cladding
Wolf Creek Generating Station; Use of material.
The licensee is the holder of Renewed
Optimized ZIRLOTM Fuel Rod Cladding III. Discussion
Facility Operating License No. NPF–42,
Material
which authorizes operation of WCGS. Pursuant to 10 CFR 50.12, the
AGENCY: Nuclear Regulatory The license provides, among other Commission may, upon application by
Commission. things, that the facility is subject to all any interested person or upon its own
ACTION: Exemption; issuance. rules, regulations, and orders of the NRC initiative, grant exemptions from the
now or hereafter in effect. The facility requirements of 10 CFR part 50 when:
SUMMARY: The U.S. Nuclear Regulatory consists of a pressurized-water reactor (1) The exemptions are authorized by
Commission (NRC) is issuing an located in Coffey County, Kansas. law, will not present an undue risk to
exemption in response to a January 27, public health or safety, and are
2016, request, as supplemented on May II. Request/Action
consistent with the common defense
19, 2016, from Wolf Creek Nuclear Pursuant to § 50.12 of title 10 of the and security; and (2) when special
Operating Corporation (WCNOC or the Code of Federal Regulations (10 CFR), circumstances are present. Under 10
licensee) in order to use Optimized ‘‘Specific exemptions,’’ the licensee CFR 50.12(a)(2), special circumstances
ZIRLOTM fuel rod cladding material at requested by letter dated January 27, include, among other things, when
Wolf Creek Generating Station (WCGS). 2016, as supplemented by letter dated application of the specific regulation in
DATES: The exemption was issued on May 19, 2016 (ADAMS Accession Nos. the particular circumstance would not
August 2, 2016. ML16033A470 and ML16161A509, serve, or is not necessary to achieve, the
ADDRESSES: Please refer to Docket ID respectively), an exemption from underlying purpose of the rule.
NRC–2016–0162 when contacting the specific requirements of 10 CFR 50.46,
‘‘Acceptance criteria for emergency core A. Special Circumstances
NRC about the availability of
information regarding this document. cooling systems [ECCS] for light-water Special circumstances, in accordance
You may obtain publicly-available nuclear power reactors,’’ and 10 CFR with 10 CFR 50.12(a)(2)(ii), are present
information related to this document part 50, appendix K, ‘‘ECCS Evaluation whenever application of the regulation
using any of the following methods: Models,’’ to allow the use of fuel rod in the particular circumstances is not
• Federal Rulemaking Web site: Go to cladding with Optimized ZIRLOTM alloy necessary to achieve the underlying
http://www.regulations.gov and search for future reload applications. The purpose of the rule. The underlying
for Docket ID NRC–2016–0162. Address regulations in 10 CFR 50.46 contain purpose of 10 CFR 50.46 and 10 CFR
questions about NRC dockets to Carol acceptance criteria for the ECCS for part 50, appendix K, is to establish
Gallagher; telephone: 301–415–3463; reactors fueled with zircaloy or acceptance criteria for ECCS
email: Carol.Gallagher@nrc.gov. For ZIRLOTM fuel rod cladding material. In performance. The regulations in 10 CFR
technical questions, contact the addition, 10 CFR part 50, appendix K, 50.46 and 10 CFR part 50, appendix K,
mstockstill on DSK3G9T082PROD with NOTICES
individual listed in the FOR FURTHER requires that the Baker-Just equation be are not directly applicable to Optimized
INFORMATION CONTACT section of this used to predict the rates of energy ZIRLOTM, even though the evaluations
document. release, hydrogen concentration, and described in the following sections of
• NRC’s Agencywide Documents cladding oxidation from the metal/water this exemption show that the intent of
Access and Management System reaction. The Baker-Just equation the regulation is met. Therefore, since
(ADAMS): You may obtain publicly- assumes the use of a zirconium alloy, the underlying purposes of 10 CFR
available documents online in the which is a material different from 50.46 and 10 CFR part 50, appendix K,
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![52912 Federal Register / Vol. 81, No. 154 / Wednesday, August 10, 2016 / Notices
using the standards described in 10 CFR Based on the above, the NRC staff exemption relates solely to the cladding
50.92(c), as presented below: concludes that the proposed exemption material specified in these regulations.
presents no significant hazards consideration
1. Does the proposed exemption involve a under the standards set forth in 10 CFR Dated at Rockville, Maryland, this 2nd day
significant increase in the probability or 50.92(c), and, accordingly, a finding of no of August 2016.
consequences of an accident previously significant hazards consideration is justified For the Nuclear Regulatory Commission.
evaluated? (i.e., satisfies the provision of 10 CFR Anne T. Boland,
Response: No. The proposed change would 51.22(c)(9)(i)).
allow the use of Optimized ZIRLOTM fuel rod Director, Division of Operating Reactor
cladding material in the reactors. The NRC Requirements in 10 CFR 51.22(c)(9)(ii) Licensing, Office of Nuclear Reactor
approved topical report WCAP–12610–P–A & Regulation.
The proposed exemption would allow
CENPD–404–P–A Addendum 1–A, [FR Doc. 2016–18979 Filed 8–9–16; 8:45 am]
‘‘Optimized ZIRLOTM,’’ prepared by
the use of Optimized ZIRLOTM fuel rod
BILLING CODE 7590–01–P
Westinghouse, addresses Optimized cladding material in the reactors.
