Nuclear Information & Resource Service v. Nuclear Regulatory Commission

457 F.3d 941, 62 ERC (BNA) 1934, 2006 U.S. App. LEXIS 18477, 2006 WL 2042893
CourtCourt of Appeals for the Ninth Circuit
DecidedJuly 24, 2006
Docket04-71432
StatusPublished
Cited by44 cases

This text of 457 F.3d 941 (Nuclear Information & Resource Service v. Nuclear Regulatory Commission) is published on Counsel Stack Legal Research, covering Court of Appeals for the Ninth Circuit primary law. Counsel Stack provides free access to over 12 million legal documents including statutes, case law, regulations, and constitutions.

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Nuclear Information & Resource Service v. Nuclear Regulatory Commission, 457 F.3d 941, 62 ERC (BNA) 1934, 2006 U.S. App. LEXIS 18477, 2006 WL 2042893 (9th Cir. 2006).

Opinion

RYMER, Circuit Judge.

The Nuclear Information and Resource Service, Committee to Bridge the Gap, Public Citizen, Inc., and Redwood Alliance (collectively NIRS) challenge the Nuclear Regulatory Commission’s (NRC) rulemak-ing, which revised regulations governing the exemption standards for the transportation of radioactive material. NIRS argues that NRC failed to comply with its obligations under the National Environmental Policy Act (NEPA), 42 U.S.C. § 4332, by not preparing an Environmental Impact Statement (EIS) and making a finding of no significant impact (FONSI) without basis. We are obligated before reaching the merits of NIRS’s NEPA challenge to determine whether NIRS has standing to bring its complaint in federal court. We conclude that it does not, and we therefore dismiss NIRS’s petition for review.

I

NRC and the Department of Transportation (DOT) co-regulate the transporta *945 tion of radioactive material in the United States. NRC is authorized to regulate the use and possession of nuclear materials, which it does by prescribing regulations for its licensees’ packaging and transport of such materials. See 42 U.S.C. § 2201(b); 10 C.F.R. § 71.0. DOT is authorized to designate material as hazardous and to prescribe regulations for the safe transportation of such material. 49 U.S.C. §§ 5103(a), (b)(1). Under this authority, DOT has promulgated its Hazardous Materials Regulations (HMR), which regulate the shipment of radioactive materials, including packaging, labeling, and notification, and which apply in addition to NRC’s requirements for the shipment of nuclear materials. 49 C.F.R. §§ 171-179. A Memorandum of Understanding (MOU) governs the respective responsibilities of NRC and DOT. Transportation of Radioactive Materials; Memorandum of Understanding, 44 Fed.Reg. 38,690 (July 2, 1979). As NRC summarizes the MOU, “DOT is responsible for regulating safety in transportation of all hazardous materials, including radioactive materials, whereas NRC is responsible for regulating safety in receipt, possession, use, and transfer of byproduct, source, and special nuclear materials.” Thus, DOT adopts regulations for all shippers and carriers of hazardous materials, including safety standards for shipping and packaging radioactive material; NRC develops safety standards for packaging certain radioactive materials and regulates its licensees; and DOT “issue[s] complete and comprehensive Federal regulations for the packaging and transportation of all radioactive materials as part of its overall body of Federal regulations.” Id.

The United States is a member of the International Atomic Energy Agency (IAEA), 1 which, in 1961, adopted international regulations for the safe transportation of radioactive material. The IAEA regulations were published in Regulations for the Safe Transport of Radioactive Materials, IAEA Safety Series No. 6 (SS-6). As a Member State, the United States harmonized its domestic regulations with the IAEA standards. The IAEA periodically has revised SS-6 with “substantial input” from DOT, and, following each revision, DOT and NRC have amended domestic regulations to make them compatible with the IAEA standards. The latest significant revision to the SS-6 was published in December 1996, and redesignated TSR-l in June 2000. The principal change from the prior IAEA regulations to TS-R-1 at issue in this case involves radionuclide exemption values.

Following the IAEA revisions, NRC and DOT began the rulemaking process for revising domestic regulations on exemption values to make them compatible with the new IAEA standards — DOT with its IAEA Compatibility Amendments and NRC with conforming amendments to its Part 71 Regulations. See Compatibility with IAEA Transportation Safety Standards (TS-R-1) and Other Transportation Safety Amendments; Final Rule, 69 Fed. Reg. 3,698 (Jan. 26, 2004) (to be codified at 10 C.F.R. pt. 71) (“NRC Final Rule”); Hazardous Materials Regulations; Compatibility With the Regulations of the International Atomic Energy Agency; Final Rule, 69 Fed.Reg. 3,632 (Jan. 26, 2004) (to be codified at 49 C.F.R. pts. 171-78) (“DOT Final Rule”). “Exemption values” are the standards adopted for determining whether nuclear material is subject to reg *946 ulation during transport; if the radioactivity of the material is below the exemption value, then the material is “exempt” and not subject to regulation. NIRS here challenges NRC’s change from an “activity concentration” to a “dose-based” standard for setting exemption values. NRC Final Rule, 69 Fed.Reg. at 3,711-20, 3,765, 3,791; id. at 3,807-13 (setting forth the exemption provisions); see also DOT Final Rule, 69 Fed.Reg. at 3,634-36, 3,656, 3,658.

Before adopting the regulation, NRC (and DOT) applied a uniform “activity concentration” standard to exempt transportation of low-radioactivity material from regulation. “Activity concentration” refers to the number of nuclear disintegrations per second in a gram of material and is commonly measured in Becquerels. A Becquerel is one radioactive disintegration per second. This prior NRC/DOT standard, which was also the pre-1996 IAEA standard, established 70-Becquerels per gram (Bq/g) as the uniform activity concentration standard; radioactive material with fewer than 70 disintegrations per second in a gram was exempted from NRC regulation during transport.

In 1996, the IAEA determined that there was no technical justification for the single activity concentration value of 70 Bq/g and concluded that the technically sound approach was a dose-based standard, which it adopted. Dose depends not only on the number of disintegrations per second but also on the type and energy of the radiation emitted by a nuclear disintegration. Dose limits are expressed in “rems” or “millirems” (mrem). To develop the dose-based approach, the IAEA used safety standards from a 1996 IAEA study — the “BSS” study, Safety Series No. 115, Internationa] Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. The BSS study used a dose-based approach in fixed facility exposure scenarios, as opposed to transport scenarios, and it calculated for each radionuclide an exemption threshold that would limit an effective annual dose to 1 mrem or less per year. 2 The IAEA researchers performed calculations on a subset of BSS scenarios and calculated the activity concentration for each of twenty radionuclides that would result in a dose of 1 mrem per year to transport workers in transportation scenarios. They concluded that “[d]ue to differences in radionuclide radiation emissions, exposure pathways, etc., the resulting radionuclide-specific activity concentrations varied widely.” 69 Fed.Reg. at 3711.

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457 F.3d 941, 62 ERC (BNA) 1934, 2006 U.S. App. LEXIS 18477, 2006 WL 2042893, Counsel Stack Legal Research, https://law.counselstack.com/opinion/nuclear-information-resource-service-v-nuclear-regulatory-commission-ca9-2006.