ML20031D172

Amend 5 to License NPF-9,correcting Setpoint Associated W/Reactor Trip Initiated by Turbine Trip

ML20031D172
Person / Time
Site:	McGuire
Issue date:	09/23/1981
From:	Adensam E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20031D173	List: ML20031D172 ML20031D175 ML20031D176 ML20031D177 ML20031D178
References
TAC-46812, NUDOCS 8110130025
Download: ML20031D172 (5)

Text

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DUXE POWER C0t'.PANY DOCKET 110. 50-369 fiCGUIRE fillCLEAR STATI0ll. UNIT 1 AMENDMENT TO FACILITY OPERATIhG LICENSt Arendment Ho. 5 License 110. HPF-9 1.

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

A.

The application for amendment to the McGuire Nuclear Station

• ...it 1

(the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated Septerter 21, 1981, complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.

The fecility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Core Mission; 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 coryliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license ar.endnent will not be inimical to the cormon defense and security or to the health and safety of the

• public; E.

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

rm o.

2.

Accordingly, the license is hereby anended by page changes to the Technical Specifications as indicated in the attachments to this license araendTnt and

-o C8 paragraph 2.C.(2) of Facility Operating License No. HPF-9 is hereby amended b

to read as follows:

oo OS (2) Technical Specifications Y

g The Technical Specifications contained in Appendix A, as revised through to o.a.

Arendment No. 5, are hereby incorporated into this license. The liccnsee shall operate the facility in accordance with the Technical Specifications and the iLnvironmental Protection P' an.

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This license amendment is ef fective as of its date of issuance.

FOR TiiE riUCLEAR REGULATORY CO.N311SSIOfl

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Elinor G. Adensan, Acting Chief Licensing Branch ho. 4 Division of Licensing

Attachment:

Technical Specification change Date of Issuance: September 23, 1981 b

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ATTAC10iEflT TO LICD!SE AMEt:f0DAT,,

FACILITY OPERATIl4G LICEllSE i 0. IIP. s DOCKET NO. 50_-3_59 Replace the following page of the Appendix "A" Technical Specificat!ons with the enclosed page. The revised page is identified by Amendment number and contains a vertical line iniic& ting the area of change. The corresponding overleaf page is also provided to r.aintain document completeness.

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l TABLE 2.2-1 n

E REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES E

1. Manual Reactor Trip Not Applicable Not Applicable i

s

2. Power Range, Neutron Flux Low Setpoint - < 25% of RATED Low-Setpoint - 1 26% of RATED THERMAL POWER -

THERMAL POWER i

High Setpoint - < 109% of RATED High Setpoint - 5110% of RATED THERMAL POWER THERMAL POWER I

3. Power Range, Neutron Flux,

< 5% of RATED THERMAL POWER with

< 5.5% of RATED THERMAL POWER i

High Positive Rate a time constant 1 2 seconds Gith a time constant 1 2 seconds

4. Power Range, Neutron Flux,

< 5% of RATED THERMAL POWER with

< 5.5% of RATED THERMAL POWER Migh Negative Rate a time constant 1 2 seconds With a time constant 1 2 seconds

5. Intermediate Range, Neutron

< 25% of RATED THERMAL PuWER

< 30% of RATED THERMAL POWER f3UX 5

5

6. Source Range, Neutron Flux 5 10 counts per second 5 1.3 x 10 counts per second

7. Overtemperature AT See Note 1 See Note 3

8. Overpower AT See Note 2 See Note 3

9. Pressurizer Pressure--Low 1 1945 psig 1 1935 psig

10. Piessurizer Pressure--High 1 2385 psig i 2395 psig 3

11. Pressurizer Water Level--High 5 92% of instrument span 5 93% of. instrument span 2?

12. Turbine Trip

_m A.

Low System Pressure Trip

> 45 psig

> 42 psig B.

Turbine Stop Valve

[1%open

[1%open Closure I

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2g TABLE 2.2-1 (Continued) 5 g

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS h

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

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13.

Loss of Flow

> 90% of cesign flow

> 89% of design flow per loop

• per loop *

14. Steam Generator Water

> 12% of span from 0 to 30%

> 11% of span from 0 to 30%

Level--Low-Low of RATED THERMAL POWER, of RATED THERMAL POWER, increasing linearly to > 54.9%

increasing linearly to of span at 100% of RATED 153.9% of span at 100% of THERMAL POWER.

RATED THERMAL POWER.

15. Undervoltage-Reactor 1 5082 volts-each bus 1 5016 volts-each bus Coolant Pumps

16. Underfrequency-Reactor 1 56.4 Hz - each bus 1 55.9 Hz each bus Coolant Pumps

17. Safety Injection Input Not Applicable Not Applicabla from ESF

-10

~II 18.

Intermediate Range Neutren 1 1 x 10 amps 1 6 x 10 amps Flux - (P-6) Enable Block Source Range Reactor Trip 19.

Power Range Neutron Flux

$ 10% of RATED THERMAL POWER 1 11% of RATED THERMAL POWER (not P-10) Input to Low Power Reactor Trips Block P-7 20.

Turbine Impulse Chamber

< 10% Turbine Impulse

< 11% Turbine Impulse E

Pressure - (P-13) Input to Fressure Equivalent Fressure Equivalent 1

2 Low Power Reactor Trips Block P-7 tr>

A Design flow is 97,500 gpm per loop.

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