ML20056D671

Amend 153 to License DPR-40,increasing Max Bypass Pressure for SG low-pressure Signal Trip Setting from 550 Psia to 600 Psia

ML20056D671
Person / Time
Site:	Fort Calhoun
Issue date:	07/26/1993
From:	Rood H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20056D668	List: ML20056D667 ML20056D671 ML20056D680
References
NUDOCS 9308170306
Download: ML20056D671 (8)

Text

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/ t UNITED STATES y-(%f) fj NUCLEAR REGULATORY COMMISSION  :

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,e WASHINGTON, D.C. 20555-0001

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OMAHA FUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 153 License No. DPR-40 ,

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

A. The application for amendment by the Omaha Public Power District (the licensee) dated May 21, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission'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 '

Commission; 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 (11) 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-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.

i 9308170306 930726 PDR ADOCK 05000285 P PDR

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.153 , 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 ,

Harry Rood, Acting Director Froject Directorate IV-I ,

Division of Reactor Projects - III/IV/V Office of Nuclear. Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 26,1993 j

~

e e ATTACHMENT TO LICENSE AMENDMENT NO.153 FACILITY OPERATING LICENSE NO. DPR-40 j 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 1-10a 1-10a 2-64a 2-64a

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2-67 2-67 2-69 2-69 3-12 3-12

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1 I

I TABLE 1-1 (Continued) l RPS LIMITING SAFETY SYSTEM SE11[NGS A Setpoint cannot be set greater than 10% above measured power whenever reactor power is greater than 10% of rated power.

B May be bypassed below 10d% power.

C May be bypassed below 600 psia.

D Bypass allowed for containment leak test.

E Inhibited below 15% power.

F For physics testing at power levels less than 10-'% of rated power the low reactor coolant flow and thermal margin / low pressure trips may be bypassed until their reset points are exceeded if automatic bypass removal of 10'% of rated power is operable.

f f

1-10a Amendment No. 5,22,153

.=

TABLE 2-1 (Continued)

ENGINEERED SAFETY FEATURES SYSTEM INITIATION INSTRUMENT SE'ITING LIMITS Functional Unit Channel Settine Limit

6. (Continued) b. (Continued) ii) Bus l A4 Side 13724.08 volts (4.8 i .5) seconds J}W P

7. Iow Steam Generator Water Level Auxiliary Feedwater Actuation 128.2% of wide range tap span

8. High Steam Generator Delta Pressure Auxiliary Feedwater Actuation .s_119.7 psid (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 .5; 2995.2 - 20.8 volts only. (For voltage A (2995.2 - 20.8) volts, time delay shall le

> 5.9 seconds.)

2-54a Amendment No. 4g153

TABLE 2-2 Imtnrment Ooeratine Reouirements for Reactor Protatire System Test, Maintenance Minimum Minimum Permissible and Operable Degree of Bypass Inoperabic h Functional Unit Channels Redundancy Condition Bioass 1 Manual (Trip Buttons) 1 None None N/A 2 High Power level 2** 1") Thermal Power (e)(f)

Input Bypassed below 10d% of Rated Power **

3 Thermal Margin / low 2*) 1 Below 10d% of (e)(f)

Pressurizer Pressure Rated Power"*

4 High Pressurizer 2*' 1 None (e)

Pressure 5 Low R.C. Flow 2 *) 1 Below 10d% of (c)

Rated Power **

6 low Steam Generator 2/ Steam 1/ Steam None (e)

Water Level Gen *' Gen 7 Low Steam Generator 2/ Steam 1/ Steam Below 600 (e) l Pressure Gen *' Gen psia"*

B Containment High 2*' 1 During leak Test (e)

Pressure ,

9 Axial Power 2** 1") Below 15% of (e)(f)

Distribution Rated Power

• 10 High Rate Trip-wide 2*) 1 Below 10d% and (e)

Range Img Channels above 15% of Rated Power *'*

11 loss of Load 2*' 1 Belove 15 % of (e)

Rated Power

• 12 Steam Generator 2*' 1 None (e) '

Differential Pressure

a. Bypass automatically removed.

b. If minimum operable channel conditions are reached, one inoperable channel must be placed in the tripped condition within one hour fro:r. the time of discovery of loss of operability. He remaining ,

channel may be bypassed for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and, if an inoperable channel is not returned to operable status within this time frame, a unit shutdown must be initiated. (See Specification (2) and exception associated with the high rate trip-wide range log channel.)

2-67 Amendment No. 50,'?,ES,153

TABLE 2-4 INSTRUMENT OPERATING CONDITIONS FOR ISOLATION RINCTIONS Test, Maintenance Minimum Minimum Permissible and l Operable Degree of Bypass Inoperable -

& Egnetional Unit Channels Redundanet Condition Bypass s

1 Containment isolation A Manual 1 None None N/A B Containment High  ;

Pressure A 2** 1 During Leak (0 B 2*

• I Test ,

C Preuurizer  :

low / Low A 2** 1 Reactor Coolant (0 I B 2* *' 1 Pressure Less Than 1700 psia *>

2 Steam Generator isolation A Manual 1 None None N/A B Steam Generator Isolation 1 None None N/A (i) Steam Generator low Pressure A 2/ Steam 1/ Steam Steam Generator (O Gen *) Gen Pressure less Than ,

600 psia")  !

B 2/ Steam 1/ Steam Gen *) Gen (ii) Containment High Pressure A 2*

• 1 During Leak (0 ,

B 2** 1 Test P

3 Ventilation Isolation A Manual 1 None None N/A B Containment High Radiation A 2") None If Contamment (0 B 2") None Relief and Purge Valves Are Closed a A and B circuits each have 4 channels.

b Auto removal of bypass prior to exceeding 1700 psia.

c Auto removal of bypass prior to exceeding 600 psia.

249 Amendment No. Se,93,!ce,142,153

i TABLE 3-2 (Continued) l MINIMUM FREOUENCIES FOR CIIE.CKS. CALIBRATIONS AND TESTING OF.

ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS 1

i Surveillance Channel Description Function Frecuency Surveillance Method

18. SIRW Tank Temperature a. Check D a. Compare two independent temperature Indication & Alarms readings.

b. Test M b. Measure temperature of SIRW tank with standard laboratory instru-ments.

19. Recirculation Actuation a. Test R a. Manual initiation.

Switches

20. Recirculation Actuation a. Test M a. Part of test 3(a) using built-in testing logic systems to initiate STLS.

b. Test R b. Complete automatic test initiated sensor operation.

21. 4.16 KV Emergency Bus a. Check S a. Verify voltage readings are above Low Voltage (less of alarm initiation on degraded voltage Voltage and Degraded level - supervisory lights "on".

Voltage)

b. Test M b. Undervoltage relay operation simu-lated one circuit at a time,

c. Calibrate R c. Known voltage applied to sensors and circuit breaker trip actuation logic verified.

Notes: (1) Not required unless pressurizer pressure is above 1700 psia.

(2) Not required unless steam generator pressure is above 600 psia. l 3-12 Amendment No. 4bl53

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