Text

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).

1 9901070255 971231 DR ADOCK O 4y8 i

(

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

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

~

.i i

l 1

W

~

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

- s..

i 2.1 SAFETY LIMITS 1 _ _

REACTOR CORE

~

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

~

' 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.

ACTION:

1 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.

7 MODES 3,4 and 5:

.t

.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 2-1 1

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qua,e2t:26:

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b N,%-q 7Imo; man) 600 -

(1.30, Sv7.48)

(1.30, $95m)

(l.30,587.28)

(1.11 f, $8173, ~

580 -

L- -

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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

roO 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.

2. Power Range, Neutron Rux

a. High Setpsint 7.5 6.1 0

$109% of RTP" sl10.7% of RTP" o

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 7% of RTP** with 6

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 psig 21860 psig 1

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

$ 4.1%ofinstrument 9

span span

12. ReactorCoolant Row-Low 4.0 2.1 0.6 2 1.8% ofloop 290.5% ofloop 9

'[

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.

3%

s

~t

m res '

l i0 TABLE 22-1 (Costmuod)

. *4 -

TABLE NOTATIONS M'

NOTE 1: OVEtIEMPERATURE AT '

t:

c

'M l

) s ATo (K - K (1 +t@ (T(. 1

)-T ) + K,(P-P')- f (AI)}

AT(1 + t:5) ( 1 i

2 1

Ih.

(1+trS)(1+T5)

(I+ tsS)

(1+t.5) 3 1i y

M Where:

AT

= Measured AT by RCS Instrumentanos:

SP -

I + t,S

= lead-lag corare==*w on measured AT:.

u.

1+T5 2

E t.22

= Tune constant utilized in lead-lag e

--=um-fw AT. ta = 8 sec, i

2 = 3 sec:

2 1

1

= Lag compensator on measured AT:

1 +t 5 3

t3'

= Tune constut utilized in the lag _ _ _, - - - for AT,t = 0 sec:

3

-u-U AT,

= Indicased ATat RATED THERMALPOWER:

K,

= I.14.or 1.13foralrernareoperatum wide ueducedRC5fime:

K

= 0.028PF:

2 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.

N~

t3= 4 see:

g g-T

= Average % - ~ *F:

oa.

I

= lag compensator on measured T,:

I + t.S g3 ZZ p.

pp t.

= Timeconstantutili.

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

i l

1

.-.,,,.-,J.,-_.--

..,--.-..-m-

.--. m m.-,..,-.-

.... - -. -. ~.

i

.1 2O C:-i TABLE 2.2-1 (Continued) 3 TABLE NOTATIONS (Continued) s2

> NOTE 1: (Continued) z E

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

operatwn with reduced RCSficn-z

~

d K

= 0.00143/psig; 3

tJ P

= Pressurizerpressure,psig; i

P'

= 2235 psig (Nominal RCS operating pressure):

S

' = Laplace transform operator, sec;

and f (AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron i

y 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

($

(3)

For each percent that *he magnitude of q,- q3 exceeds +8%, or +6%for alternate operation with reduced

's a{

RCSflow, the AT Trip Setpoint shall be automatically reduced by 2.65% ofits value at RATED E

THERAfAL POWER.

EE

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

' i span.

1 1

z Oc TABLE 2 2-1 (Continued) 3 TABLE NOTATIONS (Continued) a k:

NOTE 3: OVERPOWER AT D

h AT (1 + T S) (

l'

) s; ATo (L - K5( T7S ) ( I

) T-K (T (

1 ) -T7 - f (A 0) 6 2

-3 (I + T S) (1 +

5 3)

(1 + T75) (1+ 6S)

(1 +r6S) 2 d

~

{

Where: '

AT

= As defined in Note I, I + tis

= As defined in Note I, I+T5 2

T,T2

= As defined in Note I, i

I

= As defined in Note 1.

I +r 3S T3

= As defined in Note 1, y

6 ATo

= As defined in Note I, L

= 1.08, or LO7for alternate operation with reduced RCSflow, K

= 0.02fF for increasing average temperature and 0 for decreasing average 4

3 temperature, T7S

= He function generated by the rate-lag compensator for Tavg dynamic I+TS compensation 7

= Time constant utilized in the rate-lag compensator for T g. tr = 10 sec, T7 I _

= As defined in Note 1, I + -4 Is

= As defined in Note 1, aw

~

y w

en.

O Cd 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) = 0 for all AL 2

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.

cc E-E-m-

e e

kk aa RR aa ZZ

.o.o

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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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce TiiERMAL POWER to less than 5% of RATED TilERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 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,7 n excess of 10% RTP.

i

- ** 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

1 i

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 f

Coolant Systemflow limit consiste.,t with plugging up to 10% of steam generator tubes 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

}

accordingly when this attemate mode ofoperation is entered.

+

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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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i

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

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ML20198C374

Text

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