ML20100H132

Amend 211 to License DPR-53,allowing Use of Cladding Matl Other than Zircaloy or ZIRLO

ML20100H132
Person / Time
Site:	Calvert Cliffs
Issue date:	02/21/1996
From:	Marsh L NRC (Affiliation Not Assigned)
To:
Shared Package
ML20100H136	List: ML20100H132 ML20100H142
References
NUDOCS 9602270126
Download: ML20100H132 (4)

Text

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k UNITED STATES s

g NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, C.C. 20056 4001

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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 211 License No. DPR-53 1.

The Nuclear Regulatory Commission (the Commission) has found that:

l A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated December 21, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission'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 Commission; C.

There is reasonable assurance (i) that the activities authorized 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 Commission'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 4

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements i

have been satisfied.

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-53 is hereby amended to read as follows:

9602270126 960221 DR ADOCK OMO 7

. 2.

Technical Specification 1 The Technical Specifications. contained in Appendices A and B, as revised through Amendment No. 211, 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 to be 4

implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Marsh, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 21, 1996 1

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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 211 FACILITY OPERATING LICENSE NO. DPR-53 t

DOCKET NO. 50-317 4

j Revise Appendix A as follows:

Remove Paaes Insert Paaes t

j 5-1 5-1 4

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5.0 DESIGN FEATURES i

5.1 SITE LOCATION The site for the Calvert Cliffs Nuclear Power Plant is located on the western shore of the Chesapeake Bay in Calvert County, Maryland, about 10-1/2 miles southeast of Prince Frederick, Maryland. The site is approximately 45 miles southwest of Washington, DC, and 60 miles south of Baltimore, Maryland. The exclusion area boundary has a minimum radius of 1,150 meters from the center of the plant.

l 5.2 REACTOR CORE 5.2.1 FUEL ASSDSLIES The reactor shall contain 217 fuel assemblies.

Each assembly shall consist of a matrix of cylindrical zircaloy or ZlRLO cladding fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0,)

i as fuel material.

Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used.

Fuel assemblies shall be limited j

to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies i

j that have not completed representative testing may be placed in nonlimiting l

regions.

For Cycles 13,14 and 15 only, advanced cladding material may be used in four lead test assemblin as described in an approved temporary exemption dated November 28, 1995.

5.2.2 CONTROL ELEMENT ASSEMBLIES a

The reactor core shall contain 77 full length and no part length control element assemblies.

5.3 FUEL STORAGE i

5.3.1 CRITICALITY a

i 5.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 4.52 weight j

percent; b.

k,,, < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7.2 of the UFSAR; c.

A nominal 10-3/32-inch center-to-center distance between fuel assemblies.

I CALVERT CLIFFS - UNIT 1 5-1 Amendment No. 211

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