ML20073F963

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Amends 197 & 174 to Licenses DPR-53 & DPR-69,respectively, Re Changes to TS to Extend Interval for Three AFW SRs from 18 to 24 Months
ML20073F963
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 09/26/1994
From: Michael Case
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20073F970 List:
References
NUDOCS 9410030327
Download: ML20073F963 (7)


Text

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NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D C. 20666-0001

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BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.197 License No. DPR-53 1.

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

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 8, 1994, 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 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, 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:

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9410030327 940926 PDR ADOCK 05000317 P

PDR i

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Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 197, 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 and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Michael J. Case, Acting 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:

September 26, 1994

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UNITED STATES i '

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NUCLEAR REGULATORY COMMISSION i

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BALTIMORE GAS AND ELECTRIC COMPANY i

DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.174 License No. DPR-69 1.

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

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 8, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 t

Comission; C.

There is reasonable assurance (1) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and i

E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,

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and paragraph 2.C.2. of Facility Operating License No. DPR-69 is hereby amended to read as follows:

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2.

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174, 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 and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION i

Michael J. Case, Acting Director Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 26, 1994 i

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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 197 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 174 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Revise Appendix A as follows:

Remove Paaes Insert Paaes 3/4 7-7 3/4 7-7

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3/4.7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Before entering M0DE 3 after a COLD SHUTDOWN of at least 14 days by completing a flow test that verifies the flow path from the condensate storage tank to the steam generators.

c.

At least once per REFUELING INTERVAL by:

l 1.

Verifying that each automatic valve in the flow path actuates to its correct position (verification of flow-modulating characteristics not required) and each auxiliary feedwater pump automatically starts upon receipt of each AFAS test signal, and 2.

Verifying that the Auxiliary Feedwater System is capable of providing a minimum of 300 gpm nominal flow to each flow leg.

i This surveillance may be perfomed on one flow leg at a time.

CALVERT CLIFFS - UNIT 1 3/4 7-7 Amendment No. 197

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3/4.7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Before entering M0DE 3 after a COLD SHUTDOWN of at least 14 days by completing a flow test that verifies the flow path from the condensate storage tank to the steam generators.

c.

At least once per REFUELING INTERVAL by:

l 1.

Verifying that each automatic valve in the flow path actuates to its correct position (verification of flow-modulating characteristics not required) and each auxiliary feedwater pump automatically starts upon receipt of each AFAS test signal, and 2.

Verifying that the Auxiliary Feedwater System is capable of proyiding a minimum of 300 gpm nominal flow to each flow leg.

t This surveillance may be performed on one flow leg at a time.

CALVERT CLIFFS - UNIT 2 3/4 7-7 Amendment No. 174