ML20210E875

Amend 84 to License DPR-61,formalizing Requirement to Perform Quadrant Power Tilt Surveillance at Least Once Per 7 Days to Satisfy NRC Request Made During Review of Cycle 14 Reload Application

ML20210E875
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/18/1986
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210E830	List: ML20210E827 ML20210E875 ML20210E896
References
NUDOCS 8609250110
Download: ML20210E875 (4)

Text

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. UNITED STATES 8' g NUCLEAR REGULATORY COMMISSION s l WASHINGTON, D. C. 20555

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-61

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

A. The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated June 6, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 Connission; 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, hofagKo 86091s p 05000213 PDR

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-61 is hereby amended to read as follows:

(2) Technical Specifications -

The technical specifications contained in Appendix A, as revised through Amendment No. 84, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the technical specifications.

3. This license amendnent is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Claat p Christopher I. Grimes, Director I. @

Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Attachment:

Changes to the Technical Specif.ications Date of Issuance: September 18, 1986 l

ATTACHMENT TO LICENSE AMENDMENT N0. 84 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET N0. 50-213 Replace the following page of the Appendix A technical specifications with the enclosed pages as indicated. The revised page is identified by the captioned amendment number and contains a vertical line indicating the area of change.

REMOVE INSERT 2-5 2-5

.,, - - , = - - . . , -

. 2.4 Maximum Safety Settings - Protective Instrumentation Applicability: Applies to trip set tings for instruments monitoring reactor power and reactor coolant pressure, temperature, and flow.

Objective: To provide for protective action in the event that the principle process variables approach a safety limit.

{ Specification: Protective instrumentation trip settings shall be as follows:

Four Reactor Coolant Three Reactor Coolant Pumps Operating Pumps Operating (1) Pressurizer Pressure 4 2300 psig a 2300 psig (2) Pressurizer Level

• A 86% of range d 86% of range (3) Variable Low Pressure * * * & 17.4 (Tavg+1.17AT)-8850 2 J 7.4(Tavg+1.17 T)-8850 (4) Nuclear Overpower * * $ 109% of rated power 174% of rated power (5) Low Coolant Flow * *

• 2 90% of normal loop flow 290% of normal loop flow (6) Reactor Coolant Loop Valve-Temperature 3 200F A 200F Interlock (7) High Steam Flow 110% of full load steam 110% of full load steam flow flow

• May be bypassed when the reactor is at least 1.5%Ak subcritical.

The nuclear overpower trip is based upon a symmetrical core power distribution. If any asymmetric power distribution should occur, resulting in the power in any quadrant being 2% greater than the average core power j as indicated by the neutron detectors, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either I

a) reduce the QUADRANT POWER TILT RATIO to within its limit, or l

b) reduce thermal power at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1.0 and similarly reduce the Nuclear Overpower trip setpoint within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

I Above 50% of RATED THERMAL POWER, the QUADRANT POWER TILT RATIO l shall be determined to be within the limit by calculating the ratio at least once per 7 days.

When the reactor power is 410% the overpower trip setpoint is reduced to 25% of rated power.

• • • May be bypassed below 10% of rated power.

(

Basis: The reactor protective system is designed and constructed such that no single failure in any of the instrument systems will prevent the desired safety action if an applicable parameter exceeds a safety set point.

2-5 Amendment No. 29, 74, 84

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