ML20086A056

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Proposed Tech Spec Table 2.2-1 Re Loop Design Flow & TS 3.2.5.c Re RCS Flow
ML20086A056
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 11/12/1991
From:
GEORGIA POWER CO.
To:
Shared Package
ML20086A055 List:
References
NUDOCS 9111180215
Download: ML20086A056 (7)
v • d • e


Text

- _ _.

F0VER DISTRIBUTION LIMITS

(

3/4.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The /ollowing DNB elated parameters shall be maintained within the t

limits:

5, 592.5'F (UNIT 1) or 591'f (TI 0412 TI-0422, ?!-0432, TI-Reactor Coolant System T,y a.

(UNIT 2) b.

Pressurizer Pressure (PI 0455A,B&C, PI-0456 & PI-0456A, PI-0457 &

PI-0457A, PI 0458 & PI-0458A), ~> 2199 psig' (UNIT 1) or 2224 psig" (UNIT 2) c.

Reactor Coolant System Flow (FI-0414, F1-0415, FI-0416, FI-0424, FI-0434 f!-0435 CI-0436

'596,19Egpm*444,F1-0445, F1-0425}>FI-0426393156 gpm**(UNITli FI-0

  • (UNIT 2)

FI-0446 7

APPLICABILITY:

MODEN ACTION:

With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% 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 />.

SURVEILLANCE REQUIREMENTS 4.2.5.1 Reactor C olant System T,y and Pressurizer Pressure shall be veri-fied to be tithin their li its at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

RCS flow rate shall be monitored for degradation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Je the event of flow degradation, RCS flow rate shall be determined by p ecision heat balance within 7 days of detection of flow degradation.

4.2.5.2 TheRCSflowrateindicatorsshallbesubjectedtoCHANNEL CALIBRATION at each fuel loading and at least once per 18 months.

the RCS flow rate shall be determined by After each fuel loading,ithin 7 days af ter exceeding 90% RATED THERMAL I

4.2.5.3 precision heat balance w l0WER (UNIT 1) or prior to operation above 75% RATED THERMAL POWER (UNIT 2).

The RCS flow rate ' hall also be determined by precision heat balance at least once per 18 months. Within 7 days prior to

,b performing the precision heat balance flow measurement, the instru-9 mentation used for performing the precision heat balance shall be N"28 C

calibrated.

The provisions of 4.0.4 are not applicable for perform-58 ing the precision heat balance flow measurement.

@0 Cd

  • 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 TI RATED THERMAL POWER.

"" Includes a 2.7% (UNIT 1) or 3.5% (UNIT 2) flow measurement uncertainty.

l V0GTLE UNITS - 1 & 2 3/4 2-13 Amendment No. 43 (Unit 1 Amendment No. 23 (Unit 2

^

~

r n

m THIS PAGE APPLICABLE TO UNIT 1 CNLY l

q TABLE 2.2-1 (Continued)

O REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS - UNIT 1 l

A C

TOTAL SENSOR h

ALLOWANCE ERROR FUNCTIONAL UNIT (TA)

Z (5)

TRIP SETPOINT All0WABLE VALUE h

9.

Pressurizer Pressure-Low 3.1 0.71 1.67

->1950 psig**

~>1950 psig (PI-0455*.B&C, PI-0456 &

e.

PI-045ba, PI-0457 & PI-0457A, m

PI-0458 & PI-0458A) 10.

Pressurizer Pressure-High 3.1 0.71 1.67

<2385 psig

<2395 psig (PI-0455A,8&C, PI-0456 &

PI-0456A, PI-0457 & PI-0457A, PI-0458 & PI-0458A) 11.

Pressurizer Water level-High 8.0 2.18 1.67

<92% of instrument

<93.9% of instrument (LI-0459A,LI-0460A,LI-0461) span ipan 12.

Reactor Coolant Flow-Low 2.5 1.87 0.60

>90% of loop

>89.4% of loop y

(LOOP 1 LOOP 2 LOOP 3 LOOP 4 -

Besign flow

  • design flow
  • o' F1-0414 FI-0424 FI-0434 FI-0444 FI-0415 F1-0425 FI-0435 FI-0445 FI-0416 FI-0426 FI-0436 FI-0446) 13.

Stea Generator Water Level Low-18.5 17.18 1.67

>18.5% (37.8)***

>17.8% (35.9)***

Low (21.8)***

(18.21)***

Bf narrow range 5f narrow range (LOOP 1 LOOP 2 LOOP 3 LOOP 4 instrument span instrument span

((

LI-0517 LI-0527 LI-0537 LI-0547

=o LI-0518 LI-0528 LI-0538 LI-0548

((

LI-0519 LI-0529 LI-0539 LI-0549 gg LI-0551 LI-0552 LI-0553 LI-0554) zz

14. Undervoltage - Reactor Coolant 6.0 0.58 0

>9600 volts

>9481 volts

??

