ML20084U703
| ML20084U703 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 04/15/1991 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20084U701 | List: |
| References | |
| NUDOCS 9104220202 | |
| Download: ML20084U703 (6) | |
Text
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.ATTACFIMENT 2 PROPOSED TECllNICAL SPECIFICATIONS 2.2.1, 3.3.1, TABLES 2.2 1, 3.3 1, 3.3 2, 4.3 1, ITEM 4 l-
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r 9104220202 910413 hDR ADOCK 05000498 PDR A1/016.N16
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. TABLE 2.2-1 gto o.
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H r-5 RFACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
- ,$Q x
j'$"
i;;
IOTAL SENSOR og$
s Alt 0WANCE ERROR FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VAlUE-1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
N. A.
2.
Power Range, Neutron Flux l
a.
High Setpoint 7.5 4.56 0
<109% of RTP**'
1111.3% of RIP **
b.
Low Setpoint H. 3
- 4. %
0 co
-<75% of RTP**
- 77. 3% of RTP**
3.
Power Range, Neutron Flux,.
- 1. 6 0.5 0
<5% of RTP** with
<6.3% of RTP** with Dka High Positive Rate 5 time constant 3 time constant gg,
>2 seconds g econds 4
Power Range, Neutron Flux,
- 1. 6 -
- 0. 5 ~
O
<5% of RTP** with
<6.3% of RTP** with High Negative Rate 3 time constant i time constant h2 seconds
~
>2 seconds ro
^
5.
Intermediate Range, 17.0 8.41 0
<25% of RTP**
<31.1% of RTP**
Neutron Flux 6.
Source Range, Neutron Flux 17.0 10.01 0 110 cps
$1. 4
.v 10 cps 5
5 7.
Overtemperature AT 6.8
- 4. 66 -.1. 5 + 0. 9 #. See Note 1 See Note 2 8.
Overpower AT 5.5 1.74
- 1. 5 See Note 3 See Note 4 9.
Pressurizer Pressure-Low 3.1 0.71*
- 2. 0
>1870 psig
>1862 psig 10.
Pressurizer Pressure-High 3.1 0.71 2.0
<2380 psig
$2388 psig 11.
Pressurizer W'ater Level-High 5.0 2.76
- 2. 0
$92% of instrument
$93.6% of instrument i
span span 12.
Reactor Coolant Flow-tow 4.0 3.19 0.6
>91.8% of loop
>90.9% of loop Besign flow
- design flow"
" Loop design flow = 95,400 gpm-
- RlP = RATED THERMAL POWER
- 1.5% span for AT; 0.9% span for Pressurizer Pressure
.m.
~ _. _ _.
M f/CiMENT 4 ST-HL AE 3750
/mN PAGE
.3 0F 5
//
DC LIMITING SAFfTY SYSTEM SETTING.!,
- (
AnfJ AUG 031990 L
REACTOR TRIP SYSTEM INSTRUMEKTATION SETPOINTS (Continued)
\\L l
s COPY The various Reactor trip ef tcuits automatically open the Reac$,3 T2#
\\
t bip c breakers whenever a condition monitored by the Reactor Trip System re;atheFa preset or calculated level.
In addition to redundant channels and trains the design approach provides a Reactor Trip System which sonitors numerous sys, tem variables, therefore providing Trip System functional diversity. The functional L
capability at the specified trip setting is required for those anticipatory or diverse Reactor trips for which no direct credit was assumed in the safety i
L analysis to enhance the overall reliability of the Reactor Trip System. The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is initiated.
This prevents the reactivity insertion that would otherwise result l-from excessive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System.
Manual Reactor Trip The Reactor Trip System includes manual Reactor trip capability.
Power Ranoe, Neutron Flux In each of the Power Range Neutron Flux channels there are two independent bistables,The Low Setpoint trieach with its own trip setting used for a High and Low i (-
setting.
provides protection during suberttical and low power operations to mitigate the consequences of a power excursion beginning from low power, and the High Setpoint trip provides protection during power operations to sitigate the consequences of a reactivity excursion from all l
power levels.
The Low Setpoint trip may be manually blocked above P-10 (a power level i
of approximately 10% of RATED THERMAL POWER) end is automatically reinstated
. below the P-10 Setpoint.
power Range. Neutron Flux, Hion Rates The Power Range Positive Rate trip provides protection against rapid flux l.
increases which are characteristic of a rupture of a control rod drive housing, i
Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for-rod ejection from mid power.
The Power Range bgative Rate trip provides protection for c6KErollod drop accidents.
At high power a single or multiple rod drop accident could cause t
local flux peaking witch could cause an unconservative local DNBR to exist. The i
Power Range Negative Rate trip will prevent this from occurring by tripping the t
reactor. No credit is taken for operation of the Power Range Negative Rate trip for those control rod drop accidents for which DNBRs will be greater than the design limit.
