ML20091A824
| ML20091A824 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 03/12/1992 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091A826 | List: |
| References | |
| NUDOCS 9203300182 | |
| Download: ML20091A824 (26) | |
Text
.
l f* ** %q'o, UNITED STATES ES
~j NUCLEAR REGULATORY COMMISSION 3m E
WASHINGTON. O, C. 20%$
/
[
HOUSTON LIGHTING & PQWER COMPANY l
l C_LTY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY l
CITY OF AUSTIN. TEXAS DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 l
AMENPMENT TO FACillTY OPERATING LICENSE l
Amendment No. 34 License No. NPF-76 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendnent by Houston Lighting & Power Company *
(HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),
i and City of Austin, Texas (CCA) (the licensees) dated April 15, 1991, as supplemented by letter dated January 24, 1992, complies with the standards and requirements of the Atomic Energy Act cf 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applicatio.
as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied Houston Lighting & Power Company is authorized to act for the City Public l
Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9203300182 920312 i
1 PDR ADOCK 05000498 P.
t "
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of facility Operating License No. NPF-76 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
34, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and to be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
\\ WD W
Suzanne C. Black, Director Project Directorate IV-2 Division of fleactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation t
Attachment:
Changes to the Technical Specifications l
Date of Issuance:
March 12, 1992
ATTACHMENT TO LICENSE AMENDMENT NO. -34 FACILITY OPERATING llCENSE N0. NPF-76 00CKET N0. 50-498 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are-identified by amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 2-4 2-4 B 2-4 B 2-4 3/4 3-2 3/4 3-2 3/4 3-9 3/4 3-9 3/4 3-11 3/4 3-11 i
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l SAFETY LIMIIS AND LIMITING _ SAFETY SYSTEM __ SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent '.<ith the Trip Setpoint values showa in Table 2.2-1.
APPLICABILITY:
As shown for each channel in Table 3.3-1.
ACTION:
With a Reactor Trip System Instrumentation or Interlock Setpoint a.
less conservative than the value shown in the Trip Setpoint column l
but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the Setpoint consistent with the Trip l
Setpoint value.
b.
With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Value column of Table 2.2-1, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 2 + R + 5 < TA Where:
Z = The value from Column Z of Table 2.2-1 for the affected channel, R = The "as-measured" value (in percent span) of_ rack error for the affected channel, S = Either the "as-measured" value-(in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 2.2-1 for the affected channel, and TA = The value-from Columh TA (Total Allowance) of Table 2.2-1 for the affected channel.
I SOUTH TEXAS - UNITS 1 & 2 2-3
1 m
TABLE 2.2-1 o
g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS M
TOTAL SENSOR y
ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE E
1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
N.A.
Z 2.
Power Range, Neutron Flux a.
High Setpoint 7.5 4.56 0
$109% of RTP**
$111.3% of RTP**
H o.
N b.
Low Setpoint 8.3 4.56 0
$25% of RTP**
$27.3% of RTP**
3.
Power Range, Neutron Flux,
- 1. 6 0.5 0
<5% of RTP** with
<6.3% of RTP** with High Positive Rate i time constant i time constant 12 seconds 32 seconds 4.
Deleted T
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
$105 cps
$1.4 x 10 cps 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 gg 9.
Pressurizer Pressure-Low 3.1 0.71 2.0 11870 psig 11862 psig EE 10.
Pressurizer Pressure-High 3.1 0.71 2.0
$2380 psfo
$2388 psig 7 7 11.
Pressurizer Water Level-High 5.0 2.76 2.0
<92% of instrument
<93.6% of instrument
[
span ipan 12.
Reactor Coolant Flow-Low 4.0 3.19 0.6
>91.8% of loop
>90.9% of loop mm ll Besign flow
- Besign flow
- EE
- Loop design flow = 95,400 gpm i
ep
- RTP = RATED THERMAL-POWER
- 1.5% span for AT; 0.9% span for Pressurizer Pressure
~
I 2.2_ LIM 1 TING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the nominal values at which the Reactor trips are set for each functional unit.