ZIRLOTM and demonstrates that Optimized Optimized ZIRLOTM has essentially the
ZIRLOTM has essentially the same properties same properties as the currently
as the currently licensed ZIRLOTM. The fuel licensed ZIRLOTM. The use of the
cladding itself is not an accident initiator and Optimized ZIRLOTM fuel rod cladding OFFICE OF PERSONNEL
does not affect accident probability. Use of material will not significantly change MANAGEMENT
Optimized ZIRLOTM fuel rod cladding the types of effluents that may be
material will continue to meet all 10 CFR Excepted Service
released offsite, or significantly increase
50.46 acceptance criteria and, therefore, will
not increase the consequences of an accident.
the amount of effluents that may be AGENCY: U.S. Office of Personnel
Therefore, the proposed change does not released offsite. Therefore, the provision Management (OPM).
involve a significant increase in the of 10 CFR 51.22(c)(9)(ii) is satisfied. ACTION: Notice.
probability or consequences of an accident Requirements in 10 CFR 51.22(c)(9)(iii)
previously evaluated. SUMMARY: This notice identifies
2. Does the proposed exemption create the The proposed exemption would allow Schedule A, B, and C appointing
possibility of a new or different kind of the use of the Optimized ZIRLOTM fuel authorities applicable to a single agency
accident from any accident previously rod cladding material in the reactors. that were established or revoked from
evaluated? Optimized ZIRLOTM has essentially the
Response: No. The use of Optimized May 1, 2016 to May 31, 2016.
same properties as the currently
ZIRLOTM fuel rod cladding material will not FOR FURTHER INFORMATION CONTACT:
licensed ZIRLOTM. The use of the
result in changes in the operation or Senior Executive Resources Services,
configuration of the facility. Topical Report Optimized ZIRLOTM fuel rod cladding
material will not significantly increase Senior Executive Service and
WCAP–12610–P–A & CENPD–404–P–A Performance Management, Employee
demonstrated that the material properties of individual occupational radiation
exposure, or significantly increase Services, (202) 606–2246.
Optimized ZIRLOTM are similar to those of
standard ZIRLOTM. Therefore, the Optimized cumulative occupational radiation SUPPLEMENTARY INFORMATION: In
ZIRLOTM fuel rod cladding material will exposure. Therefore, the provision of 10 accordance with 5 CFR 213.103,
perform similarly to those fabricated from CFR 51.22(c)(9)(iii) is satisfied. Schedule A, B, and C appointing
standard ZIRLOTM, therefore precluding the authorities available for use by all
possibility of the fuel cladding becoming an Conclusion agencies are codified in the Code of
accident initiator and causing a new or
Based on the above, the NRC staff Federal Regulations (CFR). Schedule A,
different type of accident.
Therefore, the proposed change does not concludes that the proposed exemption B, and C appointing authorities
create the possibility of a new or different meets the eligibility criteria for the applicable to a single agency are not
kind of accident from any previously categorical exclusion set forth in 10 CFR codified in the CFR, but the Office of
evaluated. 51.22(c)(9). Therefore, in accordance Personnel Management (OPM)
3. Does the proposed exemption involve a with 10 CFR 51.22(b), no environmental publishes a notice of agency-specific
significant reduction in a margin of safety? impact statement or environmental authorities established or revoked each
Response: No. The proposed change will assessment need be prepared in month in the Federal Register at
not involve a significant reduction in the connection with the NRC’s proposed www.gpo.gov/fdsys/. OPM also
margin of safety, because it has been issuance of this exemption. publishes an annual notice of the
demonstrated that the material properties of
the Optimized ZIRLOTM are not significantly consolidated listing of all Schedule A,
IV. Conclusions
different from those of standard ZIRLOTM. B, and C appointing authorities, current
Optimized ZIRLOTM is expected to perform
Accordingly, the Commission has as of June 30, in the Federal Register.
similarly to standard ZIRLOTM for all normal determined that, pursuant to 10 CFR
50.12, the exemption is authorized by Schedule A
operating and accident scenarios, including
both LOCA and non-LOCA scenarios. For law, will not present an undue risk to No schedule A authorities to report
LOCA scenarios, where the slight difference the public health and safety, and is during May 2016.
in the Optimized ZIRLOTM material consistent with the common defense
properties, relative to standard ZIRLOTM and security. Also, special Schedule B
could have some impact on the overall circumstances are present. Therefore, No schedule B authorities to report
accident scenario, plant-specific LOCA the Commission hereby grants WCNOC
analyses using the Optimized ZIRLOTM
during May 2016.
properties demonstrate that the acceptance
an exemption from the requirements of
10 CFR 50.46 and 10 CFR part 50, Schedule C
mstockstill on DSK3G9T082PROD with NOTICES
criteria of 10 CFR 50.46 have been satisfied.
Therefore, the proposed change does not appendix K, to allow the use of The following Schedule C appointing
involve a significant reduction in a margin of Optimized ZIRLOTM fuel rod cladding authorities were approved during May
safety. material at WCGS. As stated above, this 2016.
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Document Created: 2016-08-10 01:59:12
Document Modified: 2016-08-10 01:59:12
| 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 August 2, 2016. | |
| Contact | Carl F. Lyon, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-2296, email: [email protected] | |
| FR Citation | 81 FR 52910 |
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