ML19327B794

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Amend 123 to License DPR-40,revising Tech Spec 3.1,Table 3-3 to Correct Administrative Error Made When Amend 32 to Tech Specs Issued
ML19327B794
Person / Time
Site: Fort Calhoun 
Issue date: 11/06/1989
From: Hebdon F
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19327B793 List:
References
NUDOCS 8911130348
Download: ML19327B794 (4)


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UNITED STATES -

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NUCLEAR REGULATORY COMMISSION

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,0MAHA PUBLIC POWER DISTRICT' DOCKET __N,0,50-285 E

FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FAClj.I,T,Y,,0,P, ERA, TING LIC_ENSE Amendment No.123 License No. DPR-40 t

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

A.

The application for amendment by the Omaha Public Power District (the licensee) dated September 8, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Corrission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applicatiun, as amended, the provisions of the Act, and the rules and regulations i

of the Cornission; C.

There is reascnable assurance:

(i)thattheactivitiesauthorized 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 license amendment will not be inimical to the corron d;fense 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.

8911130348 891106 PDR ADOCK 05000285 P

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Accordingly, Facility Operating License No. DPR-40 is amendeo by changes to the Technical Specifications as indicated in the attachnent to this license amendment, and paragrcph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B.

Technical Sp,ecifications

.The Technical Specifications contained in Appendix A, as revised through Aniendment No.123 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendnient is effective as of its date of issu:nce.

FOR THE NUCLEAR. REGULATORY COMfilSSION

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, b, Freder L J. Hebdon, Directer Project Directorate I\\

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Divisico of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuarce: 123 i

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1, i0 ATT AC HM,E,N,T,,T,0, J.1,C E N S,E,,A,M,E,N,DF,E N,T, p,0,,12,3_

s FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix'"A" Technical Specifications as indicated below. The revised page.is identified by amendment number and contains a vertical line indicating the area of change.

i Remove Page Insert Page

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3-15 3-15

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IllHIMUH FREQUf t:CIES FOR Cl!ECKS, CALIE,I% TICKS AND TESTING 2?

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Surveillance Chann_e,1, Description,_,,

Func, tion,,

Frequency Surveillance Method __

8.

Dropped CEA Indicatice a.

Test-R c.

Insert a negative rate of m

change power signal to all w

four Power Range Safety Channels to test alarm.

b.

Test P

b.

Insert CEA's below lower electrical limit to test dropped CEA alera.

9.

Calorimetric Instrumen-a.

r librate R

a.

Apply known d/p to feed-a w

tation water flow sensors.

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10. Control Room Ventilation a.

Test l'

a.

Check damper operation for i

DBA rode.

b.

Test R

b.

Check control room for posi-tive pressure.

11. Containment Humidity a.

Test R

a.

Place sensor in a known high humidity Detector atmosphere.

4 12.

Interlocks-Isolation Valves a.

Test R

a.

Known pressure of 265 psia applied-on Shutdown Cooling Line to pressure transmitter and pressure switch and operability i

of redundant interlock verified.

13. Control Room Thermometer a.

Test R

a.

Compare reading with cali-

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brated thermometer.

If not within 2'F, replace.

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