ML13211A128
| ML13211A128 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/31/2013 |
| From: | NRC/FSME/DWMEP |
| To: | Dairyland Power Cooperative |
| Hickman J | |
| References | |
| TAC J00464 | |
| Download: ML13211A128 (2) | |
Text
(3) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as were produced by the prior operation of the facility.
A. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50. 59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is not authorized to operate the reactor. Fuel may not be placed in the reactor vessel.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 72, are hereby incorporated in the license. The licensee shall possess and maintain the facility in accordance with the Technical Specifications.
(3) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revision to 10 CFR 73 55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plan, which contains Safeguards Information protected under 10 CFR 73.21, is entitled, "Physical Security Plan for La Crosse Boiling Water Reactor (LACBWR)," as revised and reflecting exemptions from 10 CFR 73.55 granted June 20, 2012).
(4) Fire Protection The licensee shall implement and maintain in effect all provisions of the facility Fire Protection Program as described therein and as approved by the NRC.
The licensee may make changes to the approved Fire Protection Program without prior NRC approval if these changes do not decrease the effectiveness of fire protection for facilities, systems, and equipment which could result in a radiological hazard, taking into account the decommissioning plant conditions and activities.
Amendment No. 72
B. This Possession only license supersedes and terminates in their entirety changes to the license issued in License Amendments: No. 17, July 27, 1979; No. 56, August 4, 1987; No. 61, May 18, 1988; No. 63, August 18, 1988; No. 66, August 7, 1991; and No. 69, April 11, 1997.
C. This amended license is effective 30 days from the date of issuance and shall expire at midnight, March 29, 2031.
FOR THE NUCLEAR REGULATORY COMMISSION Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Project Management Office of Nuclear Reactor Regulation
Attachment:
Appendix A - Technical Specifications Date of Issuance: April 11, 1997 Amendment No. 72