The Trip Setpoints have been selected to ensure that the core and Reactor Coolant System are prevented from exceeding their safety limits during normal operation and design basis anticipated operational occurrences and to assist the Engi-neered Safety Features Actuation System in mitigating the consequences of accidents.
The Setpoint for a Reactor Trip System or interlock function is considered to be adjusted consistent with the nominal value when the "as-measured" Setpoint is within the band allowed for calibration accuracy.
l To accommodate the instrument drift assumed to occur between operational l
tests and the accuracy to which Setpoints can be measured and calibrated, Allowable Values for the Reactor Trip Setpoints have been specified in Table 2.2-1.
Operation with Setpoints less conservative than the Trip Set-point but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error. An optional provision has been included for determining the OPERABILITY of a channel when its Trip Setpoint is found to exceed the Allowable Value.
The methodology of this option utilizes the "as measured" deviation from the spacified calibration l
point for rack and sensor components in conjunction with a statistical combi-natien of the other uncertainties of the instrumentation to measure the process t
varia'ble and the uncertainties in calibrating the instrumentation.
In Equa-tion 2.2-1, Z + R + 5 < TA, the interactive effects of the errors in the rack and the sensor, and.the "as measured" values of the errors are considered.
Z, as specified in Table 2.2-1, in percent span, is the statistical summation of errors assumed in the analysis excluding those associated with the sensor and rack drift and the accuracy of their measurement.
TA or Total Allowance is the difference, in percent span, between the Trip Setpoint and the value used in the analysis for Reactor trip.
R or Rack Error is the "as-measured" devia-tion, in percent span, for the affected channel from the specified Trip Set '
point.
5 or Sensor Error is either the "as-measured" deviation of the sensor from its calibration point or the value specified in Table 2.2-1, in percent span, from the analysis assumptions. Use of Equation 2.2-1 allows for a sensor drift factor and an increased rack drift factor, and provides a threshold value for REPORTABLE EVENTS.
The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels.
Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties.
Sensors and other instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes.
Rack drut in excess of the Allowable Value exhibits the behavior that the rack has not met its allowance.
Because there is a small statistical chance that this will happen, an infrequent excessive drift is expected.
Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of more serious problems and should warrant further investigation.
SOUTH TEXAS - UNITS 1 & 2 B 2-3
LIMITING SAFETY SYSTEM SETTINGS BASES REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS (Continued)
The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by the Reactor Trip System reaches a preset or calculated level.
In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trip System functional diversity.
The functional 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 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 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 Range, Neutron Flux In each of the Power Range Neutron Flux channels there are two independent bistables, each with its own trip setting used for a High and Low Range trip setting.
The Low Setpoint trip provides protection during suberitical and low power operations to mitigate the consequences of a power excursion beginning l
from low power, and the High Setpoint trip provides protection during power operations to mitigate the consequences of a reactivity excursion from all power levels.
The Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) and is-automatically reinstated below the P-10 Setpoint.
Power Range, Neutron Flux, High Rates The Power Range Positive Rate trip provides protection against rcpid flux increases which are characteristic of a rupture of a control rod drive housing.
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.
l SOUTH TEXAS - UNITS 1 & 2 B 2-4 Unit 1 - Amendment No. 34 Unit 2 - Amendment No. 25
1 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.with RESPONSE TIMES as-shown in Table 3.3-2.
APPLICABILITY:
As shown in Iable 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REOUIREMENTS 4.3.1.1 Each Reactor Trip Systen instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1, 4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels I
are tested at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in the
" Total No. of Channels" column of Table 3.3-1.
l l
i SOUTH TEXAS - UNITS 1 & 2 3/4 3-1
TABLE 3.3-1 y,
E 3!
REACTOR TRIP SYSTEM INSTRUMENTATION Q
MINIMUM g
TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1.
1 2
1, 2 1
g 2
1 2
3*, 4*, 5*
10
[
2.
Power Range, Neutron Flux a.
High Setpoint 4
2 3
1, 2 2
y b.
Low Setpoint-4 2
3 1###, 2 2
3.
Power Range, Neutron Flux 4
2 3
1, 2 2
High Positive Rate-4.
Deleted 5.
Intermediate Range, Neutron Flux 2
1 2
1###, 2 3
A 6.
