ML18052B029

Proposed Tech Specs Revising Requirements for Receipt,Use & Possession of Byproduct,Source & SNM

ML18052B029
Person / Time
Site:	Palisades
Issue date:	05/26/1987
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18052B027	List: ML18052B026 ML18052B028 ML18052B029
References
NUDOCS 8706020128
Download: ML18052B029 (3)

Text

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ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED LICENSE CHANGES May 26, 1987 2 Pages Proposed OC0387-0001A-NL02-NL04

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555 CONSUMERS POWER COMPANY (Palisades Plant)

DOCKET NO 50-255 PROVISIONAL OPERATING LICENSE License No DPR-20 Provisional Operating License No DPR~20, issued to the licensee for operation of the facility, on September 1, 1972, is hereby amended its* entirety to read as follow:s:

1. Provisional Operating License No DPR-20 applies to the Palisades Plant, a pressurized, light water moderated and cooled reactor, and electric generating equipment (the facility). The facility is located in Covert Township on the Consumers Power site in Van Buren County, Michigan, and is described in the "Final Safety Analysis Report," as supplemented and amended.

2. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Consumers Power Company (the licensee):

A. Pursuant to Section 104b of the Atomic Energy Act of 1954, as amended (the Act), and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess, use, and operate the facility as a utilization facility at the designated location; B. Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nu.clear material as reactor fuel, in accordance wi.th the limitations for storage and amounts required for operation, as described in the Final Safety Analysis Report, as supplemented and amended; C. Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required by any byproduct, source or special nuciear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; Proposed OC0387-0001A-NL02-NL04

.e 2 E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, suc_h byprodu_ct ~nd special nuclear materials as may be produced by the operation of the facility.

3. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50 and Section 70.32 of 10 CFR 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 below:

A. Maximum Power Levels The licensee is authorized. to operate the facility at steady state reactor core power levels not in excess of 2530 megawatts thermal (100% of the rated power level of the facility).

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 102 are hereby incorporated in the license. The licensee shall 'operate the facility in accordance with the Technical Specifications.

C. Reports The licensee sh~ll make certain reports in accordance with the requirements of the Technical Specifications and the Interim Special Technical Specifications.

D. Records The licensee shall keep facility operating records in accordance.

with the requirements of the Technical Specifications.

E. The licensee may proceed with and is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.23 of the NRC's Fire Protection Safety Evaluation (SE) on the facility dated September 1, 1978, Supplement No 1 to the SE dated March 19, 1980, and Supplement No 2 to the SE dated February 10, 1981. These modifications shall be completed as specified in Table 3.1 of the SE, as supplemented, in accord~nce with the schedule contained therein.

Proposed OC0387-0001A-NL02~NL04