ML20134Q050

Amend 65 to License DPR-61,revising Tech Specs by Deleting Logic Requirement of Pressurizer Low Water Level for Safety Injection Trip

ML20134Q050
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/03/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20134Q033	List: ML20134Q029 ML20134Q050 ML20134Q064
References
NUDOCS 8509090145
Download: ML20134Q050 (4)

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CM'i'ECTICUT YANKEE ATOMIC POWER COMPANY FADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendmen't No.65 License No. DPR-61

1. The Nuclear Regulatory Commission (the Comission) has found that:

A. The application for amendment by Connecticut Yankee Atomic Power Company (the licensee) dated October 20, 1981, 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 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 Comission'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.

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2. Accordingly, the license is amerded by changes to the Technical Specifica!. ions as indicated in the attachment to this license amendment and Paragraph P.C.(2) of Facility Operating License No. DPP.-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 65, are hereby incorporated in the license. The licensee shall crerate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORK COWISSICE l

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s John . Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

. Changes to the Technical Specifications Date of Issuance: September 3,1985

V ATTACHMENT TO~ LICENSE AMENDPEFT NO. q FACILITY OPERATING LICENSE NO. DPR-61 DOCVET FO. 50-713 Peplace the following page of the Apperdix A Technical Specifications with the enclosed page as indicated. The revised pace is identified by the captioned anendnent nunber and conteins e vertical line indicating the area of change.

REMOVE INSERT 3-15a 3-15a l

TABLE 3.9-1 -

MINIMUM INSTRUMENTATION OPERATING CONDITIONS Column I Column 11 At Power Requirements Logic Required For Required Operating Action If Full Power Operation Column I Logic Cannot Be Met 1 Nuclear Overpower Reactor Trip 2/3

2. Pressurizer Variable Low Pressure Reactor Trip Maintain Shutdown Conditions

3. 1/2 Pressurizer Fixed High Pressure Reactor Trip 1/2 Maintain Load Below 10% Full Power (F.P.)

4. Pressurizer liigh Water Level Reactor Trip Maintain Shutdown Conditions

5. 1/2 Maintain Load Below 10% F.P.

Low Coolant Flow Reactor Trip - 4 Loop Operation 1/4

- 3 Loop Operation Maintain Load Below 84% F.P.

6 1/3 Maintain Load Below 10% F.P.

Pressurizer Low Pressure Signal (For Safety Injection Trip) 1/2

7. Deleted Maintain Shutdown Conditions

8. Manual Trip .

y 1/1 Maintain Hot Shutdown Conditions

9. Steam-Feedwater Flow Mismatch Coincident g with Low Steam Generator Level-Reactor Trip Continuous Operator Surveillance of

= 1/4 Steam and Feedwater Flow Recorder  ;

and Steam Generator Water Level of 4

10. High' Steam Flow Isolation Valve Trip - 4 Loop Operation Affected Steam Generator (

2/4 Isolate Corresponding Loop

- 3 Loop Operation 2/3

11. Containment High Pressure Signal (For Safety Maintain Shutdown with 1/2 Injection Trip) 2/3 Maintain Shutdown Conditions Startup Requirement f

p Intermediate Range SUR Reactor Trip 1/1 g Source Range SUR Rod Stop Maintain Shutdown Conditions  ;'

1/1 Maintain Shutdown Conditions Refueling Requirement Shutdown High Neutron Level Alarm l/l No Changes in Core Geometry Permitted

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