Source Range, Neutron Flux a.
Startup 2
1 2
2##
4 b.
Shutdown-2 1
2 3*, 4*, 5*
10 7.
Extended Range, Neutron Flux 2
0 2
3, 4, 5 4
8.
Overtemperature AT 4
2 3
1, 2 6
i CC gh 9.
Overpower AT 4
2 3
1, 2 6
10.
Pressurizer Pressure--Low 4
2 3
1 6
(Interlocked with P-7) i Q Q 11.
Pressurizer Pressure--High 4
2 3
1, 2 6
i xz E @ 12.
Pressurizer Water Level--High 4
2 3
1 6
i (Interlocked with P-7) zz PP l
5%
i vs TABLE 3.3-2 EE i
5$
REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES
-4 i
R d?
FUNCTIONAL UNIT RESPONSE TIME 1.
Manual Reactor Trip N.A.
h!
2.
Power Range, Neutron Flux
$ 0.5 second*
3 e.
3.
Power Range, Neutron Flux, as High Positive Rate N.A.
4.
Deleted 5.
Intermediate Range, Neutron Flux N.A.
us
-< 0.5 second*
6.
Source Range, Neutron Flux s*"
7.
Extended Range, Neutron Flux N.A i
T 8.
Overtemperature AT
$ 8.0 seconds
- 9.
Overpower AT
$ 8.0 seconds
- 10.
Pressurizer Pressure--Low 1
-< 2 seconds 11.
Pressurizer Pressure--High EI!?
~< 2. seconds
. M: %:
12.
Pressurizer Water Level--High
< 2 seconds n> s ie 8a 4
Etit
- Neutron detectors are exempt from response time testing.
Response time of the neutron flux signal portion gg of'the channel shall be measured from detector output or input of first electronic component in channel.
r* r+
U i
i
TABLE 3.3-2 (Continued) v, 8
-p REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES R$
ik FUNCTION.L UNIT RESPONSE TIME h
13.
Reactor Coolant Flow--Low a
Di a.
Single Loop (Above P-8)
~< 1 second b.
Two Loops (Above P-7 and below P-8)
$ 1 second
~.
14.
Steam Generator Water Level--Low-Low
< 2 seconds 15.
Undervoltage - Reactor Coolant Pumps 5 1.5 seconds 16.
Underfrequency - Reactor Coolant Pumps 5 0.6 second w
3:
17.
'o a.
Low Emergency Trip Fluid Pressure N.A.
c' b.
Turbine Stop Valve Closure N. A.
18.
Safety Injection Input from ESFAS N.A.
19.
Reactor Trip System Interlocks N.A.
20.
Reactor Trip Breakers N.A.
- 21. Automatic Trip and Interlock Logic N.A.
1 4
i
I y,
TABLE 4.3-1 E
I y
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Q
TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE c$
FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED N
1.
Manual Reactor Trip N.A.
N.A.
N.A.
R(14)
N.A.
1, 2, 3*,
4*, 5*
g 2.
Power Range, Neutron Flux m
a.
High Setpoint S
D(2, 4),
Q(17)
N.A.
N.A.
1, 2 o
M(3, 4),
Q(4, 6),
R(4, 5) b.
Low Setpoint 5
R(4)
S/U(1)
N.A.
N.A.
1***, 2 R
3.
Power Range, Neutron N.A.
R(4)
Q(17)
N.A.
N.A.
1, 2
- Flux, y
High Positive Rate U
4.
Deleted 5.
Intermediate Range, S
R(4,5)
S/U(1)
N.A.
N.A.
1***,
2
. Neutron Flux g
6.
Source Range, Neutron S R(4, 5)
S/U(1),
p Flux Q(9)(17)
N.A.
h.A.
2**, 3, 4, S e
7.
Extended Range, S.
R(4)
Q(12, 17)
N.A.
N.A.
3, 4, 5 8
Neutron Flux
[
8.
Overtemperature AT S
R Q(17)
N.A.
N...
1, 2 l
y 9.
Overpower AT S
R Q(17)
N.A.
N.A.
1, 2 10.
Pressurizer Pressure
[
--Low S
R Q(17)
N.A.
