[Federal Register Volume 59, Number 163 (Wednesday, August 24, 1994)] [Unknown Section] [Page 0] From the Federal Register Online via the Government Publishing Office [www.gpo.gov] [FR Doc No: 94-20756] [[Page Unknown]] [Federal Register: August 24, 1994] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-313/368, 72-1007; License Nos. DPR-51/NPF-6] Arkansas Nuclear One; Sierra Nuclear Corporation; Receipt of Petition for Director's Decision Under 10 CFR 2.206 Notice is hereby given that by Petition dated July 5, 1994, Dennis Dums, on behalf of the Wisconsin Citizen's Utility Board (CUB or Petitioner) requested that the Nuclear Regulatory Commission (NRC) take action with regard to Arkansas Nuclear One Units 1 and 2 (ANO). The Wisconsin CUB has previously corresponded with NRC concerning issues related to the NRC-certified VSC-24 dry storage cask due to Wisconsin Electric Power Company's planned use of the cask at its Point Beach nuclear power plant. Petitioner requests that: (1) The NRC determine the applicability of 10 CFR 72.48 to 10 CFR Subparts K and L and inform the public of this determination; (2) the NRC direct its legal counsel to determine whether Entergy Operations, Inc. (Entergy) is in violation of any NRC regulations regarding Entergy's use of 10 CFR 72.48 with respect to making modifications to the VSC-24 Cask Safety Analysis Report (SAR) for use at Arkansas Nuclear One (ANO) and inform the public of this determination; (3) the NRC determine whether Entergy's directions to Sierra Nuclear Corporation (SNC) to construct more casks than were approved was a violation of NRC regulations and order Entergy to cease its use of 10 CFR 72.48 until the NRC completes an investigation of the applicability of 10 CFR 72.48 to 10 CFR Part 72, Subparts K and L; and (4) the NRC determine whether SNC's construction of the casks for use at ANO was a violation of NRC regulations and order SNC to cease all construction of VSC-24 casks for use at ANO that are being constructed based on Entergy's 10 CFR 72.48 evaluation. Petitioner asserts as bases for these requests that: ANO is currently pursuing spent fuel storage at ANO through use of 10 CFR Subparts K and L; ANO currently intends to utilize the VSC-24 constructed by vendor SNC under an SAR submitted in October, 1991 and safety evaluation report (SER), issued by the NRC in April, 1993; an NRC response, dated January 31, 1994, to an October 13, 1993, public request for information, stated that Subparts K and L of 10 CFR Part 72 are silent on cask SAR and certificate changes after the final rule; and ANO request for a rule exemption to 10 CFR 72.234(c) was granted by the NRC to allow for the fabrication of four VSC-24 casks to the longer length prior to NRC approval of SNC's June 14, 1993, submittal of Revision 1 to the 1991 VSC-24 Cask SAR; a February 14, 1994, memorandum to NRC Assistant General Counsel Treby requested a legal interpretation of the applicability of 10 CFR 72.48 to general licenses issued under 10 CFR 72.210; a May 19, 1994, meeting was held regarding SNC's revisions to VSC-24 SAR and the applicability of 10 CFR 72.48 to general license users, as well as a June 3, 1994, memorandum regarding this meeting which stated that ``the license can make its own interpretation of the regulations;'' and a letter, dated June 2, 1994, from Entergy to the NRC which stated that Entergy has directed SNC to fabricate all fourteen planned casks with the increased length and that Entergy plans to continue to conduct evaluations in accordance with 10 CFR 72.48. The Petition has been referred to the Office of Nuclear Material Safety and Safeguards pursuant to 10 CFR 2.206. As provided by Section 2.206, appropriate action will be taken with regard to the specific issues raised by the Petition in a reasonable time. A copy of the Petition is available for inspection at the Commission's Public Document Room at 2120 L Street, NW., Washington, DC 20555. Dated at Rockville, Mayland, this 16th day of August 1994. For the Nuclear Regulatory Commission. Robert M. Bernero, Director, Office of Nuclear Material Safety and Safeguards. [FR Doc. 94-20756 Filed 8-23-94; 8:45 am] BILLING CODE 7590-01-M