ML17353A383

Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint

ML17353A383
Person / Time
Site:	Turkey Point
Issue date:	09/28/1995
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17353A382	List: L-95-250, Application for Amends to Licenses DPR-31 & DPR-41, Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A383
References
NUDOCS 9510020306
Download: ML17353A383 (22)

Text

675 24R PSIA 655 UNACCEPTABLE OPERATlQN 59<<

575 OA) 7 L1 03 OA LS 0.7 M

0.9 t.O 7

t.1 Om (reeO0N N0uWa.)

FIGURE 2. 1-1 REACTOR CORE SAFETY LIMIT-THREE LOOPS IH OPERATION TURKEY POINT - UNITS 3 8

4 9510020306 950928 PDR ADOCK 05000250 P

PDR 1

2-2 AMEHtjMENT HOS.>37AXD i3-

'J

~

g

~

670 rNsfgT A ~

660 650 455 PS 2400 PS UNACCEPTAB~

OPERATlON 640 630

~

620 CO 610 MPS 600 580 OPERATKN 0.1 02 0.3 0.4 0.6 0.6 07 08 0.9 1

1.1 1.2 POWER (FRACTION OF NOMINAL)

Figure 2.1-1 Reactor Core Safety Limit-Three Loops in Operatior

l.

Naval Reactor Trip 2.

Poser

Raaye, NeeCrea flex a.

Hips Setyoiak b.

Lm Setyelat 3.

lateeeediate

lhaye, Neotroa Flax 4.

Scwrce Raage, Neotroa Rm 6.

Overixaar hT 7.

Pressurizer tressare-bw 8.

frasserine'ressure-HSIb 9.

tressurizer %ter Lerel-Hiyk 10.

Reactor Ceelmt Fl~lm 11.

Stem Ceaerater ihter Level Lao-Lcm

~ Loop desiya flew ~ N,500 ge

~ NF Rated %leal hear I.A

+12.N of~

~AS of~

+1.0% of~

glA X lIP cps Seo Neto 2 Soe Note 4 plIP ysSI 524N psiy

~.N of fastest spaa gg pre

.7% of loop ga fl 8.'I'e2%

of aRFFNI raage Sastnmat spaa N.h.

F09% of~

~of~

~of~

ply cps See Note 1

See Note 3

>163S psii

+38S ysig

~ of )ast~at spa%~of l~

desiya SL ofa~

rassle iast~t spah

~

i

~

12.

StemIFaodeater Bee Nsaatch Coiacldeat Ntl Stem Ccoerater lkter level-Lcm NlONSLK

%UK Focd f)m 5g3.9%

~else rated Stem flee s.gh 3.

of aarwe raayo iastnaeat feed f1m~

hei~ rated Stem flm I0%

~f Wa~

raaye iastrmoat 13.

IJndereAtago - 4.1C N 8osses A aid I N.

Qaderfreqaearg - Tri~ of Reactor Cool aat hap Ireaher(s)

Opec 15.

Tibiae Trip

~ dies voltage

~.0 Nz g7lS bus voltage 256.1 Mz 1$.

17.

a.

hecto Stol Oil Pressure h.

Tibiae Stop Alvo Closore Safety l~iea layet Ae

%SF Ioactor Trip System later locks lkterINdlaie l4MQO Nostroa Flex, ~

~ psi9 FillyClose~

~ Ixlo" aops

~ psig fu)ly Clos~

N.h.

Noeinal lxl0

~ Llait mite is set area Tibiae Stop Salvos are fs)ly closed,

I

~

NOTE 1:

OVERTEIIPERATURE hT TABLE

.2-1 Co t ued l

1+ t>S where:

hT (~) <fsfo <"t

<a (-)-'t-fog) p (

t

) - f') e K (g - p') f

()st))

1 + AS

( 1 + ASS)

Neasured hT by RTD Instrumentation 1 ~>S Lead/Lag coapensator on aeasured hT; r>~, z> ~

1 + AS t.ag oNspensator on neasored ftf; rs ~ gs 1 + t3S hTo Kz Mme 1+ r5S T4g Ts 1 + reS Indicated hT at RATED THHUNL PNER li2E OF 0eOL Q The function generated by the lead-lag compensator for T dynaaic coIIpensation; Tiae constants utilized in the lead-lag compensator for T~Q, r4

25s, fg ~ 3 sg Average teaperature, F;

Lag caapensator on aeasured Te>>.g re ~ Os T'

~

574.2 F (Nominal Te at RATED THERNAL POMER);

K3.