N.A.
1
?
u
TABLE 4.3-1 (Continued) v.8y REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
EJ TRIP ANALOG ACTUATING MODES FOR CilANNEL DEVICE milch e
CilANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE 5 FUNCTIONAL UNIT CllECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRE 0 d
11.
Pressurizer Pressure e.
--liigh S
R Q(17)
N.A.
M.A.
1, 2 m
12.
Pressurizer Water Level--High S
R Q(17)
N.A.
N.A.
I 13.
Reactor Coolant Flow
--Low 5
R Q(17, 18)
N.A.
N.A.
I w1 14.
Steam Generator Water w
g Level--Low-Low S
R Q(17,18)
N.A.
M.A.
1, 2 15.
Undervoltage - Reactor Coolant Pumps M.A.
R N.A.
Q(17)
N. A.
I
^
16.
Underfrequency -
Reactor Coolant Pumps N.A.
R N.A.
Q(17)
N.A.
1 17.
Turbine Trip a.
Low Emergency N.A.
R N.A.
S/U(1, 10)
N.A.
1 Trip Fluid Pressure 4
b.
Turbine Stop N.A.
R N.A.
S/U(1, 10)
N.A.
1 Valve Closure 18.
Safety Injection N.A.
N.A.
N.A.
R N.A.
1, 2 Input from ESFAS
- 4
m ato
/
'o UNITED STATES
! " 3 y, f h NUCLEAR REGUL ATORY COMMISSION
- E WASHINGTON, O C. 20555 e
HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET No. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACillTY OPERATJNG LICENSE Amendment No. 25 License No, NPF-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Houston Lighting & Power Company (HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),
and City of Austin, Texas (C0A) (the licensees) dated April 15, 1991, as supplemented by letter dated January 24, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations se'. forth in 10 CFR Chapter I; B.
The 'acility will operate in conformity with the application, as.
amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commitsion's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- Houston Lighting & Power Company is authorized to act for the City Public Service Board of San Antonio, Central Pouer and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
l l
. _~. _.
' 2.
Accordingly, the license is amended by changes to the Technical Specifi-
.,ations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of facility Operating License No. NPF-80 is hereby amended to read as follows:
2.
Technical Specification _q The Technical Specifications contained in Appendix A, as revised through Amendment No.
25, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall. operate the facility in accordance with the Technical Specifications and the Environmental Protection Dian.
3.
The license amendment is effective as of its date of issuance arJ to be implemented within 30 days of the'date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSIO WD Q
Suzanne C. Black, Direc or Project Directorate IV-2 Division of Reactor Projects - til/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 12, 1992 r
-.,.--,,,y
_. _. ~ - -
s alJA[HMENT TO LICENSE AMENDMENT NO. 25 FACILITY OPERATING LICENSE NO NPF-80 DOCKET NO. 50-499 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 2-4 4 B 2-4 B 2-4 3/4 3-2 3/4 3-2 3/4 3-9 3/4 3-9 3/4 3-11 3/4 3-11 l
-A, s%
- e
-n
,, _ _, _ ~,
SAEEILI.1MITS AND_ LIMITIRQ_3AFETY SYSTEM SETTINGS L2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
A_pPLICABILITY:
As shown for each channel in Table 3.3-1.
ACTION:
With a Reactor Trip System Instrumencation or Interlock Setpoint a.
less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the Setpoint consistent with the Trip Setpoint vane.
b.
With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Value column of Table 2.2-1, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 Z + R + S < TA Where:
1 = The value from Column 2 of Table 2.2-1 for the affected channel, R = The "as-measured" value (in percent span) of rack error for the affected channel, S = Either the "as-measured" value (in percent span) of the sensor error, or the value from Column S (Senar Error) of Table 2.2-1 for the affected channel, and TA = The value from Columh TA (Total Allowance) of Table 2.2-1 for the diected channel.
k SOUTH TEXAS - UNITS 1 & 2 2-3
m TABLE 2.2-1 wo REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS g
M TOTAL SENSOR y
ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE e
E 1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
N.A.
7-2.
Power Range, Neutron Flux a.