Pumps

{70% bus voltage)

I69% bus voltage)

NO

15. Underfrequency - Reactor Coolant 3.3 0.50 0

>57.3 Hz

>57.1 Hz Pumps

?] froc

_cc hh

" Loop design flow = SS,700 gpa

    • Time constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 10 seconds for lead and 1 secona.for lag.

CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values.

y,_,

      • The value stated inside the parentheds is for instrument that has the lower tap at elevation 333"; the value stated outside the parenthesis -s for instrumentation that has the Tower tap at elevation 438".

THIS PAGE APPLICABLE TO UNIT 1 ONLY

]

POWER DISTRIBUTION L1 HITS - UNIT 1 BASES 3/4.2.5 DNB PARAMETERS (Continued)

The measurement uncertainty for the RCS total flow is based upon perform-ing a precision heat balance flow measurement above 90% RATED THERMAL POWER and using the results to correlate the flow indication channels with the measured flow.

If a precision heat balance flow measurement is performed below 90%

' '}

RATED THERMAL POWER, the effect on the measurement uncertainty shall be taken into account.

Potential fouling of the feedwater venturis which might not be detected could bias the results from the precision heat balance in a non-conservative manner.

Therefore, a penalty of 0.1% for undetected feedwater venturi fouling is included in the measurement uncertainty.

Any fouling which t aht bias the RCS flow rate measurement greater than 0.1% may be detected by m-litoring and trending various plant performance parameters.

If detected,

a.,'on shall be taken before performing subsequent precision heat balance flow m a.urements, i.e., either the effect of the fouling shall be quantified and accounted for in the RCS flow rate measurement or the affected venturis shall be cleaned to eliminate the foulin.

The indicated RCS flow va'ue of

[ 393713fr gpm corresponds to an anal tical value of 000,000-gpm > th allowance for measurement and indication uncertainties.

y7py khb2-hourper'iodicsurveillanceoftheseparametersthroughinstrument I

readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

The 18 month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with measured flow such that the irdicated percent flow will provide sufficient verification of the flow rate degradation on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.

A change in indicated percent flow which is greater than the instrument channel inaccura-cies and parallax errors is an appropriata indication of RCS flow degradation.

)

)

)

Amendment No. 43 Unit 1)

Amendment No. 23 ((Unit 2)

V0GTLE UNITS - 1 & 2 B 3/4 2-6

,s e

Change pages that become effective after the impicmentation of Amendments 44 and 24.

l i

l POWER DISTRIBUTION LlHITS 3/4.2.5 DNB PARAMETERS

[lMITINGCONDIT10IFOROPERATION 3.2.5 The following DNB-related parameters shall be maintained within the limits:

a.

Reactor Coolant System Tgg (T1-0412 TI-0422, TI-0432 TI-0442),

5 592.5'F b.

Pressurizer Pressure (PI-0455A,B&C, PI-0456 & PI-0456A, PI-0457 &

PI-0457A, PI-0458 & PI-045BA), 3 2199 psig*

I c.

Reactor Coolant System flow '71-0414. F1-0415, FI-0416, F1-0424, F1 0425, F1-0426, F1-0434, il 0435, F1-0436, F1-0444, F1-0445, 1

I F1-0446) 1 4937136'gpm**

JV H00E 1. s WY APPLICABillTY:

ACTION:

With any of the above 96rameters exceeding its limit, restore the pararneter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% 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 />.

SURVEILLANCE REQUIREMENTS 4.2.5.1 Reactor Coolant System T,yg and Pressurizer Pressure shall be verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

RCS flow rate shall be monitored for degradation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

In the event of flow degradation, RCS flow rate shall be determined by precision heat balance within 7 days of detection of flow degradation.

4.2.5.2 TheRCSflowrateindicatorsshallbesubjectedtoCHANNEL CAllBRATION at each fuel loading and at least once per 18 months.

4.2.5.3 After each fuel loading, the RCS flow rate shall be determined by precision heat balance within 7 days af ter exceeding 90% RATED THERMAL POWER.

The RCS flow rate shall also be determined by precision heat balance at least once per 18 months. Within 7 days prior to performing the precision heat balance flow measurement, the instru-mentation used for performing the precision heat balance shall be calibrated.

The provisions of 4.0.4 are not applicable for perform-ing the precision heat balance flow measurement.

  • 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.
    • Inciudes a 2.7% flow measurement uncertainty.

