ML20215J358

Proposed Tech Specs,Allowing Storage of Fuel in Either Unit Fuel Pool

ML20215J358
Person / Time
Site:	LaSalle
Issue date:	06/16/1987
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20215J347	List: ML20215J345 ML20215J358
References
NUDOCS 8706240409
Download: ML20215J358 (5)

Text

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ATTACHMENT B T17HNICAL SPECIFICATION CHANGE-REOUEST- ' i, ,

LASALLE COUNTY ST)\ TION UNIT 1 j NPP-11 j 1

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REVISED SECTION:- 2.B.5 .page.3 of license

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2/11/87 License No. NPF-11 (4) Commonwealth Edison Company, 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 calibration or associated with radioactive apparatus or components; and (5) Commonwealth Edison Company, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation oft-aSalk the f::111ty.

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C. This license shall be deemed to contain and is subject to the I conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 reactor core power levels not in excess of full power (3323 megawatts thermal). -

l (2) The Technical Specifications contained in Appendix A, as i revised through Amendment No. 49, and the Environmental l49 l protection Plan contained in Appendix B, are hereby  !

incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Conduct of Work Activities Durinc Fuel Load and Initial Startup The licensee shall review by committee all Unit 1 Preopera-tional Testing and System Demonstration activities performed concurrently with Unit 1 initial fuel loading or with the Unit a 1 Startup Test Program to assure that the activity will not l

.' affect the safe performance of the Unit 1 fuel loading or the  !

portion of the Unit 1 Startup Program being performed. The review shall address, as a minimum, system interaction, span of control, staffing, security and health physics, with respect to q q

performance of the activity concurrently with the Unit 1 fuel a loading or the portion of the Unit 1 Startup Program being performed. The committee for the review shall be composed of at least three members, knowledgeable in the above areas, and who meet the qualifications for professional- technical personnel specified by section 4.4 of ANSI N18.7-1971. At

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least one of these three shall be a senior member of the Assistant Superintendent of operation's staff. l J

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4 ATTACHMENT C TECHNICAL SPECIFICATION CHANGE REOUEST LASALLE COUNTY STATION UNIT 2 NPP-18 REVISED SECTION: 2.B.5 page 3 of license I

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2/09/87 i

License No. NPF-18 (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to

• receive, possess, and use in amounts as required any i byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis  !

or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of th: f;;ility.

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c. The license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in i 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and others 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 reactor core power levels not in excess of full power (3323 megawatts thermal). Items in Attachment i shall be completed as specified. Attachment 1 is hereby incorporated into this

. license.

(2) Technical Specifications and Environmantal Protection Plag The Technical Specifications contained in Appendix A, as revised through Amendment No. 30 and the Environmental 30 Protection plan contained in Appendix B, are hereby incorporated into the license. The licensee shall operate the f acility in accordance with the Technical Specifications and

- the Environmental Protection Plan. -

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(3) Conduct of Work Activities Durino Puel Load and Initial Startup The licensee shall review by committee all Unit 2 Preopera- l tional Testing and system Demonstration actvities performed .

concurrently with Unit 2 initial fuel loading or with the Unit 2 Startup Test Program to assure that the activity will not affect the safe performance of the Unit 2 fuel loading l l

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c ATTACHMENT D SIGNIFICANT HAZARDS CONSIDERATION 1

Commonwealth Edison has evaluated the proposed Technical Specification l amendments and determined that they do not represent a significant hazards consideration. Based on the criterla for defining a significant hazards consideration established in 10 CPR 50.92, operation of LaSalle county l Station-Units 1 and 2 in accordance with the proposed amendments will not: l l

1) Involve a significant increase in the probability or consequences of an accident previously evaluated because the configuration and operation of the plant will remain essentially the same. The .

designs of the two fuel pools and the associated operating and j accident analysis assumptions are not changed by these amendments.

Puel assemblies discharged from the Units 1 and 2 reactors have essentially the same mechanical design, enrichments, and burnup j histories. Fuel assemblies being used at LaSalle County Station {

are analyzed for storage in both fuel pools prior to their j '

placement in the fuel pools.

2) create the possibility of a new or different kind of accident from any accident previously evaluated because this change does not modify the configuration or operation of the plant. Transfer of fuel assemblies from one fuel pool to the other is performed with the fuel handling platform utilizing the main fuel grapple or the auxiliary fuel hoist, and does not require defeating any fuel  ;

handling interlocks. Transfer of fuel assemblies from a fuel pool to the transfer canal and the cask well vault is discussed in the Updated PSAR, Subsection 9.1.2. potential fuel handling accidents are also evaluated in the Updated FSAR, Section 15.T(

consequently, the handling and transport of the spent fuel are enveloped by previous analyses.

3) Involve a significant reduction in the margin of safety because Keff will be maintained below 0.95 and the Updated FSAR accident analyses results bound the evolutions that would be necessary in transferring spent fuel from one fuel pool to the other.

Guidance has been provided in 51 FR 7744 (example x) for the application of standards to license change requests for determination of the existence of significant hazards considerations. Based on that guidance and the preceding discussion, it is concluded that the proposed Technical Specification amendments clearly will not alter the performance of any plant {

systems as previously evaluated in the Updated FSAR, will not modify any  !

plant systems that might lead to a new or different type of accident not previously evaluated and the margin of safety will not be reduced.

Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(e), the proposed change does not constitute a significant hazards consideration.

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