High Setpoint 7.5 4.56 0
$109% of RTP**
1111.3% of RTP**
e.
N b.
Low Setpoint 8.3 4.56 0
525% of RTP**
127.3% of RTP**
3.
Power Range, Neutron Flux, 1.6 0.5 0
<5% of RTP** with
<6.3% of RTP** with High Positive Rate i time constant i time constant 12 seconds 32 seconds 4.
Deleted 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
$105 cps
$1.4 x 105 cps 7.
Overtemperature AT 6.8 4.66 1.5 + 0.9#
See Note 1 See Note 2 l
8.
Overpower AT 5.5 1.74 1.5 See Note 3 See Note 4 gg 9.
Pressurizer Pressure-Low 3.1 0.71 2.0 11870 psig 11862 psig NN 10.
Pressurizer Pressure-High 3.1 0.71 2.0 12380 psig
$2388 psig l
l
" 7 11.
Pressurizer Water Level-High 5.0 2.76 2.0
$92% of instrument
$93.6% of instrument span span 12.
Reactor Coolant Flow-Low 4.0 3.19 0.6
>91.8% of loop
>90.9% of loop ll Besign flow
- Besign flow
- EE
- Loop design flow = 95,400 gpm oo
- RTP = RATED THERMAL POWER
- 1.5% span for AT: 0.9% span for Pressurizer Pressure 0$%
...ma-...a....-.
s-.. -.-....I -..
2.2 LIM 3 TING SAFEW SYSTEM SETTINGS flASES 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the nominal values at which the Reactor trips are set for each functional unit.
TM Trip Setpoints have been selected to ensure that the core and Reactor Coolans System are prevented from exceeding their safety limits during normal operation and design basis anticipated operational occurrences and to assist the Engi-neered Safety Features Actuation System in mitigating the consequences of 6ccidents.
The Setpoint for a Reactor Trip System or interlock function is considered to be adjusted consistent with the nominal value when the "as-measured" Setpoint is within the band allowed for calibration accuracy.
To accommodate the instrument drift assumed to occur between operational tests and the accuracy to which Setpoints can be measured and calibrated, Allowable Values for the Reactor Trip Setpoints have been specified in Table 2.2-1.
Operation with Setpoints less conservative than the Trip Set-point but within tne Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error.
An optional provision has been included for determining the OPERABILITY of a channel when its Trip Setpoint is found to exceed the Allowable Value.
The methodology of this option utilizes the "as measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical combi-natien of the other uncertainties of the instr uentation to measure the process varisble and the uncertainties in calibrating the instrumentation.
In Equa-tion 2.2-1, 2 + R + 5 < TA, the interactive effects of the errors in the rack i
and the sensor, and.the "as-measured" values of the errors are considered.
Z,
)
as specified in Table 2.2-1, in percent span, is the statistical summation of l
l errors assumed in the analysis excluding those associated with the sencor and rack drift cnd the accuracy of their measurement. TA or Tutal Allowance is the difference, in percent span, between the Trip Setpoint and the value used i
in the analysis for Reactor trip.
9 av Rau Error is the "as-measured" devia-tion, in percent sp e, for the affa.ted channel from the specified Trip Set-point.
S or Sensor Error is either the "as-measured" deviation of the sensor from its calibration point or the value specified in Table 2.2-1, in percent span, from the analysis assumptions.
Use of Equation 2.2-1 allows for a sensor drift factor and an increased rack drift factor, and provides a threshold value for REPORTM LE EVENTS.
The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels.
Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties.
Sensors and other instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes.
Rack drift in excess of the Allowable Value exhibits the behavior that the rack has not met its allowance.
Because there is a small statistical chance that this will happen, an infrequent excessive drift is expected.
Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of more serious problems and should warrant further investigation.
SOUTH TEXAS - UNITS 1 & 2 8 2-3
l l
LIMITING SAFETY SYSTEM SETTINGS i
BASES REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS'(Continued)
The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by.the Reactor Trip System reaches a preset or calculated level.
In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trip System functional diversity.
The functional 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 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 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 Range, Neutron Flux In each of the Power Range Neutron Flux-channels there are two independent bistablec, each with its own trip setting used for a High and Low Range trip setting.
