ML20198C374
| ML20198C374 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/31/1997 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20198C365 | List: |
| 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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g mo2,rf37r-es 620 -
qua,e2t:26:
S T
b N,%-q 7Imo; man) 600 -
(1.30, Sv7.48)
(1.30, $95m)
(l.30,587.28)
(1.11 f, $8173, ~
580 -
L- -
~
~
(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.
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
i 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,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 <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
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