(
SOUTH TEXAS - UNITS 1 & 2 B 2-4 June 27, 1990
hh-i m.
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TABLE 3.3-1 5
REACTOR TRIP SYSTEM INSTRUMENTATION 5
MINIMUM M
TOTAL NO.
CHANNELS CHANNELS APPLICABLE 5-OF CHANNELS TO TRIP OPERABLE MODES _
ACTION 7 FUNCTIONAL UNIT E
1.
1 2
1, 2 1
l 2
1 2
3*, 4*, 5*
10 3
I
~
2.
Power Range, Neutron Flux 4
2 3
' 1, 2 2
4 2
3 1###, 2 2
j a.
High Setpoint b.
Low Setpoint'
~
4 2
3 1, 2 2
i
\\3.
Power Range, Neutron Flux M'
J liigh Positive Rate
)
9s1 4
2 3
1, 2 2
w 4.
Power Range, deutron Flux
~-
High Negative Rate J 45.
Intermediate Range, Neutron Flux 2
1 2
1###, 2 3
6.
Source Range, Neutron Flux 2
1 2
2##
4 b.
Shutdown 2
1 2
3*, 4*, 5*
10 a.
Startup 7.
Ext. ended Rance, Neutron Flux 2
0 2
3, 4, 5 4
w3l 4
2 3
1, 2 6
> --4 -y 8.
Overtemperature AT 4
2 3
1, 2 6
Sh5l 5 11 9.
Overpower AT W " E l 4
2 3
1 6
Ski l
- 10. Pressurizer Pressure--Low (Interlocked with P-7) o %o m
11.
Pressurizer Pressure--High 4
2 3
1, 2 6
12.
Pressurizer Water Level--High 4
2 3
1 6
h I
(Interlocked with P-7) i 1
1
f n
m, 4
s-
' TABLE 3.3-2 ISy
' REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES, y
FUNCTIONAL UNIT RESPONSE TIME 1.'
Manual': Reactor Trip -
N.A.
h
~2.
Power Ran'ge, Neutron Flux.
$ 0.5 second*'
- 'I 3.
Power Range, Neutron Flux, High Positive Rate.
N.A.
h 4.V Power Range, Neutron Flux.
High Negative Rate J.5 second*
5.
Intermediate Range, Neutron Flux N.A.
w Source Range, Neutron Flux
$ 0.5 second*
1 o.
7.
Extended' Range, Neutron' Flux
'N.A.
d.
Overtemperature AT
$ 8.0 seconds
- 9.
' Overpower AT'
$ 8.0 seconds *
- 10. Pressurizer' Pressurr -Low
$ 2 seconds
- 11. Pressurizer Pressure--Hig;a
$ 2 seconds w a -i 12.
Pressurizer Water Level--High
-< 2 seconds Si5:
<oSI cng t
r UE t
am ou l
'O
- Neutron detectors'are exempt'from response time testing. Response time of the neutron flux signal portion of the channel shall be' measured from detector output or input of first electronic component in channel.
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TABLE 4.3-1 y.
c2 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILt.ANCE REQUIREMENTS.
N TRIP ANALOG ACTUATING MODES FOR
]
CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL-OPERATIONAL ACTUATION SURVEILLANCE k _ FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED--
1.
Manual Reactor Trip M.A.
N.A.
M.A.
R(14)
M.A.
1, 2, 3*, 4*, 5*
2.
Power Range, Meutron e.
Flux u
a.
High Setpoint S
O(2,4),
Q(17)
N.A.
N.A.
1, 2
'M(3. 4),
^
Q(4. 6),
R(4, 5)
[
b.
Low Setpoint
~,
R(4)
$/U(1)
N.A.
M.A.
1***, 2 w
3.
Power Range, Neutron N. A.'
R(4)
Q(17)
N.A.
M.A.
1, 2 5
Y
- Flux, tf High Positive Rate
- 0. f r Range, Neutron 4
N.A.
R(4)
Q(17)
N.A.
M.A.
p Negative Rate
[
^
5.
Intermediate Range, 5
R(4,5) 5/U(1)
N.A.
M.A.
1***, 2
{
Neutron Flux e
h 6.
Source Range, Neutron S R(4,5)
S/U(1).
Flux Q(9)(17)
N.A.
M.A.
2**, 3, 4, 5 g
7.
Extended Range, 5,
R(4)-
Q(12,17)
M.A.
N.A.
3, 4, 5 y
g3-y Neutron Flux
[
8.
-dverteeperature AT S
R-Q(17)
N.A.
N.A.
1, 2
"' y j
9.
Overpower AT S
R Q(17)
N.A.
M.A.
1, 2 d2
[ 10.
Pressurizer Pressure N.A.
1 oWp
,--Low 5
R Q(17)
N.A.
o
's O
<.g
~_.
f p
g
,