ML20235G039

Proposed Tech Specs Allowing Unit Operation Above 50% Power W/Rcs Flow Between 90% & 100% of Total Required Flow

ML20235G039
Person / Time
Site:	Catawba
Issue date:	07/01/1987
From:	DUKE POWER CO.
To:
Shared Package
ML20235F982	List: ML20235F979 ML20235G039
References
NUDOCS 8707140082
Download: ML20235G039 (4)

Text

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e POWER DISTRIBUTION LIMITS 3/4.2.3 REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System total flow rate and R shall be maintained within the region of allowable operation shown on Figure 3.2-3 for four loop operation.

l Where:

N

$H K = 1.49 [1.0 + 0.3 (1.0 - P)]

a.

f THERMAL POWER and

'b*

P = RATED THERMAL POWER I

btained by using the movable incore c.

F H = Measured values of F H detectors to obtain a power distribution map.

The measured values of F shall be used to calculate R since Figure 3.2-3 g

includes penalties for undetected feedwater venturi fouling of 0.1% and for measurement uncertainties of 2.1% for flow and 4%

f for incere measurement of F a..

g.

. APPLICABILITY:

MODE 1.

i I

ACTION:

b With the combination of Reactor Coolant System total flow rate and R outside the region of acceptable operation shown on Figure 3.2-3:

1)(.

Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:

a) K Restore the combination of Reactor Coolant System total flow rate and R to within the above limits, or b)%

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2.M.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially being outside the above limits, verify through incore flux mapping and Reactor Coolant System total flow rate comparison that the combination of R and Reactor Coolant System total flow rate are restored to within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

8707140082 870701 PDR ADOCK 05000413 P

PDR CATAWBA - UNITS 1 & 2 3/4 2-9

p l

a.

With the combination of Ibactor Coolant System total flow rate and R within the region of acceptable operation with the flow rate less i

than 396100 gpm, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> reduce the Power Range Neutron Flux-High Trip Setpoint to below the ncminal setpoint by the same amount (% RTP) as the power reduction required by Figure 3.2-3.

i POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) 3M.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2. and/or b., above; subsequent POWER OPERA-TION may proceed provided that the combination of R and indicated Reactor Coolant System total flow rate are demonstrated, through incore flux mapping and Reactor Coolant System total flow rate comparison, to be within the region of acceptable operation shown on Figure 3.2-3 prior to exceeding the following THERMAL POWER levels:

qY%.

A nominal 50% of RATED THERMAL POWER,

@ k' A nominal 75% of RATED THERMAL POWER, and l

hX Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 95%

I of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

e 4.2.3.2 The combination of indicated Reactor Coolant System total flow rate determined by process computer readings or digital voltmeter measurement and R shall be determined to be within the region of acceptable operation of Figure I

3.2-3:

Prior to operation above 75% of RATED THERMAL POWER after each fuel a.

loading, and b.

At least once per 31 Effective Full Power Days.

4.2.3.3 The indicated Reactor Coolant System total flow rate shall be verified 1

to be within the region of acceptable operation of Figure 3.2-3 at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the most recently obtained value of R, obtained per Specifica-tion 4.2.3.2, is assumed to exist.

4.2.3.4 The Reactor Coolant System total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.

The measurement instrumentation shall be calibrated within 7 days prior to the performance of the calorimetric flow measurement.

l 4.2.3.5 The Reactor Coolant System total flow rate shall be determined by precision heat balance measurement at least once per 18 months.

1

\\

i CATAWBA - UNITS 1 & 2 3/4 2-10 j

PENALTIES OF 0.1'S FOR UNDETECTED FEEDWATER VENTURI l,,

FOULING ARD MEASUREMENT UNCERTAINTIES OF 2.1% FOR j

I FLOW AMD 4.0% FOR INCORE MEASUREMENT OF F[g ARE

{

INCLUDED IN THIS FIGURE.

I I

i 8_

ACCEPTABLE UNACCEPTABLE IIIIiiiI IIII IiiitIiiiil l.

l l 1 i iiiiiiIil i 6 iiiiiii6I i l

OPERATION OPERATION lIliI lii1 iII Iit i IiIiiIII i iiiiiiiiili liiI 4iii6i i I 4 0. 0 __

REGION REGION 5

c.

O (1.000,39.610) g p

,j O

39.5

[12 ACCEPTABLE FOR I

W l I I i t tili!!I I

H 6 i i i iiiiii6 i I

POWER 98% RTP r

g l l l l l l l!l 1

i i i t i IIIII It if (0.994,39.214)

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ACCEPTABLE FOR iIl t I i iiI I IIII I

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O

(([ POWER 1 9'6% RTP H

39*0 "

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(0.988,38.8W

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Z

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POWER 1 94% RTP I

38.5 =

l l 1) ii!lII

/

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(0.982,38.422)

I o

__Jilililit 1 46 _,

I ACCEPTABLE FOR g

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M

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POWER 1 92% RTP I

i U

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ACCEPTAPLE FOR I

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POWER $ 90% RTP I,

IIIIililIl 1l It i

i i ii i l IIII II

-Ii (0.971,37.630) i 37.51-l, i.

6 i

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l 1

0.95 0.96 0.97 0.98 0.99 1.00 1.01 1.02 R=F$gM M + GM FIGURE 3.2-3 REACTOR COOLANT SYSTEM TOTAL FLOW RATE VERSUS R - FOUR LOOPS IN OPERATION CATAWBA - UNITS 1 & 2 3/4 2-11