The Southern Nuclear Operating Company, Inc. (SNC, the licensee) is the holder of the Renewed Facility Operating License No. NPF-5 which authorizes operation of the Edwin I. Hatch Nuclear Plant, Unit No. 2 (HNP-2). The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC or the Commission) now or hereafter in effect.
The facility consists of a boiling-water reactor located in Appling County in Georgia.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.12, “Specific Exemptions”, SNC has, by letters dated March 21, May 2, August 8 and September 22, 2008, requested an exemption from the fuel cladding material requirements in 10 CFR 50.46, “Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors,” and Appendix K to 10 CFR part 50, “ECCS Evaluation Models,” (Appendix K). The regulation in 10 CFR 50.46 contains acceptance criteria for emergency core cooling system (ECCS) for reactors fueled with zircaloy or ZIRLOTM cladding. In addition, 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 exemption request relates solely to the specific types of cladding material specified in these regulations. As written, the regulations Start Printed Page 67556presume the use of zircaloy or ZIRLOTM fuel rod cladding. Thus, an exemption from the requirements of 10 CFR 50.46, and Appendix K is needed to irradiate a lead test assembly (LTA) comprised of different cladding alloys at HNP-2.
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 Section 50.12(a)(2) of 10 CFR, 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.
Authorized by Law
This exemption would allow the licensee to insert two lead test fuel assemblies with fuel rod cladding that does not meet the definition of Zircaloy or ZIRLOTM as specified by 10 CFR 50.46, and Appendix K, into the core of HNP-2, beginning with fuel cycle 21. 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 of the licensee's proposed exemption will 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.
No Undue Risk to Public Health and Safety
In regard to the fuel mechanical design, the exemption request relates solely to the specific types of cladding material specified in the regulations. The underlying purpose of 10 CFR 50.46 is to establish acceptance criteria for ECCS performance. In Section VI of its letter dated May 2, 2008, SNC provides a technical basis supporting the continued applicability of the 50.46 Paragraph (b) fuel criteria to GNF-Ziron. Quench tests under a restrained load have been conducted on GNF-Ziron samples oxidized to various levels at elevated loss-of-coolant accident (LOCA) temperatures. While these tests differ from the post-steam oxidized ring-compression testing (which forms the basis of the 50.46 post-quench ductility criteria), these results provide reasonable assurance that the 17 percent oxidation and 2200 degree Farenheit criteria are valid for GNF-Ziron and meet the underlying purpose of the rule, which is to maintain a degree of post-quench ductility in the fuel cladding material.
Based on an ongoing LOCA research program at Argonne National Laboratory, as discussed in NRC Research Information Letter 0801, “Technical Basis for Revision of Embrittlement Criteria in 10 CFR 50.46,” ADAMS Accession No. ML081350225, cladding corrosion (and associated hydrogen pickup) has a significant impact on post-quench ductility. Post-irradiation examinations provided by the licensee demonstrate the favorable hydrogen pickup characteristics of GNF-Ziron as compared with standard zircaloy. Hence, the GNF-Ziron fuel rods would be less susceptible to the detrimental effects of hydrogen uptake during normal operation and their impact on post-quench ductility.
Paragraph I.A.5 of Appendix K to 10 CFR Part 50 states that the rates of energy, 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 the rule would not permit use of the equation for the LTA cladding for determining acceptable fuel performance. Metal-water reaction tests performed by GNF on GNF-Ziron demonstrate conservative reaction rates relative to the Baker-Just equation. Thus, application of Appendix K, Paragraph I.A.5 is not necessary for the licensee to achieve its underlying purpose in these circumstances.
High temperature perforation test results were provided. These test results illustrate similar burst characteristics of GNF-Ziron as compared with standard zircaloy. In addition, the licensee provides further comparisons of material properties between GNF-Ziron and zircaloy. Based upon this comparison of material properties, GNF and SNC believe that currently approved methods and models are directly applicable to GNF-Ziron. Based upon the material properties provided in SNC's letters dated May 2 and August 8, 2008, the NRC staff finds the use of current LOCA models and methods acceptable for the purpose of evaluating LTAs containing a limited number of GNF-Ziron fuel rods.
In support of their exemption request, SNC submitted, with its letter dated August 8, 2008, a GNF document entitled, “Impact of GNF-Ziron Cladding on Thermal-Mechanical Licensing Limits”. This report provides an assessment of the potential impact of differences in material properties on the GSTR-M fuel thermal-mechanical methodology. While not directly related to the 50.46 exemption request, the NRC staff finds the conclusion of this report acceptable for the purpose of evaluating LTAs containing a limited number of GNF-Ziron fuel rods. Further NRC staff review may be necessary prior to batch application of GNF-Ziron fuel cladding material.
Through mechanical testing and a comparison of material properties, SNC has provided reasonable assurance that anticipated in-reactor performance will be acceptable. Further, the licensee has demonstrated that the use of current methods and models are reasonable for evaluating the cladding's performance in response to anticipated operational occurrences and accidents. Nevertheless, as with any developmental cladding alloy, the NRC staff requires a limitation on the total number of fuel rods clad in a developmental alloy in order to ensure a minimal impact on the simulated progression and calculated consequences of postulated accidents. This limitation is directly related to the available material properties (both unirradiated and irradiated) used to judge the cladding alloy's anticipated in-reactor performance. Based on the material properties data presented within the application attachments, the NRC staff finds the HNP-2 LTA program acceptable with respect to achieving the underlying purpose of 10 CFR 50.46 and Appendix K to 10 CFR part 50.
Based upon results of metal-water reaction tests and mechanical testing which ensure the applicability of ECCS models and acceptance criteria, the limited number and anticipated performance of the advanced cladding fuel rods, and the use of approved LOCA models to ensure that the LTAs satisfy 10 CFR 50.46 acceptance criteria, the NRC staff finds it acceptable to grant an exemption from the requirements of 10 CFR 50.46 and Appendix K to 10 CFR part 50 for the use of two LTAs within HNP-2.
Consistent With Common Defense and Security
The proposed exemption would allow the licensee to insert two lead test fuel assemblies with fuel rod cladding that does not meet the definition of Zircaloy or ZIRLOTM as specified by 10 CFR 50.46, and Appendix K, into the core of HNP-2, beginning with fuel cycle 21. This change has no relation to security issues. Therefore, the common defense Start Printed Page 67557and security is not impacted by this exemption.
Special circumstances, in accordance with 10 CFR 50.12, 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 emergency core cooling system performance. The wording of the regulations in 10 CFR 50.46 and Appendix K is not directly applicable to these advanced cladding alloys, even though the evaluations discussed above show that the intent of the regulations is met. Therefore, since the underlying purpose of 10 CFR 50. 46 and Appendix K is achieved with the use of these advanced cladding alloys, the special circumstances required by 10 CFR 50.12 for the granting of an exemption from 10 CFR 50.46 and Appendix K exist.
Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. Also, special circumstances are present. Therefore, the Commission hereby grants SNC exemptions from the requirements of 10 CFR 50.46, and 10 CFR Part 50, Appendix K, to allow the limited use of two LTAs with selected rods clad with GNF-Ziron cladding during fuel cycles 21 through 23 for the HNP-2 plant.
This exemption is effective upon issuance.Start Signature
Dated at Rockville, Maryland, this 7th day of November 2008.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E8-27102 Filed 11-13-08; 8:45 am]
BILLING CODE 7590-01-P