/psig; 0

a 001L Pressurizer

pressure, psig;

I

~

N lt r

NOTE 1:

(Continued)

, TABLE 2.2-1 Continued TABLE NOTATIONS Continued P'

2235 psig (Noainal RCS operating pressure);

S Laplace transfora operator, s-~;

and fq (hI) is a function of the indicated difference between top and bottoa detectors of the power range neutron ion chambers; with gains to be selected based on eeasured instrument response during plant startup tests such that:

(1)

For q - qD Antenna~and ft (Al) ~ 0, nhere qt and qn are percent RATED TRERRAL PSKR in the top and bottos halves of the core respectivel nd qt + qb is total THERNL PNER in percent of RATED THERNAL PNN;

-+e%

(2)

For each percent that the mgnitude of qt - qb exceeds the hT Trip Setpoint shall be autoaatfcally reduced by 1.% of its value at RATED THERNAL PNER; and (3)

For each percent that the sagnitude of qt - qb exceeds, the hT Tr ip Setpo nt shall be autoaatically reduced by of its value at RATED THERNAL PNER.

.s%

NOTE 2:

The channels saxi'rip setpoint sha not exceed its coaputed setpoint by sore than of instrint span.

o,13%

TABLE 2. 2-1 Continued TABLE NOTATIONS Continued NOTE 3:

OVERPONER OT nT 1 + e S

1

< OT (K - K ~

T - K [T

- T ] - f (n()j (tS

)

(

1

)

1

+ te

+ te o

e e

1+ tfS (1+ xoS) o (1+ xoS)

Mhere:

As defined in Note 1, hs defined in Note 1, 1+ taS 1

~

AI defined

$ n Note 1, M~xa.N aT X7 1

+ Ta As defined in Nate 1, c.,

l >O 0.02/ F'or increasing average temperature and 0 for decreasing average teaperature, The function generated by the rate-1ag compensator for T dyneaic coepensation, avg Time constants uti1$zed in the rate-lag compensator for T

, t

> 10 s avg's defined in Note 1,

t sr g

fJ

0,002.32 TABLE 2.2-1 Continued TABLE NTATIDNS Continued NTE 3:

(Continued)

Kg F for T > l or

< T",

As defined in Note 1, Indicated Tay at RATED THERNAL PNER (Calibration teaperature for hT instnaentation,

< 57'.2'F),

S

~

As defined in Note 1, and fg (hI)

~

0 for all hI NTE 4:

The nel's aaxfaa trip setpoint shall not exceed its cowputed trip setpoint by sore than of inst+cent span.

O,g

~ ~

POWER DISTRIBUTION LIMITS 3/4.2. 5 ONB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the following limits:

a.

Reactor Coolant System Tav

( 576 6of b.

Pressurizer Pressure

> 2209 psig", and c.

Reactor Coolant System Flow

>277,900 gpm APPLICABILITY:

MODE 1.

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 5X 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 RE UIREMENTS

)Qsf g& '5'~

4.2.5.1 I

O 4.2.589 The RCS flow rate Indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.

4.2.5

~

~

1 ihlSZfd.T'C) REe.e

• Limit not applicable during either a THERMAL POWER ramp in excess ofi'f RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10K of RATED THERMAL POWER.

TURKEY POINT - UNITS 3 Ec 4 3/4 2-16 AMENDMENT NOS.137 AND 132

~

~ ~

EP

~

aS Attachment 4 to L-95-250 ZNSERT B

Reactor Coolant System T,~ 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 />.

