ML080380002

Exemption to Allow the Use of Optimized Zirlo Fuel Rod Cladding Material

ML080380002
Person / Time
Site:	Waterford
Issue date:	03/11/2008
From:	Kalyanam N NRC/NRR/ADRO/DORL/LPLIV
To:	Entergy Operations
Kalyanam N, NRR/DORL/LP4, 415-1480
References
TAC MD5426, FOIA/PA-2011-0148, FOIA/PA-2011-0137
Download: ML080380002 (9)

Text

March 11, 2008

Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - EXEMPTION FROM SPECIFIC REQUIREMENTS IN 10 CFR 50.46 AND FROM APPENDIX K TO 10 CFR PART 50, TO ALLOW THE USE OF OPTIMIZED ZIRLOŽ FUEL ROD CLADDING MATERIAL (TAC NO. MD5426)

Dear Sir or Madam:

Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.12, the Commission has granted an exemption from specific requirements to the cladding material specified in 10 CFR 50.46, AAcceptance criteria for emergency core cooling systems for light-water nuclear power reactors,@ and from Appendix K to 10 CFR Part 50, AECCS Evaluation Models@ to allow the use of Optimized ZIRLOŽ fuel rod cladding material in future core reload applications for the Waterford Steam Electric Station, Unit 3. This action is in response to your letter dated April 24, 2007.

A copy of the exemption has been forwarded to the Office of the Federal Register for publication.

Your amendment request, which proposes to revise the Technical Specifications, is being reviewed and will be addressed separately from this exemption request, which, as noted above, is granted in the document included with this letter.

Sincerely, /RA/

N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382

Enclosure:

Exemption

cc w/encl: See next page

ML080380002 (*) See previous concurrence OFFICE NRR/LPL4/PM NRR/LPL4/LA DSS/SNPB* DIRS/ITSB NRR/LPL4/BC DORL/D OGC - NLO DORL/D [sign] NAME NKalyanam JBurkhardt (*) AMendiola (*) GWaig: TKolb for (*) THiltz (*) CHaney (*) PMoulding (*) CHaney DATE 3/6/08 2/12/08 2/15/08 2/21/08 2/21/08 2/21/08 3/4/08 3/11/08 Waterford Steam Electric Station, Unit 3 (2/25/08) cc: Senior Vice President Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995 Vice President, Oversight Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995 Senior Manager, Nuclear Safety & Licensing Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995

Senior Vice President & Chief Operating Officer Entergy Operations, Inc. P.O. Box 31995 Jackson, MS 39286-1995 Associate General Counsel Entergy Nuclear Operations P.O. Box 31995 Jackson, MS 39286-1995 Manager, Licensing Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 Mr. Timothy Pflieger Environmental Scientist - Supervisor REP&R-CAP-SPOC Louisiana Department of Environmental Quality P.O. Box 4312 Baton Rouge, LA 70821-4312

Parish President Council St. Charles Parish P.O. Box 302 Hahnville, LA 70057 Chairman Louisiana Public Services Commission P.O. Box 91154 Baton Rouge, LA 70825-1697 Mr. Richard Penrod, Senior Environmental Scientist/State Liaison Officer Office of Environmental Services Northwestern State University Russell Hall, Room 201 Natchitoches, LA 71497

Resident Inspector Waterford NPS P.O. Box 822 Killona, LA 70057-0751

Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011

7590-01-P UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ENTERGY OPERATIONS, INC.

WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 EXEMPTION

1.0 BACKGROUND

Entergy Operations, Inc. (the licensee), is the holder of Facility Operating License No. NPF-38, which authorizes operation of the Waterford Steam Electric Station, Unit 3 (Waterford 3). 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, the Commission) now or hereafter in effect.

The facility consists of one pressurized-water reactor located in St. Charles Parish, Louisiana.

2.0 REQUEST/ACTION Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.46 (a)(1)(i), "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,"

states:

"Each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical zircaloy or ZIRLO cladding must be provided with an emergency core cooling system (ECCS) that must be designed so that its calculated cooling performance following postulated loss-of-coolant accidents conforms to the criteria set forth in paragraph (b) of this section." Paragraph I.A.5 of Appendix K to 10 CFR Part 50 states: "Metal--Water Reaction Rate. The rate of energy release, hydrogen generation, and cladding oxidation from the metal/water reaction shall be calculated using the Baker-Just equation (Baker, L., Just, L.C., "Studies of Metal Water Reactions at High Temperatures, III.

Experimental and Theoretical Studies of the Zirconium-Water Reaction," ANL-6548, page 7, May 1962)." The April 24, 2007, exemption request relates to the specific types of cladding material specified in the regulations. As written, the regulations presume the use of zircaloy or ZIRLOŽ fuel rod cladding. Also, 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 Optimized ZIRLOŽ cladding for determining acceptable fuel performance. Thus, exemptions from the specific requirements of 10 CFR 50.46 and Appendix K to 10 CFR Part 50 are needed to allow a cladding alloy other than zircaloy or ZIRLOŽ.

