ML20078C330

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Amends 200 & 177 to Licenses DPR-53 & DPR-69,respectively, Revise Various UFSAR Sections to Address Removal of Orifice Plate in Containment Vent/Purge Line to Allow Greater Flow Through Line
ML20078C330
Person / Time
Site: Calvert Cliffs  
Issue date: 10/21/1994
From: Marsh L
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20078C332 List:
References
NUDOCS 9410310175
Download: ML20078C330 (4)


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BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AME4DMENT TO FACILITY OPERATING LICENSE Amendment No. 200 License No. OPR-53 l

1.

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

A.

The application for amendment by Baltimore Gas and Electrir Company (the licensee) dated November 4, 1993, complies with the standards and i

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 E.

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

2.

Accordingly, by Amendment No. 200, the license is amended to authorize revision of the Updated Final Safety Analysis Report (UFSAR) as set forth in the application for amendment by the licensee dated November 4,1993.

The licensee shall update the UFSAR to reflect the removal of the orifice plate in the containment. vent / hydrogen purge system and revise the maximum hypothetical accident analysis to address the increased flow as the result of the removal of the orifice plate, as authorized by this amendment, in accordance with 10 CFR 50.71(e).

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3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Marsh, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance: 0ctober 21, 1994

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NUCLEAR REGULATORY COMMISSION If WASHINGTON, D.C. 20555 4 001 I

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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.177 License No. DPR-69 l

1.

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

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated November 4, 1993, 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-1 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 E.

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

2.

Accordingly, by Amendment No. 177, the license is amended to authorize revision of the Updated Final Safety Analysis Report (UFSAR) as set forth in the application for amendment by the licensee dated November 4, 1993.

The licensee shall update the UFSAR to reflect the removal of the orifice plate in the containment vent / hydrogen purge system and revise the maximum hypothetical accident analysis to address the increased flow as the result of the removal of the orifice plate, as authorized by this amendment, in accordance with 10 CFR 50.71(e).

. 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION M

Ledyard B. Marsh, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:

October 21, 1994 1

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