4.2.5.2 RCS flow rate shall be monitored foz 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 />.

V INSERT C

4.2.5.4 After each fuel loading, and at least once per 18 months, the RCS flow rate shall be determined by precision heat balance after exceeding 90%

RATED THERMAL POWER.

The measurement instrumentation shall be calibrated within 90 days prior to the performance of the calorimetric flow measurement.

The provisions of 4.0.4 are not applicable for performing the precision heat balance flow measurement.

I+y

• a

~

~ ~

I J

5.

Feaster Isolatiea (Ceatiaeel)

c. St~ Ceaerater i@ter Level Ni~igh C.

%ciliary Faadnter (3) a.

Aitoeatic Acbsatiea Lee)c sad Actuatice Iel~

h.

Steae 6eaerator ltater LevelLew-Lce c.

Safety lajectioe d.

Ivs Stt )ppiae

+1.%S of aarras ramie isetr~et spae I.A.

~ e,vl QSS ef MtFCN iest~t ski See Itea l. above for al'I Safety l~

Alleieble Valves.

See ltea 7. below fer all Ivs Stripping Alleahle Valves.

~ of aa~

raage iastnmat span N.A.

Io%

SK ef carr riage iast~t spaI o See Bee 1. abeve for a)1 Safety Eeject$ ee Trip Setpoiats.

See lteo 7. helm for al)

Ivs Striyyine Trip Setpoiats.

C

~

70 e.

Trip ef All Na)a Feahater hap Sreakers toss of i~ir a.

4.16 RV basses A and b

{toss of Voltage)

I.A.

I.A.

N.A.

N.A.

CJ A

~

~ i

)

POWER OISTRIBUTION LIMITS BASES 3/4.2.4 UAORANT POWER TILT RATIO The gUAORANT POWER TILT RATIO limit assures that the radial power dis-tribution satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides ONB and linear heat generation rate protection with x-y plane power tilts.

A limit of 1.02 was selected to provide an allowance for the uncertainty asso-ciated with the indicated power tilt.

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 correc-tion of a dropped or misaligned control rod.

In the event such action action does not correct the tilt, the margin for uncertainty on F~ (Z) is reinstated by reducing the maximum allowed power by 3X for each percent of tilt in excess of l.

For purposes of monitoring gUAORANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors or incore thermocouple map are used to confirm that the normalized symmetric power distribution is consistent with the gUAORANT 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 syaeetric thimbles is a unique set of eight detector locations.

These locations are C-8, E-5, E-Q, H-3, H-13, L-5, L-11, N-8.

3/4.2.5

'ONB PARAMETERS The limits on the ONB-related parameters assure that each of the param-eters 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 ade-quate to maintain a minimum ONBR above the applicable design limits throughout each analyzed transient.

The indicated iT v value of 576.6'F and the indicated pressurizer pressure value of 2209 psig correspond to analytical limits of 578.24F and 2I85 psig respectively, with allowance for measurement uncertainty.

The indicated RCS flow value of 277,900 gpm corresponds to an analytical limit of 268,500 gpm which is assumed to have a 3.5X measurement unce~inty.

The above measurement uncertainty estimates assume that'hese instrument channel outputs are averaged to minimize the uncertainty.

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.

TURKEY POINT - UNITS 3 8( 4 B 3/4 2-8 AMENOMENT NOSl37 AN0 132

Attachment 4 to L-95-250 XNSERT D

The 18-month periodic measurement of the RCS total flow rate is adecpxate to ensure that the DNB-related flow assumption is met and to ensure correlation of the flow indication channels with measured flow.

Six month drift effects have been included for feedwater temperature, feedwater flow, steam pressure, and the pressurizer pressure inputs.

The flow measurement is performed within ninety days of completing the cross-calibration of the hot leg and cold leg narrow range RTDs.

The indicated percent flow surveillance on a 12-hour basis will provide sufficient verification that flow degradation has not occurred.

A change in indicated percent flow which is greater than the instrument channel inaccuracies and parallax errors is an appropriate indication of RCS flow degradation.

V' g'I.

4