I V0GTLE UNITS - 1 & 2 3/4 2-13 Amendment No. 44 (Unit 1)

Amendment No. 24 (Unit 2)

.J 1

TABLE 2.2-1 (Continued)

~ ~

p g

REACTOR TRIP SYSTEM INSTRt#ENTATION TRIP SETPOINTS e

c>

y

[

N-TOTAL SENSOR ALLOWANCE ERROR 5

FUNCTIONAL UNIT (TA)

Z_

(S)

TRIP SETPOINT ALLOWABLE VALUE i.

U 9.

Pressurizer Pressure-Low 3.1 0.71 1.67

>1960 psig**

->1950 psig j.

(PI-0455A,8&C,.PI-0456 &

w PI-0456A, PI-0457 & PI-0457A, e-PI-0458 & PI-0458A) m'

}

10.

Pressurizer Pressure-High 3.1 0.71 1.67 12385 psig

$2395 psig

?

(PI-0455A,8&C, PI-0456 &

I PI-0456A, PI-0457 & PI-0457A, 1

PI-0458 & PI-0458A) 2 11.

Pressurizer Water Level-High 8.0 2.18 1.67

<92% of instrument

<93.9% of instrtment t

(LI-0459A, LI-0460A, LI-0461) span span j

12.

Reactor Coolant Flow-Low 2.5 1.87 0.60

>90% of loop

>89.4% of loop (LOOP 1 LOOP 2 LOOP 3 LOOP 4 Besign riow*

Besign flow

  • FI-0414 FI-0424 FI-0434 FI-0444 FI-0415 FI-0425 FI-0435 FI-0445' l-FI-0416 FI-9426 FI-0436 FI-0446)
13. Steam Generator Water Level Low.

18.5 17.18 1.67

>18.5% (37.8)***

>17.8% (35.9)***

1 Low

.(21.8)***

(18.21)***

Ef narrow range if narrow range (LOOP 1 LOOP 2 LOOP 3 LOOP 4 LI-0517. LI-C-527 - LI-0537 LI-0547 instrument span instrument span

!((

LI-0518 LI-0528 LI-0538 LI-0548 LI-0519.LI-0529 LI-0539 LI-0549 2

o=

LI-0551 LI-0552 LI-0553' LI-0554) kk

14. Undervoltage - Reactor Coolant 6.0 0.58 0

>9600 volts

>9481 volts

%5 Pumps T70% bus voltage)

I69% bus voltage) fy

15. Underfrequency - Reactor Coolar,t 3.3 0.50 0

>57.3 Hz

>57.1 Hz

[

Pumps

!TR T& (oo

" Loop des'I n flow = 95, 2 gpa

!nm 9

LEE

    • Time constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 10 seconds for lead and

{33 1 second for lag. CHANNEL CALIBRATION shall. ensure that these time constants are adjusted to these values.

iw-

      • The value stated inside the parenthesis is for.instrum-nt that has the lower tap at elevation 333"; the j*

value stated outside the parenthesis is for instrumentation that has the lower tap at elevation 438".

i b

l' i

l P0k'ER D!$TRIBUT10N LIMITS BASES 3/4.2.5 chb PARAhETER( (Continued)

I The measurenent uncertainty for the RCS total flow is basec upon perform-ing a precision heat balance flow n.tasurement abovt 90% RA1ED THERMAL PCLER and using the rebults tc correlate the ficw indication channels with the measurto flow.

If a precision heat talance fluw measurement is performed below 90%

RA1ED ThERKAL POWER, the effect on the measurcrent uncertainty shall be taken Potential fouling of the feedwater venturis which might not te into acccunt.

detected coulo bias the results from the precision heat balance in a r.cn-Theref ore, a penalty cf 0.1% for undetected feedwater conservet;ve manner.

venturi fouling is included in the measurement uncertainty. Any fouling which might bias the RCS flow rtte measurement greater than 0.1% may be detected by If detecteo, monitoring and trending varicus plant performance parameters.

acticn shall be taken before performing subsequent precision heat balance flow measuremerets, i.e., either the effect of the fouling shall be quantified and acccunted for in the RCS flow rate measurement or tbt affected venturis shall The indicated RCS flow value of-493,136-be cleaned to elimintte the fouling.

gpm corresponds to an analytical value of 202,200 gpm with allowance for yyy,rO 9 measurement and indication untertainties. 3/q} 9foo The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure.that the perrmeters are restored within their The limits fc11owing load changes and other expected transient operation.

18 month periodic measurement of the RCS total flow rete is acequate to detect flow degracaticr end ensure correlation of the flow indication channels with neasured ficw such that the indicated percent flow will provide sufficient verification of the flow rate degracation on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis. A change in indicateo percent flow which is greater than the instrument channel inaccuracies and parallax errors is an appropriate indication of RCS flow cegradation.

V0GTLE UNITS - 1 & 2 8 3/4 2-5 Amendment No. 44 (Unit 1)

Amendment No. 24 sunit2)

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