The FirstEnergy Nuclear Operating Company (FENOC/ the licensee) is the holder of Facility Operating License No. NPF-58 which authorizes operation of Perry Nuclear Power Plant (PNPP). 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 a boiling water reactor located on FENOC's PNPP site, which is located in Lake County, Ohio.
Title 10 of the Code of Federal Regulations (10 CFR) part 50, Appendix G requires that pressure-temperature (P-T) limits be established for reactor pressure vessels (RPVs) during normal operating and hydrostatic or leak rate testing conditions. Specifically, 10 CFR part 50, Appendix G states that “[t]he appropriate requirements on * * * the pressure-temperature limits and minimum permissible temperature must be met for all conditions.” Appendix G of 10 CFR part 50 specifies that the requirements for these limits are the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), Section XI, Appendix G Limits.
To address provisions of amendments to the technical specifications P-T limits in the submittal dated June 4, 2002, the licensee requested that the staff exempt PNPP from application of specific requirements of 10 CFR part 50, § 50.60(a) and Appendix G, and substitute use of ASME Code Case N-640. Code Case N-640 permits the use of an alternate reference fracture toughness (KIc fracture toughness curve instead of KIa fracture toughness curve) for reactor vessel materials in determining the P-T limits. Since the Kic fracture toughness curve shown in ASME Code, Section XI, Appendix A, Figure A-2200-1 provides greater allowable fracture toughness than the Start Printed Page 24025corresponding KIa fracture toughness curve of ASME Code, Section XI, Appendix G, Figure G-2210-1, using the Kic fracture toughness, as permitted by Code Case N-640, in establishing the P-T limits would be less conservative than the methodology currently endorsed by 10 CFR part 50, appendix G. Considering this, an exemption to apply the Code Case would be required by 10 CFR 50.60.
The licensee proposed to revise the P-T limits for PNPP using the KIc fracture toughness curve, in lieu of the KIa fracture toughness curve, as the lower bound for fracture toughness.
Use of the KIc curve in determining the lower bound fracture toughness in the development of P-T operating limits curve is more technically correct than the KIa curve since the rate of loading during a heatup or cooldown is slow and is more representative of a static condition than a dynamic condition. The KIc curve appropriately implements the use of static initiation fracture toughness behavior to evaluate the controlled heatup and cooldown process of a reactor vessel. The staff has required use of the initial conservatism of the KIa curve since 1974 when the curve was codified. This initial conservatism was necessary due to the limited knowledge of RPV materials. Since 1974, additional knowledge has been gained about RPV materials, which demonstrates that the lower bound on fracture toughness provided by the KIa curve is well beyond the margin of safety required to protect the public health and safety from potential RPV failure.
In summary, the ASME Code, Section XI, Appendix G, procedure was conservatively developed based on the level of knowledge existing in 1974, concerning RPV materials and the estimated effects of operation. Since 1974, the level of knowledge about these topics has been greatly expanded. The NRC staff concurs that this increased knowledge permits relaxation of the ASME Code Section XI, Appendix G requirements by applying the KIc fracture toughness, as permitted by Code Case N-640, because compliance with ASME Code, Section XI, Appendix G is not necessary to achieve the underlying purpose of 10 CFR 50.60 and part 50, appendix G.
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. The staff accepts the licensee's determination that an exemption would be required to approve the use of Code Case N-640. The staff examined the licensee's rationale to support the exemption request and concurred that the use of the Code Case N-640 would meet the underlying intent of these regulations. Based upon a consideration of the conservatism that is explicitly incorporated into the methodologies of 10 CFR part 50, Appendix G; Appendix G of the Code; and Regulatory Guide 1.99, “Radiation Embrittlement of Reactor Vessel Material,” Revision 2, the staff concluded that compliance with ASME Code, Appendix G is not necessary to achieve the underlying purpose of 10 CFR 50.60 and 10 CFR part 50, Appendix G because the application of Code Case N-640 as described would provide an adequate margin of safety against brittle failure of the RPV. This is also consistent with the determination that the staff has reached for other licensees under similar conditions based on the same considerations. Therefore, the staff concludes that requesting exemption under the special circumstances of 10 CFR 50.12(a)(2)(ii) is appropriate and that the methodology of Code Case N-640 may be used to revise the P-T limits for PNPP.
Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), the exemption is authorized by law, will not endanger life or property or common defense and security, and is, otherwise, in the public interest. Therefore, the Commission hereby grants FENOC, exemption from the requirements of 10 CFR part 50, § 50.60(a) and 10 CFR part 50, Appendix G, for PNPP.
This exemption is effective upon issuance.Start Signature
Dated at Rockville, Maryland, this 29th day of April 2003.
For the Nuclear Regulatory Commission.
John A. Zwolinski,
Director, Division of Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. 03-11159 Filed 5-5-03; 8:45 am]
BILLING CODE 7590-01-P