ML20059J244

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Amend 159 to License DPR-40,revises TS to Change Setpoint Limit for degraded-voltage Protection Sys Referred to as offsite-power Low Signal
ML20059J244
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 01/14/1994
From: Beckner W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059J216 List:
References
NUDOCS 9401310412
Download: ML20059J244 (5)


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1[A E UNITED STATES NUCLEAR REGULATORY COMMISSION

OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION. UNIT NO. 1  ;

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.159.

License No. DPR-40 -

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

A. The application for amendment by the Omaha Public Power District- i (the licensee) dated October 7, 1992, as supplemented July 12,.1993, complies with the standards and requirements of-the Atomic. Energy Act of 1954, as amended (the Act), and the Commission's rules and t 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; i C. There is reasonable assurance: (1) 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 'i conducted in compliance with the Commission's regulations; i D. The issuance of this license 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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9401310412 940114 PDR ADOCK 05000285 P PDR i

2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.159 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

[ V ' d <: w L) 6 , l. ,, .

William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: January 14, 1994 l

ATTACHMENT TO LICENSE AMENDMENT NO.159 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

REMOVE PAGES INSERT PAGES 2-64 2-64 2-64a 2-64a i

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1

TAHLE 21 ENGINEERED SAFETY FEATURES SYSTEM INITI A FION INSTRUMENT SETTING LIMITS Functional Unit Channel Settine Limit

1. liigh Containment Pressure a. Safety Injection $_5 psig
h. Containment Spray *
c. Containment Isolation
d. Containment Air Cooler DBA Mode
e. Steam Generator Isolation
2. Pressurizer Low / Low Pressure a. Safety injection A 1600 psia *
b. Containment Spray *
c. Containment Isolation
d. Containment Air Cooler DBA Mmle
3. Containment liigh Radition Containment Ventilation isolation in accordance with the applicable Chemistry Manual calibration procetture
4. Low Steam Generator Pressure a. Steam Line Isolation 1500 psia o b.' Auxiliary Feedwater Actuation 1466.7 psia
5. SIRW Low Level Switches Recirculation Actuation 16 inches +0, -2 in, above l . tank bottom
6. 4.16 KV Emergency Bus Low a. Loss of Voltage '1 (2995.2 +- 104) volts ,

L Voltage Trip 15.9*2" seconds j f b. Degraded Voltage 13988.8 volts }Tn,p l i) Bus I A3 Side (4.81 5) seconds J l

l 2 Amendment No. 4!,65,ar,m* !5',159 F

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TAllLE 2-1 (Continued)

ENGINEERED SAFETY FEATURES SYSTEM INITIATION INSTRUMENT SETTING LIMITS Functional Unit Channel Settine Limit

6. (Continued) b. (Continued) ii) Bus I A4 Side > 3990.6 volts 1

' Tn,p l (4.8 i .5) seconds j

7. Low Steam Generator Water Level Auxiliary Feedwater Actuation A 28.2% of wide range tap span i
8. liigh Steam Generator Delta Pressure Auxiliary Feedwater Actuation < I 19.7 psid

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(1) May be bypassed below 1700 psia and is automatically reinstated prior to exceeding 1700 psia.

(2) May be bypassed below 600 psia and is automatically reinstated prior to exceeding 600 psia.

(3) Simultaneous high containment pressure and pressurizer low / low pressure.

(4) Applicable for bus voltage < 2995.2 - 20.8 volts only. (For voltage >_ (2995.2 - 20.8) volts, time delay shall be

> 5.9 seconds.)

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2-64a Anwndment No. 11.65,"6,!53. 159 4

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