The Low Setpoint trip provides protection during subcritical and low i
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 mitigate the. consequences of a reactivity excursion from all power levels.
The Low Setpoint trip may be manually blocked above P-10 (a power level-of approximately 10% of RATED THERMAL POWER) and is automatically reinstated below the P-10 Setpoint.
Power Range, Neutron Flux, High Rates The Power Range Positive Rate trip provides protection against rapid flux increases whic:h are characteristic of a rupture of a control rod drive housing.
Specifically, this trip complements the. Power Rang? Neutron Flux High and Low-trips to ensure that the criteria are met for rod ejection from mid power.
I l
l~
SOUTH-TEXAS-- UNITS 1 & 2 B 2-4 Unit 1 - Amendment No. 34' Unit 2 - Amendment No. 25 l
l 1
3/4.3 INSTRUMENTAT10N 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDIT10H_f0R OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.with RESPONSE TIMES as shown in Table 3.3-2.
i i
APPLICABILITY:
As shown in Table 3.3-1.
i ACTION:
As shown in Table 3.3-1.
i SURVEILLANCE R ULREMENTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of tne Reacter Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1.
4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number t
l of redundant channels in a specific Reactor trip function as shown in the j
" Total No. of Channels" column of Table 3.3-1.
i SOUTH TEXAS - UNITS 1 & 2 3/4 3-1
.i i
TABLE 3.3-1 m8y REtCTOR TRIP SYSTEM INSTRUMENTATION h
MINIMUM g
TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1.
1 2
1, 2 1
g 2
1 2
3*, 4 *, 5*
10
[
2.
Power Range, Neutron Flux a.
High Setpoint 4
2 3
1, 2 2
i y
b.
Low Setpoint 4
2 3
1###, 2 2
3.
Power Range, Neutron Flux 4
2 3
1, 2 2
High Positive Rate 4.
Deleted 5.
Intermediate Range, Neutron Flux 2
1 2
1###, 2 3
i 6.
Sourc'e Range, Neutron Flux a.
'Startup 2
1 2
2##
4 b.
Shutdown 2
1 2
3*, 4*, 5*
10 7.
Extended Range, Neutron Flux 2
0 2
3,4,5 4
8.
Overtemperature AT 4
2 3
1, 2 6
CC y h 9.
Overpower AT 4
2 3
1, 2 6
10.
Pressurizer Pressure--Low 4
2 3
1 6
(Interlocked with P-7)
Es
- Q Q 11.
Pressurizer Pressure--High 4
2 3
1, 2 6
xxEj'12.
Pressurizer Water Level--High 4
2 3
1 6
(Interlocked with P-7) 5.5
g TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES
--4W M
FUNCTIONAL UNIT RESPONSE TIME e
C 1.
Manual Reactor Trip N.A.
i'i I
d 2.
Power Range, Neutron Flux
$ 0.5 second*
w o.
3.
Power Range, Neutron Flux, High Positive Rate N.A.
so 4.
Deleted 5.
Intermediate Range, Neutron Flux N.A.
6.
Source Range, Neutron Flux
$ 0.5 second*
,s*
7.
Extended Range, Neutron Flux N.A.
Y 8.
Overtemperature AT
~< 8.0 secor4s*
i 9.
Overpower AT
$ 8.0 seconds
- j 10.
Pressurizer Pressure--Low
$ 2 seconds 11.
Pressurizer Pressure--High CC
-<-2 seconds D3pp 12.
Pressurizer Water Level--High 5 2 seconds i
ro w e e NN
&@
- Neutron detectors are exempt from response time testing.
Response time of the neutron flux signal portion
'g of the channel shall be.'easured from detector oO~put or input of first electronic component in channel.
g
.55
TABLE 3.3-2 (Continued) o, E
gj REACTOR TRIP SYSTEM INSTRUMENTATION RESIONSE TIMES M
k h!
FUNCTIONAL UNIT RESPONSE TIME E
13.
Reactor Coolant Flow--Low
'E Uf a.
Single Loop (Above P-8)
< 1 second b.
Two Loops (Above P-7 and below P-8) 31second I
e.
14.
