ML20198C374

Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow

ML20198C374
Person / Time
Site:	South Texas
Issue date:	12/31/1997
From:	HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20198C365	List: ML20198C374 NOC-AE-000050, Application for Amends to Licenses NPF-76 & NPF-80,revising TS Sections 2.1,2.2 & 3/4.2.5 by Including Alternate Operating Criteria to Allow Continued Plant Operation W/ Reduced Measured RCS Flow Rate If Necessary
References
NUDOCS 9801070255
Download: ML20198C374 (11)

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i ATTACHMt..a 4 PROPOSED TECHNICAL SPECIFICATION REPLACEMENT PAGES Affected Pages iii 2-1 2 2 (A)[NEW]

2 2-7 2-8

.2-9 2-10 3/42-11 B 3/4 2-6 Proposed changes are italicized and indicated by revision bars on the right-hand margin of the page The ' exception is the new figure on page 2-2 (A).

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9901070255 971231 DR ADOCK O 4y8 i

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INDEX 2.0 RAFETY I.IMITS AND I IMITING SAFETY SYSTEM SE*ITINGS L

SECTION PAGE 2.1 SAFETY LIMITS-2.1.1 - R E A CTO R CO R E .. .. ... ........ .. .. ........... .... ............ . .... .. .... .. .. . 21 2.1.'1 REACTOR COOLANT SYSTEM PRESSURE .. .. ..... ... ....... . . ........... . 21 FIGURE 2.1 1 REACTOR CORE SAFETY LIMIT.FOUR LOOPS IN OPERATION... 22 FIGURE 2.12 REACTOR CORE SAFETl'IJMIT.FOUR LOOPS IN OPERA TION.. 2 2 (A)

(ALTERNATE) 2,2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REAGTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS ........................ 23 TABLE 2.21 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS.. 24 HASFS SECTION 2.1 SAFETY LIMITS 2.1.1 R E A CTO R CO R E ......... .......................... . .......... ..... .. ....... ........... ......... . B21 2.1.2 REACTOR COOLANT SYSTEM PRESSURE ............ .. .. ................ .... . B22 2.2 I.IMITING SAFETY SYSTEM SETTINGS 2.2.1 ' REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS .................. . B23 l

SOUTil TEXAS - UNITS 1 & 2 111 '

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? 10 SAFETY 1 IMITS AND T.IMITING SAFETY SYSTEM SETTINGSi a - s ..

i 2.1 SAFETY LIMITS 1 _ _

REACTOR CORE

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2.1.1 L The combination of THERMAL POWER, pressurizer pressure, and the' highest -

operating loop coolant temperature (T y,) shall not exceed the limits shown in Figure 2.1- s

^l,'or in Figure 2.12 when operating under alternate; operating criteria consistent with .

reduced Reactor Coolant Systempow as addressed in Technical Specification 3.2.5.

APPLICABILITY:' MODES 1 and 2.-

- ACTION:

Whenever the point defined lg the combination of the highest operating loop average temperature and: THERMAL- POWER has exceeded the appropriate pressurizer pressure.

- line, be. in HOT. STANDBY within 1 -hour, and comply -with the' requirements of

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' Specification 6.7.1.

REACTOR COOLANT SYSTEM PRESSUllE -

2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.

/ 6PPLICABIL}_TX: MODES 1,2,3,4, and 5.

1 ACTION:

i M_ ODES I and _2:

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY,with the Reactor Coolant System pressure. within its limit within I hour, and comply with the requirements of Specification 6.7.1.

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, MODES 3,4 and 5:

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.Whenever the Reactor Coolant System pressure has exceeded' 2735 psig, freduce~the Reactor _ Coolant _ System pressure to within its limit within 5 minutes, and comply with the requirements of Specification 6.7.1.

- ::SdUTH TEXAS.- UNITS 1 & 2 -

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(1.30, $95m)

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(l.30,573,34)

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(uo,362.7o 0 0.2 0,4 0,6 0,8 1 1,2 Fraction of Rated Thermal Power Figure 2.1-2 Reactor Core Safety Limit - Four Loops in Operation (Alternate) 50UTil TEXAS - UNITS 1 & 2 . 2-2 (A) Unit 1 - Amendment No 4, M Unit 2 - Amendment No. 60 i

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TABLE 2.2-1 C REACTOR TRIP SYSTEM INSTRUMENTATIO TRIP SETPOINTS I:i X

