ML20205K971

Proposed Tech Specs Re Transfer of Byproduct Matl from Other Util Job Sites for Decontamination & Vol Reduction

ML20205K971
Person / Time
Site:	Prairie Island
Issue date:	10/24/1988
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20205K964	List: ML20205K959 ML20205K966 ML20205K971
References
NUDOCS 8811010426
Download: ML20205K971 (3)

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EXHIBIT B License Amendment Request Dated October 24, 1988

' Docket No. 50-282 50 306-License No.' DPR-42 DPR 60 '

Exhibit B consists of marked up pages from the Prairie Island Technical Specifications showing the proposed changes listed below:

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Page 3 - Unit 1 Operating License Page 3 - Unit 2 Operating License i

88110104P6 881024 PDR ADOCK 05000282 P PNU 1

3 (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear aterials as may be produced by the operation of the fac.ilit j C. Tnis amended 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, Sections 50.54 and 50.59 c," Part 50, and Section 70.32 of Part 70; 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 license is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawats thermal.

(2) Technien1 Specifications The Technical Specifications contained in Appendix A, as revised through amendment No. 83, are hereby incorperated in the license. The licenseo shall operate the facilicy in accordance with tl.e Technict.1 Spacfficatiens.

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i UNIT 1 LICENSE

(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any by product, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such by-product and special nuclea materials as j may be produced by t'se operation of the facility  ; l l

1 C. This amended license shall be deemed to contain and is subject to  ;

l the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 license is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawats thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 76, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) i'hysical Protee dp_q The license aball fully implement and maintain in effect all provisions of the follog Commission approved documents, incl. ding amendmente and changes made pursuant to the aucherity of 10 CPR 50.54(p). These approve.d documents consist of information witheid from public disclosure pursuant to 10 CFR 2.790(d):

a. ' Prairie Island Nuclear Generating Plant Security Plan" --

Devision 4 filed on March 3, 1978 and Revision 5 filed hptember 25, 1978. _

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UNIT 2 LICENSE