Nuclear Regulatory Commission March 2015 – Federal Register Recent Federal Regulation Documents
Results 51 - 70 of 70
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM Underground Maximum Capacity Canister Storage System, Certificate of Compliance No. 1040
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by adding the Holtec International HI- STORM Underground Maximum Capacity (UMAX) Canister Storage System, Certificate of Compliance (CoC) No. 1040, to the ``List of approved spent fuel storage casks.'' Holtec International's intent with this design is to provide an underground storage option compatible with the Holtec International HI-STORM FLOOD/WIND (FW) System (CoC No. 1032).
Combined License Application for Turkey Point Nuclear Plant, Unit Nos. 6 and 7
The U.S. Nuclear Regulatory Commission (NRC) and the U.S. Army Corps of Engineers (USACE), Jacksonville District, are issuing for public comment NUREG-2176, ``Draft Environmental Impact Statement for Combined Licenses (COLs) for Turkey Point Nuclear Plant, Units 6 and 7,'' to support the environmental review for the COL. Florida Power and Light Company (FPL) submitted an application for COLs to construct and operate two new nuclear power plants at its Turkey Point site near Homestead, Florida.
Impact of Variation in Environmental Conditions on the Thermal Performance of Dry Storage Casks
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-2174, ``Impact of Variation in Environmental Conditions on the Thermal Performance of Dry Storage Casks.'' This report evaluates spent fuel dry storage cask thermal impact of varying environmental conditions and transient thermal behavior when subjected to a sudden boundary condition change. Different cask designs are evaluated (vertical underground, vertical aboveground, and horizontal aboveground). The NRC staff will consider the analysis results in this report when performing technical reviews, applicants should consider them when applying for cask certification. These results can be used as additional guidance when considering the thermal impact of the environmental factors in the thermal performance of dry storage systems.
Considerations in Licensing High Burnup Spent Fuel in Dry Storage and Transportation
The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on the draft regulatory issue summary (RIS) addressing considerations for licensing high burnup spent fuel in dry storage and transportation. The purpose of this RIS is to provide information on some approaches acceptable to the NRC for demonstrating compliance with regulations in applications for issuance of dry storage cask certificate of compliance (CoCs), independent spent fuel storage installation (ISFSI) licenses, and CoCs for transportation packages involving high burnup spent fuel (HBF).
Scope Expansion of the Post-Investigation Alternative Dispute Resolution Program
The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision to its Enforcement Policy (Enforcement Policy or Policy) to incorporate Commission direction to add escalated non-willful (traditional) enforcement cases with the potential for civil penalties within the scope of the Commission's Alternative Dispute Resolution Program and to make other conforming edits.
Reviewing and Assessing the Financial Condition of Operating Power Reactor Licensees, Including Requests for Additional Information
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG), OL/FR-ISG-2014-01, ``Reviewing and Assessing the Financial Condition of Operating Power Reactor Licensees, Including Requests for Additional Information,'' dated February 17, 2015. The ISG provides clarifying guidance to the NRC staff when reviewing licensee financial information, and when requesting additional information regarding licensee financial conditions, as authorized under the NRC's regulations. Such review and inquiry are performed by NRC staff for currently operating power reactor licensees, absent a licensing action such as a license transfer.
Guidance for Evaluation of Acute Chemical Exposures and Proposed Quantitative Standards
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG), ``Guidance for Evaluation of Acute Chemical Exposures and Proposed Quantitative Standards.'' The ISG supplements existing guidance in NUREG-1520, ``Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility,'' by providing additional guidance for the NRC to follow when evaluating descriptions of proposed quantitative standards. The ISG identifies sources of information on which proposed quantitative standards may be based.
Information Collection: NRC Request for Information Concerning Patient Release Practices
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on this proposed collection of information. The information collection is entitled, ``NRC Request for Information Concerning Patient Release Practices.''
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular biweekly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued from February 5, 2015 to February 18, 2015. The last biweekly notice was published on February 17, 2015.
Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of four amendment requests. The amendment requests are for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2; Peach Bottom Atomic Power Station, Unit 2; Diablo Canyon Nuclear Power Plant, Units 1 and 2; and Vogtle Electric Generating Plant, Units 1 and 2, Joseph M. Farley Nuclear Plant, Units 1 and 2, and Edwin I. Hatch Nuclear Plant, Units 1 and 2. The NRC proposes to determine that each amendment request involves no significant hazards consideration. In addition, each amendment request contains sensitive unclassified non-safeguards information (SUNSI).
Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating, Unit 2
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License No. DPR-26, issued to Entergy Nuclear Operations, Inc., for operation of the Indian Point Nuclear Generating, Unit 2. The proposed amendment would allow a revision to the acceptance criteria for the Surveillance Requirement 3.1.4.2 for Control Rod G-3. During the last two performances of this Surveillance on September 18, 2014, and December 11, 2014, Control Rod G-3 misalignment occurred with Shutdown Bank B group movement as displayed by the Individual Rod Position Indication and Plant Instrument Computer System. The proposed change is to defer subsequent testing of the Control Rod G-3 until repaired during the next refuel outage (March 2016) or forced outage long enough to repair the Control Rod.
Duke Energy Florida, Inc.; Crystal River Unit 3 Nuclear Generating Plant
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of exemptions in response to a request from Duke Energy Florida, Inc. (DEF, the licensee) that would permit the licensee to reduce its emergency planning (EP) activities at the Crystal River Unit 3 Nuclear Generating Plant (CR-3). CR-3 has been shut down since September 26, 2009, and the final removal of fuel from the reactor vessel was completed on May 28, 2011. By letter dated February 20, 2013, DEF submitted a certification to the NRC of permanent cessation of power operations and the removal of fuel from the reactor vessel. The licensee is seeking exemptions that would eliminate the requirements to maintain offsite radiological emergency plans and reduce some of the onsite EP activities based on the reduced risks at the permanently shutdown and defueled reactor. Offsite EP provisions would still exist using a comprehensive emergency management plan process. The NRC staff is issuing a final environmental assessment (EA) and final finding of no significant impact (FONSI) associated with the proposed exemptions.
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