> TOTAL SENSOR 7 A' ! OWANCE ERROR j FUNCTIONAL UNTF 0 ,. I (S) TRIP SETPOINT ALLOWABLE VALUE

=

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

> 2. Power Range, Neutron Rux o a. High Setpsint 7.5 6.1 0 $109% of RTP" sl10.7% of RTP"

b. Iow Setnoint 83 6.1 0 $25% of RTP" s27.7% of RTP**

3. Power Range, Neutron Rux 2.1 0.5 0 s5% of RTP** with 5 67% of RTP** with High Positive Rate a time constant a time constn.nt 22 seconds 22 seconds

4. Deleted

5. Intermediate Range, 16.7 8.4 0 $25% of RTP** $31.1% of RTP**

Neutron Rux

$ 6. Source Range, Neutron Rux 17.0 10.0 0 510' cps $1.4 :: 10' cps

7. Overtemperature AT 10.7 8.7 1.5 + 1.5# See Note I See Note 2

8. Overpower AT 4.7 2.1 1.5 See Note 3 See Note 4

9. Pressurizer Pressure-Iow 5.0 23 2.0 2870 1 psig 21860 psig

10. Pressurizer Pres ,ure-High 5.0 23 2.0 s2380 psig $2390 psig i1. Pressurizer Water Level-High 7.1 43 2.0 $92% ofinstrument $ 94.1%ofinstrument span span

$$ 12. ReactorCoolant Row-Low 4.0 2.1 0.6 291.8% ofloop 290.5% ofloop

'[ design flow

• design flow

• SS g8 *Loor design flow = 93,400 gpm (or 92,500 gymfor alternate operation with reduced RCSl low) y$ **RTP = RATED THERMAL POWER 3_ $ #1.5% span for AT; 1.5% span for Pressurizer Pressure h h.

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i0 TABLE 22-1 (Costmuod)

TABLE NOTATIONS

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NOTE 1: OVEtIEMPERATURE AT '

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. AT(1 + t:5) ( 1 ) s ATo (K - K2 (1 +t@ (T( . 1 )-T ) + K,(P- P')- f (AI)}

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Ih. (1+trS)(1+T5) 3 (I+ tsS) (1+t.5) 1i y M Where

AT = Measured AT by RCS Instrumentanos:

SP -

u. I + t,S = lead-lag corare==*w on measured AT: .

1+T5 2 E = Tune constant utilized in lead-lag e --=um- fw AT. ta = 8 sec, t.22 i

22= 3 sec:

1 1 = Lag compensator on measured AT:

1 +t35

, t3' = Tune constut utilized in the lag _ _ _ , - - - for AT,t 3= 0 sec:

-u-U AT, = Indicased ATat RATED THERMALPOWER

K, = I.14.or 1.13foralrernareoperatum wide ueducedRC5fime:

K2 = 0.028PF:

I + t.S = The function gc~C by the lead-lag compensator fort ,

i 1+TS dynanuc m .,-.. mion:

3 CC EE t ts = Tune constants utdized i. the lead-lag compensasor for T t. = 28 sec.

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.. .. t3= 4 see:

g g- T = Average % - ~ *F:

oa.

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. = lag compensator on measured T ,:

g3 I + t.S ZZ

p. pp t. = Timeconstantutili. e enessured T,., lag e.. t. = 0 see; 3

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-i TABLE 2.2-1 (Continued) 3 s TABLE NOTATIONS (Continued) 2 z NOTE 1: (Continued)

E T' s 593.0 F( Nominal T.,, at RA'ED THERhiAL POWER) or590.O*Fforalternate m

z operatwn with reduced RCSficn-

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d K3 = 0.00143/psig; tJ P = Pressurizerpressure,psig; i P' = 2235 psig (Nominal RCS operating pressure):

S ' = Laplace transform operator, sec;

y and f i(AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron i k ion chambers; with gains to be selected based on measured instrument response during plant startup tests such hat-

6) For q, - qs between -70% and + 8%, or +6%for alternate operation with reduced RCSflow, f,(Al) = 0, where q, and qs are percent RATED THERAf AL POWER in the top and bottom halves of the core respectively, and q,+ q3 is total THERAfAL POWER in percent of RATED THERAfAL POWER:

E$ (2) For each percent that 'he magnitude of q1- qs exceeds M the AT Trip Setpoint shall be

,] [ automatically reduced by 0 0% ofits value at RATED Tlit:RAf AL PO%TR: and I

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E (3) For each percent that *he magnitude of q,- q3 exceeds +8%, or +6%for alternate operation with reduced RCSflow, the AT Trip Setpoint shall be automatically reduced by 2.65% ofits value at RATED

's a{ THERAfAL POWER.

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' } } NOTE 2: De channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 1.6% AT

' -i span.

