ML20198S637

Amend 94 to License DPR-3,changing Tech Specs by Adding Containment Isolation Valves for Containment Breathing Air Sys

ML20198S637
Person / Time
Site:	Yankee Rowe
Issue date:	05/28/1986
From:	Clifford J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20198S627	List: ML20198S621 ML20198S637 ML20198S656
References
NUDOCS 8606100502
Download: ML20198S637 (6)

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YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO.50-029 YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-3

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

A. The application for amendment by Yankee Atomic Electric Company (the licensee) dated Sept' ember 30, 1985 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 Comission; 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 Comission's regulations and all applicable requirements have been satisfied.

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F606100502 PDR 860528 P

ADOCK 05000029 PDR

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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-3 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.94 , 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.

FOR THE NUCLEAR REGULATORY COMMISSION bli.:eacb$ 0-James W. Clifford, Project Manager Project Directorate #1 Division of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of Issuance: May 28, 1986

ATTACHMENT TO LICENSE AMENDMENT N0. 94 FACILITY OPERATING LICENSE N0. DPR-3 DOCKET N0.50-029 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 2-6 2-6 B 2-5 B 2-5 3/4 3-14 3/4 3-14

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R i si gj TABLE 2.2-1 (continued) i REACTOR PROTECTIVE SYSTEN INSTRUMENTATION TRIP SETPOINTS

FUNCTIONAL UNIT TRIP SETPOINT t

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8. High Main Coolant System Pressure 1 2300 psig

9. Low Main Coolant System Pressure 1 1800 psig

10. High Pressurizer Water Level 1 200 inches 1

11. Low Steam Generator Water Level 1 - 13"*

12. Turbine Trip Not Applicable i

13. Generator Trip Not Applicable

! 14. Main Steam Isolation Trip Logic 1 262.5 psig j >

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g *Where 0 inches corresponds to 10" above the feed ring conterline.

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LIMITING SAFETY SYSTEM SETTINGS BASES  ;

Steam Generator Water Level The Low Steam Generator Water Level trip provides core protection by I preventing operation with the steam generator watee level below the minimum  !

volume required for adequate heat removal capacity. Th'e specified setpoint '

provides allowance that there will be sufficient water inventory in the steam ,

generators at the time of trip to provide 15 minutes, as assumed in the '

accident analysis, for starting delays of the emergency feedwater system.

Turbine and Generator Trip A Turbine or Generator Trip causes a direct reactor trip when operating above 15 MWe, Eachoftheturbinetripsprovideturbineprotectionandreducel the severity of the ensuing transient. No credit was taken in the accident analyses for operation of these trips. Their functional capability is required to enhance the overall reliability of the Reactor Protection System.

Main Steam Isolation Trio A Main Steam Isolation Trip closes the main steam line noneeturn valves and causes a direct reactor trip. This trip reduces the severity of the l cooldown and the ensuing transient effects resulting from a main steam line break. This trip also serves to assure the availability of a secondary system heat sink following a seismic event, until the Safe Shutdown System is available to provide feedwater to the steam generators. Its functional capability enhances the overall reliability of the Reactor Protection System.

Main Coolant System High Pressure The Main Coolant System High Pressure Trip is provided to ensure protection against main coolant system overpressurization caused by a loss of load incident. Its functional capability enhances the overall reliability of the Reactor Protection System.

YANKEE-ROWE B 2-5 Amendment No. 69 94 r __________. _ _ _ _____ _ _

, TABLE 3.3-3 ENCINEERED SAFEGUARDS SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL-UNIT TRIP SETPOINT

1. SAFETY INJECTION

a. Actuation Channel # 1

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1) RPS Low Main Coolant -

• Loop 1 Pressure Channel a 165ti psig

2) High Containment Pressure Sensor s 5 psig

3) Manual Initiation Not Applicable

b. Actuation Channel # 2

1) RPS Low Main Coolant -

Loop 2 Pressure Channel 11650 psig

2) High Containment Pressure Sensor 1 5 psig

3) Manual Initiation Not Applicable

2. CONTAINMENT ISOLATION

a. Manual Initiation Not Applicable

b. Actuation Channel A

1) High Containment Pressure ,

Sensor 1 5 psig

2) Safety Injection (All Safety Injection Setpoints)

c. Actuation Channel B

! 1) High Containment Pressure Sensor 1 5 psig

2) Safety Injection (All Safety Injection Setpoints)

3. MAIN STEAM ISOLATION

a. Low Steam Line Pressure 1 262.5 psig

b. Automatic Trip Logic Not Applicable

c. Manual Initiation Not Applicable

d. High Cpntainment Pressure l Trip - Containment Isolation 1 5 psig YANKEE-ROWE 3/4 3-14 Amendment No. % [ f ( [ 94

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