ML20246L819

Amend 96 to License DPR-6,revising OL to Allow for Increase in Amount of Byproduct Matl Plant May Possess & Use from 10.5 to 45 Ci Cs-137,as Sealed Sources

ML20246L819
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/02/1989
From:	Yandell L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246L816	List: ML20246L812 ML20246L819 ML20246L825
References
NUDOCS 8905180410
Download: ML20246L819 (4)

Text

. _ . . _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4p atouq v o UNITED STATES

8. , g

. n NUCLEAR REGULATORY COMMISSION

$  :: $ WASHINGTON, D. C. 20555 k ..... / '

CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET NO. 50-155 AMENDMENT TO FACILIY OPERATING LICENSE Amendment No. 96 License No. DPR-6

1. The Nuclear Regulatory Comission (th.e Comission) has found that:

A. The application for amendment by Consumers Power Company (the licensee) dated December 19, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. Thereisreasonableassurance(i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

8905180410 890502 5 PDR ADOCK 0500 P

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-6 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 96 ,,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION W C Lawrence A. Yandell, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V

& Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: May 2, 1989

ATTACHMENT TO LICENSE AMENDMENT N0. 96 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET N0. 50-155 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

• REMOVE INSERT 3 3 L

g *[)r (3) Pursuant to the Act and 10 CFR Part 30, " Rules of General

1. N Applicability to Domestic Licensing of By-product Material," to receive, possess and use at any one time up to 7000 curies of antimony-beryllium in the form of neutron sources, 3.7 curies of cobalt-60 as sealed ggt /gf sources, 45 curies of cesium-137 as sealed sources,10 microcuries of miscellaneous alpha emitting material as sealed sources, and up to 500 millicuries per nuclide of any by-product material between atomic numbers I and 83, inclusive, without restrictions as to chemical and physical form; .

(4) Pursuant to the Act and 10 CFR Part 40, " Licensing of Source Material,"

to receive, possess and use at any one time up to 500 kilograms of depleted uranium dioxide contained in the facility's fuel assemblies; (5) Pursuant to the Act and 10 CFR Parts 30 and 70', to possess,'but not separate, such by-product and special nuclear materials as may be produced by the operation of the facility.

C. 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 authorized to operate the facility at steady state reactor core power levels not in excess of 240 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 93 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Exemption from 10 CFR 650.46, Appendix K, Paragraph I.D.1 g

Pursuent to 10 CFR 550.12 the licensee is granted an exemption from g /6 the ECCS tailure criterion of 10 CFR 650.46, Appendix K, Paragraph I.D.1 as applied to a Loss-of-Coolant Accident followed by I concurrent single failure in the redundant core spray system for the /o//7/7 1978 operating fuel cycle.

_ _ _ _ - _ _ _ - _ _ - - - _ __