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c TABLE 2 2-1 (Continued) 3 a TABLE NOTATIONS (Continued) k: NOTE 3: OVERPOWER AT D

h AT (1 + T S) ( l' ) s; ATo (L - K5( T7S ) ( I ) T- K6(T ( 1 ) -T7 - f 2(A 0)

-3 (I + T2 S) (1 + 3) 5 (1 + T75) (1+ 6S) (1 +r6S) d ~

{ Where: ' AT = As defined in Note I, I + tis = As defined in Note I, I+T5 2 T,T2 i = As defined in Note I, I = As defined in Note 1.

I +r 3S y T3 = As defined in Note 1, 6

ATo = As defined in Note I, L = 1.08, or LO7for alternate operation with reduced RCSflow, 4

K3 = 0.02fF for increasing average temperature and 0 for decreasing average temperature, T7S = He function generated by the rate-lag compensator for Tavg dynamic

, I+TS 7 compensation T7 = Time constant utilized in the rate-lag compensator for T g. tr = 10 sec, I _ = As defined in Note 1, I + -4 Is = As defined in Note 1, '

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y w , ,, , - ...,,..

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d TABLE 2.2-1 (Continued)

Q TABLE NOTATIONS (Continued) g NOTE 3: (Continued)

L = 0.002 /*F .'or T > T" and L = 0 for T s T",

R

$ T = As defined in Note 1.

W T" = Indicated T.,at RATED THERMAL POWER (Calibraion temperature for AT instrumentation, S593.0*F, or $590.0'Ffor a: ternate operation wih reduced RCSflow), l S = As defined in Note 1 and f(AI) 2 = 0 for all AL e,a E NOTE 4: He channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 1.9"x AT span.

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l POWER DISTRIBUTION LIMITS 3/4.2.5 DNB PARAMETERS I IMITINO CONDITION FOR OPERATION i 3.2.5 The following DNB related parameters shall be maintained within the limits  !

following:

a. Reactor Coolant System T.,,,3; 598'F  :

(or s 595*F with reduced RCSflow of 3.2.5.c)

b. Pressurizer Pressure, > 2189 psig*

c. Reactor Coolant System Flow.2 392,300 gpm** ,

(or 2380,500 gym *

• with reduced RCS Tar, of 3.2.5.a)

APPLICABILITY: MODE 1. T 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 TiiERMAL POWER to less than 5% of RATED TilERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVI:lf I ANCE REOUIREMENTS 4.2.5.1 Each of the parameters shown above shall be verined to be within its 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 />. The provisions of Specification 4.0.4 are not applicable for verification that RCS flow is within its limit.

4.2.5.2 The RCS How rate indicators shall be subjected to a channel calibration at least once per 18 months.

4.2.5.3 The RCS _ total now rate shall be determined by precision heat balance 3 measurements at least once per 18 months. The provisions of Specl0 cation 4.0.4 are not applicable.

• Limit not applicable during either a Thermal Power ramp in excess of 5% of RTP per minute or a Thermal Power ste,7i n excess of 10% RTP.

- ** Includes a 2.8% How measurement uncertainty.

SOUTil TEX,.S - UNITS I & 2 3/4 2-11 Unit 1 - Amendment No. 61 Unit 2 - Amendment No. 60 1

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POWER DISTRIBUTION LIMITS DARRM 3/4.2.5 DNB PARAMRTERS (Continued)'

initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of greater than or equal to the design limit throughout each analyzed l transient. The T.,, value of $98'F and the pressurizer pressure value of 2189 psig are '

analytical values. The readings from four channels will be averaged and then adjusted to  !

account for_ measurement uncertainties before comparing with the. required limit. The --  :

flow requirement (392,300 gpm) includes a measurrment uncertainty of 2.8%. I Technical Spec {fication 3.2.5 provides for an alternate minimum measured Reactor Coolant Systemflow limit consiste.,t with plugging up to 10% of steam generator tubes f:

and Departurefrom Nucleate Bolling requirements. When using the alternate minimum '

.i pow limit, the Ta,, limit is reduced to 595*Ffor Reactor Coolant SystemJIow no less  ;

than 380,$00 gym. Setpoint and constant valuesfor OPAT and OTAT are also revised

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accordingly when this attemate mode ofoperation is entered.  :

+

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is [

sufficient to ensure that the parameters are restored wit}h their limits following load j changes and other expected transient operation.  !

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~ SOUTH TEXAS - UNITS I & 2 B 3/4 2 6 Unit 1 - Amendment No. 6M40495 Unit 2 - Amendment No. 60 n

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