Accordingly, this exemption would result in changes to the plant by allowing only the use of an alternative cladding alloy other than zircaloy or ZIRLOŽ in lieu of meeting the specific cladding requirements of 10 CFR 50.46 and Appendix K to 10 CFR Part 50. Specifically, the exemption would allow the use of Optimized ZIRLOŽ cladding. All other requirements of 10 CFR 50.46 and of Appendix K to 10 CFR Part 50 would remain applicable. 3.0 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. As discussed below, special circumstances are present because the continued operation of Waterford 3 with zircaloy or ZIRLOŽ fuel rod cladding, rather than with Optimized ZIRLOŽ, is not necessary to achieve the underlying purpose of the rule.

Authorized by Law This exemption would result in changes to the plant by allowing use of an alternative cladding (Optimized ZIRLOŽ) alloy other than zircaloy or ZIRLOŽ in lieu of meeting the requirements of 10 CFR 50.46 and Appendix K to 10 CFR Part 50. As stated above, 10 CFR 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR 50.46 and Appendix K to 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 The underlying purpose of 10 CFR 50.46 is to establish acceptance criteria for adequate ECCS performance. The underlying purpose of Paragraph I.A.5 of Appendix K to 10 CFR Part 50 is to calculate the rates of energy, hydrogen concentration, and cladding oxidation from the metal-water reaction using the Baker-Just equation. Based on the above and on the NRC staff's previously documented topical report safety review as discussed further below, in the context of the proposed exemption, no new accident precursors are created by allowing the use of an alternative cladding (Optimized ZIRLOŽ) alloy other than zircaloy or ZIRLOŽ. Thus, the probability of postulated accidents is not increased. For the same reasons, the consequences of postulated accidents are not increased. Therefore, there is no undue risk to public health and safety.

Consistent with Common Defense and Security The proposed exemption would allow the use of an alternative cladding (Optimized ZIRLOŽ) alloy other than zircaloy or ZIRLOŽ. This change to the plant has no relation to security issues. Therefore, the common defense and security is not impacted by this exemption.

Special Circumstances Pursuant to 10 CFR 50.12(a)(2)(ii), special circumstances are present whenever application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule. 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 review of topical reports submitted by Westinghouse Electric Company, LLC (Westinghouse), and subject to compliance with the specific conditions of approval established therein, the NRC staff finds that the applicability of these ECCS acceptance criteria to Optimized ZIRLOŽ has been demonstrated by Westinghouse. Ring compression tests performed by Westinghouse on Optimized ZIRLOŽ (NRC-reviewed, approved, and documented in Appendix B of WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, AOptimized ZIRLOŽ,@ July 2006, Agencywide Documents Access and Management System (ADAMS) Accession No. ML062080576) 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 (ECR). Furthermore, the NRC staff has concluded that oxidation measurements provided by the licensee (letter from Westinghouse to NRC, "SER Compliance with WCAP-12610-P-A & CENPD-404-P-A Addendum 1-A 'Optimized ZIRLOŽ'," LTR-NRC-07-58, November 6, 2007, ADAMS Accession No. ML073130562) illustrate that oxide thickness (and associated hydrogen pickup) for Optimized ZIRLOŽ at any given burnup would be less than both zircaloy-4 and ZIRLOŽ. Hence, the NRC staff concludes that Optimized ZIRLOŽ would be expected to maintain better post-quench ductility than ZIRLOŽ. This finding is further supported by an ongoing loss-of-coolant accident (LOCA) research program at Argonne National Laboratory, which has identified a strong correlation between cladding hydrogen content (due to in-service corrosion) and post-quench ductility.

In addition, utilizing currently-approved LOCA models and methods, Westinghouse will perform an evaluation to ensure that the Optimized ZIRLOŽ fuel rods continue to satisfy 10 CFR 50.46 acceptance criteria. For the reasons above, granting the exemption request will ensure that the underlying purpose of the rule is achieved. Paragraph I.A.5 of Appendix K to 10 CFR Part 50 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 the rule would not permit use of the equation for Optimized ZIRLOŽ cladding for determining acceptable fuel performance. However, the NRC staff has found that metal-water reaction tests performed by Westinghouse on Optimized ZIRLOŽ (NRC-reviewed, approved, and documented in Appendix B of WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A and subject to compliance with the specific conditions of approval established therein) demonstrate conservative reaction rates relative to the Baker-Just equation. Thus, the NRC staff agrees that application of Appendix K, paragraph I.A.5 is not necessary to achieve the underlying purpose of the rule in these circumstances. Accordingly, the NRC staff has determined that the special circumstances required by 10 CFR 50.12 (a)(2)(ii) for granting an exemption from the aforementioned specific paragraphs of 10 CFR 50.46 and Appendix K of 10 CFR Part 50 exist.

4.0 CONCLUSION

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 Entergy Operations, Inc., an exemption from the specific cladding requirements of 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," and of Appendix K to 10 CFR Part 50, "ECCS Evaluation Models," to allow the use of Optimized ZIRLOŽ fuel rod cladding material in future core reload applications for Waterford 3. Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will not have a significant effect on the quality of the human environment as published in the Federal Register on October 22, 2007 (72 FR 59560). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 11th day of March 2008.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation