ML20063H200

Proposed Tech Specs Revising Power Rerate Parameters

ML20063H200
Person / Time
Site:	Wolf Creek
Issue date:	02/07/1994
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20063H193	List: ML20063H190 ML20063H200
References
NUDOCS 9402170156
Download: ML20063H200 (6)

Text

I l Attachment IV to MA 94-0018

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! ATTACHMENT IV '

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l PROPOSED TECHNICAL SPECIFICATION CHANGE l

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. 9402170156 940207 i PDR ADOCK 050004B2 P PDR g; l

Attachment IV to NA 94-0018 Page 2 of 6 TABLE 2 2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS SENSOR TOTAL Z ERROR EUNCTIONAL UNIT A_LLOWANCE (TA) .1S) TRIP SETPOINT ALLOWABLE VALUE

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

2. Power Range, Neutron Flux

a. High Setpoint 7.5 4.56 0 $109% of RTP* 5112.3% of RTP*

b. Low Setpoint 8.3 4.56 0 525% of RTP* 528.3% of RTP*

3. Power Range, Neutron Flux, 2.4 0.5 0 54% of RTP* with 6.3% of RTP* with High Positive Rate a time constant a time constant 22 seconds 22 seconds

4. Power Range, Neutron Flux, 2.4 0.5 0 54% of RTP* with 56.3% of RTP* with High Negative Rate a time constant a time constant 22 seconds 22 seconds

5. Intermediate Range, 17.0 8.41 0 525% of RTP* $35.3% of RTP*

Neutron Flux

6. Source Range, Neutron Flux 17.0 10.01 0 5105cps $1.6 x 106 cps

.,-m - -

7.0 4.86 1.67 l 7. Overtemperature AT -P -+6+- 2.57 See Note 1 See Note 2 4.6 2.02 0.14 l 8. Overpower AT -te- -e45- -e See Note 3 See Note 4

9. Pressurizer Pressure-Low 3.7 0.71 -2.49 21915 psig 21906 psig

10. Pressurizer Pressure-High 7.5 0.71 2.49 52385 psig 52400 psig

11. Pressurizer Water Level-High 8.0 2.18 1.96 592% ofinstrument 593.9% of instrument span span

• RTP = RATED THERMAL POWER

• '1_oop design flow - 93,600 gpm

n . - . . . .. .~ -- - - . .. . .

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Attachment IV to NA 94-0018 Page 3 of 6 TABLE 2.2-1 (Continued)

TABLE NOTATIONS (Continued)

NOTE 1: (Continued 586.5 l T' Nominal Tavg at RATED THERMAL POWER);

K3 = 0.000671; P = Pressurizer pressure, psig; P' = 2235 psig (Nominal RCS operating pressure);

S = Laplace transform operator, s-1; and fj(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 - uch that:

5 (i) for qt - Ab between -25% an +%, j(AI) = 0, where qt and qb are percent RATED THERMAL POVER in the top and bottom halves of the core respectively, and qt + Abi s total THERMAL POWER in percent of RATED THERMAL POWER; (ii) for each percent that the magnitude of qt - Ub exceeds -25%, the AT Trip Setpoint shall be automatically reduced by 1.8% of its value at R D THERMAL POWER; and 5

(iii) for each percent that the magnitu '

- qb exceed #2%, he AT Trip Setpoint shall be automatically reduced b  % fits value a TED THERMAL POWER.

1.56 NOTE 2: anners maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than l -25% f AT span.

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_.-.__mm___..__.._._m_ _ _ _ _ _ . . - - - _ _ _ _ _ _ _ _ _ . _ + _ - . _ _ _ _ _ ___ _ __ _ _ _ _ _ _ _ _

Attachment IV to NA 94-0018 Page 4 of 6 TABLE 2.2-1 (Continued)

TABLE NOTATIONS (Continued)

NOTE 3: (Continued)

K6 = 0.00128FF for T > T" and K6 = 0 for T 5 T";

T = Average temperature,"F; T" = Indicated Tavg at HERMAL POWER (Calibration temperature for AT l instrumentation 54&+@F);

586.5 S = Laplace transform opera r, s' ; and f2(AI) = 0 for all 41 NOTE he channers maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than l -eW/c of AT span.

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Attachment IV to NA 94-0018 Page 5 of 6 TABLE 3.2-1 1

DNB PARAMETERS l I

I LIMlIS Four Loops in PARAMETER Operation l l 1. Indicated Reactor Coolant System Tavg 56864*F 590.5  ;'

2. Indicated Pressurizer Pressure 2 psig*

3. Reactor Coolant System Flow Rate 238.4 x 104 GPM l

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• 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.

WOLF CREEK - UNIT 1 3/4 2-16 Amendment No. 64,69

l Attachment IV to NA 94-0018 j Page 6 of 6 I

l POWER DISTRIBUTION LIMITS BASES

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I OUADRANT POWER TILT RATIO (Continued)

The 2-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and -

correction of a dropped or misaligned control rod. In the event such ACTION does not correct the tilt, the margin for uncertainty on Fo(X,Y,Z) is reinstated by reducing the maximum allowed power by 3% for each percent of tilt in excess of 1.

For purposes of monitoring OUADRANT POWER TILT RATIO when one excore l

detector is inoperable, the movable 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 limits on the Reactor Coolant System T and the pressurizer pressure assure that each of the parameters are mai,ntained within the normal steady-state envelope of operation assumed in the transient and accident i analyses. The limits are consistent with the initial USAR assumptions and I

have been analytically demonstrated adequate to maintain a DNBR above the safety analysis limit DNBR specified in the CORE OPERATING LIMITS REPORT R) throughout each analyzed transient. The indicatedyT value of

-666'F nd the indicated pressurizer pressure value of 2220 psig correspond 590. ( ,

! l to analyticallimits o(6Bf 7 2205 psig respectively, with allowance for l measurement uncertair, y. 593.0 l

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

Fuel rod bowing reduces the value of DNB ratio. Credit is available to offset this reduction in the generic margin. The generic margins completely offset any rod bow penalties. This is the margin between the correlation DNBR limit and the safety analysis limit DNBR. These limits are specified in the COLR.

The applicable values of rod bow penalties are referenced in the USAR.

When RCS flow rate and F3gg,Y), per Specification 3.2.3, are measured, no additional allowances are necessary prior to comparison with the limits in the COLR. Measurement uncertainties of 2.5% for RCS total flow rate and 4%

for F,g(X,Y) have been allowed for in determination of the design DNBR value.

WOLF CREEK - UNIT 1 B 3/4 2-3 Amendment No. 54, St 69 l

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