ML20126M111

Proposed TS Table 2.2-1 Re Reactor Trip Sys Instrumentation Trip Setpoints & Table 3.2-1 Re DNB Parameters

ML20126M111
Person / Time
Site:	Wolf Creek
Issue date:	01/05/1993
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20126M098	List: ML20126M093 ML20126M107 ML20126M111
References
NUDOCS 9301080204
Download: ML20126M111 (9)

Text

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i APPENDIX A Technical Specification Markups A-1 9301080204 930105 I PDR ADOCK 05000482 P PDR

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8 OEFINITIONS QUADRANT POWER TILT RATIO 1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output is greater. to the With average of the lower one excore excore detector ino detector calibrated outputs, whichever shall be used for computing the average. perable, the remaining three detectors RATED THERMAL POWER 1.25 reactorRATED coolant of THERMAL 4+1+ HWt. POWER shall be a total core heat transfer rate to the 3565 REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval fro when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SHUTOOWN MARGIN 1.28 SHUTOOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is suberitical or would be suberitical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully inserted worth which is assumed except fortothe single be fully rod cluster assembly of highest reactivity withdrawn.

SITE BOUNDARY ~

1.29 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

SLAVE RELAY TEST 1.30 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay.

The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

WOLF CREEK - UNIT 1 1-5 Amendment No. 42

t TABLE 2.2-1 8

5 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS O

m

^

SENSOR TOTAL ERROR

' FUNCTIONAL UNIT ALLOWANCE (TA) Z (5) TRIP SETPOINT ALLOWABLE VALUE

1. Manual Reactor Trip H.A. N.A. N.A. N.A. N.A.

~ 2. Power Range, Neutron Flux

a. liigh Setpoint 7. 5 4.56 0 $109% of RTP* 1112.3% of RTP*

b. Low Setpoint 8.3 4.56 0 $25% of RTP* 128.3% of RTP*

3. Power Range, Heutron Flux, 2.4 0.5 0 <4% of RTP* with <6.3% of RTP* with liioh Positive Rate i time constant i time constant 12 seconds 22 seconds

4. Power Range, Neutron Flux, 2.4 0.5 0 <4% of RTP* with <6.3% of RTP* with m liigh Negative Rate -

i time constant i time constant A 12 seconds 12 seconds

5. Intermediate Range, 17.0 8.41 0 125% of RTP* $35.3% of RTP" Neutron Flux

6. Source Range, Neutron Flux 17.0 10.01- 0 $105 cps $1.6 x 105 cps V6/ 2.57

7. Overtemperature AT X" 360 k?f See Note 1 See Note 2 l g 2.if o.tr

[ 8. Overpower AT JMJ .1-frJ A-1f See Note 3 See Note 4

[

9. Pressurizer Pressure-Low 3.7 0.71 2.49 11915 psig 11906 psig a

10. Pressurizer Pressure-High 7. 5 0.71 2.49 $2385 psig 12400 psig

[

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( 11. Pressurizer Water Level-liigh 8.0 2.18 1.96 $92% of instrument span 193.9% of instrument span E *RTP = RATED TilERHAL POWER sy ** Loop design flow = 93,750 gpm

TABLE 2.2-1 (Continued)

G; TABLE NOTATIONS (Continued) o E NOIE 1: (Continued)

? S8/.2 *f a

T' <

jifwS*f (Nominal T,yg at RATED THERMAL POWER);

= 0.000671;

$ K3 P = Pressurizer pressure, psig; P' = 2235 psig (Nominal RCS operating pressure);

5 = Laplace transform operator, s 1; and ft(AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP t,ests such that:

y (i) for qt qb between -27% and + H , f (AI) = 0, where qt and qb are Percent t

• 55 RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb total THERMAL POWER-in percent of RATED THERMAL POWER; (ii) for each percent that the magnitude of qt qb exceeds -2 M , the AT Trip Setpoint shall be automatically reduced by 1.5 M of its value at RATED THERMAL POWER; and (iii) for each percent that the magnitude of qt qb exceeds +M , the AT Trip 5,etpoint a shall be automatically reduced by 0.85% of its value at RATED THERMAL POWER.

5 NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than I

g JA% of AT span.

. .24%

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I g TABLE 2.2-1-(Continued)

TABLE NOTATIONS (Continued)

O g; NOTE 3: (Continued) n a

Ka = 0.00128/*F for T > T" and'Ka = 0 for T $ T";

g:

q T = Average temperature, *F; I" =

, Indicated T,yg at RATED THEllMAL POWER-(Calibration temperature for AT-instrumentation, 5 jiBikS*F); :

5s/.a v

.5 = Laplace transform operator, s 1; and f 2(AI) = 10.for all AI.

NOTE 4: The channel's maximum Trip Setpoint shall not' exceed its computed Trip Setpoint by more than-

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A of'AT span.

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w TABLE 3:2-1

'ONB PARAMETERS LIMITS Four_ Loops in.

P A R A'tETER Ooeration Indicated Reactor Coolant System T < 5JUHi'F IgfC 7" gg ,

nci:atec Pressuri:er Pressure > 2220 psig" 4

" Limit not applicable during either a THERMAL POWER ramp in excess of 5%.of.

RATED THERMAL POWER per minute or a THERMAL POWER step in excess of .10% of -

RATED THERMAL POWER.

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1 WOLF CREEK - UNIT 1 3/4 2-15 l-4

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-F0WER-DISTRIBUTION LIMITS BASES QUADRANT POWER TILT RATIO (Continued)

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, tha moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, N-8.

3/4.2.5 DNB PARAMETERS The lit;'. on the ONB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to. ,

maintain a DNBR above the safety analysis limit DNBR (1.32) throughout each analyzed transient. The indicated T,yg val n of g and the-indicated pressurizer pressure value of 2220 psig correspond to analytical limits of

.595*F -and 2205 psig respectively, with allowance for measurement uncertainty.

Sri 7 Y The 12-hour periodic surveillance of these parameters through instrument-readout is sufficient to ensure that the parameters are restored within their J limits following load changes and other expected transient operation.

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WOLF CREEK - UNIT 1 B 3/4 2-6 Amendment No. 51 i

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r APPENDIX B

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Operating License Markup 1

'B-1 8l

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l (1) Pursuant to Section 103 of the Act-and 10 CFR Part 50 " Domestic Licensing of Prnduction and Utilization Facilities," the Operating Corporation, to possess, use and operate the facility at the designated location in Coffey County, Kansas, in accordance with the procedures and limitations set forth in this license; (2) KG&E, KCPL aid KEPC0 to possess the facility at the designated location in Coffey County, Kansas, in accordance with the procedures and limitations set forth in this license; (3) The Operating Corporation, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the liniitations for storage and amounts required for reactor operation, as described in the Final Safety Analycis Report, as supplemented and amended.

(4) The Operating Corporation, pursuant to the Ac' and 10 CFR Parts 30, 40 and 70, to receive, possess, and use a. any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) The Operating Corporation, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form,.for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) The Operating Corporation, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C, This ifcense shall be deemed.to contair; and is subject to the conditions-specified in the Commission's regulations set forth in'10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereaf ter in effect; and is subject to the additional conditions-specified or incorporated below:

(1) Maximum Power Level q3565 The Operating Corporation is authorized to operatje the facility at reactor core power levels not in excess of[54F1-megavatts thermal (100% power) in accordance with the conditions specified herein and in Attachment I to.this license. The activities identified in Attachment 1 to this license shall be completed ~

as specified. Attachment 1 is hereby incnrporated into this' license. j Amendment No. 53

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