Steam Generator Water Level--Low-Low i 2 seconds n,
15.
Undervoltage - Reactor Coolant Pumps 1 1.5 seconds
- 16. Underfrequency - Reactor Coolant Pumps 1 0.6 second w
3:
17.
w
,L a.
Low Emergency Trip Fluid Pressure N.A.
C' b.
Turbine Stop Valve Closure N.A.
18.
Safety Injection Input from ESFAS N.A.
19.
Reactor Trip System Interlocks N.A.
i 20.
Reactor Trip Breakers N.A.
- 21. Automatic Trip and Interlock Logic N.A.
O e
_ _ _ _ _ _ _ _ _ __.,.........i....
..P
8 TABLE 4.3-1 5
~
]
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE]UIREMENTS
[
s TRIP ANALOG ACTUATING MODES FOR E
CHANNEL DEVICE WHICH Z
CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE i
" FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED w 1.
Manual. Reactor Trip N.A.
N.A.
N.A.
R(14)
N.A. '
1, 2, 3*, 4*, 5*
}
2.
Power Range, Neutron Flux j
a.
High Setpoint S
D(2, 4),
Q(17)
N.A.
N.A.
1, 2 M(3,4),
l Q(4, 6),
j'
-R(4,Sa) t'
- b. -Low Setpoint S
R(4)
S/U(1)
N.A.
N.A.
1***,
2 e-3.
Power Range, Neutron N.A.
R(4)
Q(17)
N. A.
N.A.
1, 2 w
i L
1
- Flux,
'Higa Positive Rate 4.
Deleted
];
5.
Intermediate Range, S
R(4,Sa)
S/U(1)
N.A.
N.A.
1***,
2 Neutron Flux i
6.
Source Range, Neutron 5
R(4, Sa)
S/U(1),
c-3.
Flux-(Unit 1)
Q(9)(17)
N.A.
N. A.
2**, 3, 4, 5 4
e
' Source Rang, Neutron S
R(4,5b)
S/U(1),
i-m Flux (Unit 2)
Q(9)(17)
N.A.
N.A.
2**, 3, 4, 5
[
j F
7.
Extended Range, S
R(4)
Q(12, 17)
N.A.
N.A.
3,'4, 5 r
{
Neutron Flux j
8.
Overtemperature t.T S
R Q(17)
N.A.
N.A.
1, 2 1
9.
Overpower AT S
R Q(17)
N.A.
N.A.
1, 2 2
P 10.
Pressurizer Pressure
,j
--Low '
S R'
Q(17)
N.A.
N.A.
1 l
mw i
I TA8LE 4.3-1 (Continued) w 8
i l
M REACTOR TRIP SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREE NT$
1 O
i TRIP C
ANALOG CHANNEL ACTUATING MODES FOR DEVICE idHICH I
e CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE
'i
- 5. FUNCTIONAL UNIT
_C_WE#. -
CALIBRATION TEST TEST LOGIC TEST IS REQUIRED y
M
- 11. Pressurizer Pressure I
-High S
R W17)
N.A.
N.A.
1, 2 t
=
l
- 12. Pressuriier Water
[
i Level-Migh 5
R W17)
N.A.
N.A.
1 i
h
- 13. Reactor Coolant Flow
-Low i
R W17,18)
N. A.
N.A.
1 w2 4
l l
- 14. Steam Generator Water w
l 1
Level-Loir-Low 5
4 W17,18)
N. A.
N. A.
1, 2 l
t
=
i
- 15. Underveltage - Reacter I
l Coolant Pumps N.A.
W N.A.
W17)
N. A.
I
^
l 16.
L'nderfrequency -
Reactor Coolant Pumps N.A.
R N. A.
W17?
N.A.
I
[
~
f'
- 17. Turbine Trip-i' a.
Low L. r.aj N.A.
R N.A.
S/9(1,10)
- 2. A.
1
(
Trip Fluid Pressure i
b.
Tudine Step
- 3. A.
R N.A.
S/9(1,10)
N. A.
I i
i Valve Closure i
t i
18._ Safety injection N.A.
N.A.
N.A.
R N.A.
1, 2
[
i Input free ESFAS i
I i
j
[
t-
'