ML20045A466

Corrected Tech Spec Pages to Amends 50 & 39 to Licenses NPF-76 & NPF-80,respectively.TS Previously Issued W/Amends, Were Inadvertently Copied on One Side Only

ML20045A466
Person / Time
Site:	South Texas
Issue date:	05/25/1993
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20045A467	List: ML20045A466
References
NUDOCS 9306100343
Download: ML20045A466 (16)

Text

..

INDEX s

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EAG[

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE...................................... 3/4 2-1 FIGURE 3.2.1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER......................................... Deleted 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F,(Z)....................... 3/4 2-5 FIGURE 3.2-2 K(Z) - NORMALIZED F,(Z) AS A FUNCTION OF CORE HEIGHT.... Deleted 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR................... 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO.................................. 3/4 2-10 3/4.2.5 DNB PARAMETERS............................................. 3/4 2-11 3 /4. 3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION........................ 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION.....................

3/4 3-2 TABLE 3.3-2 (Thi s tabl e number not used)............................ 3/4 3-9 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................................

3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............................................

3/4 3-16 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............................................

3/4 3-18 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS............................. 3/4 3-29 TABLE 3.3-5 (Thi s tabl e number not used)............................

3/4 3-37 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS..................

3/4 3-42 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations..................

3/4 3-50 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS....................................... 3/4 3-51 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS....................... 3/4 3-53 Movabl e Incore Detectors................................... 3/4 3-54 Seismic Instrumentation.................................... 3/4 3-55 TABLE 3.3-7 SEISMIC HONITORING INSTRUMENTATION...................... 3/4 3-56 SOUTH TEXAS - UNITS I & 2 v

Unit 1 - Amendment No. B7, 50 Unit 2 - Amendment No. +7, 39 9306100343 930525 PDR ADOCK 05000498 p

PDR

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATIOT 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 Chapter 16 in the Updated Final Safety Analysis Report (UFSAR).

APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVElllANCE RE0VIREMENTS 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 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 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.

i 1

50'JTH TEXAS - UNITS 1 & 2 3/4 3-1 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 39

INDEX o

LIMITING CONDITIONS FOR OPERATION AND SURVElllANCE REQUIREMENTS SECTION

.P_A.G1 G

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE...................................... 3/4 2-1 FIGURE 3.2.I AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER......................................... Deleted 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F,(Z)....................... 3/4 2-5 FIGURE 3.2-2 K(Z) - NORMALIZED F,(Z) AS A FUNCTION OF CORE HEIGHT.... Deleted 3/4.2.3 NUCLEAR ENTHALPY RISE H0Y CHANNEL FACTOR................... 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO.................................. 3/4 2-10 3/4.2.5 DNB PARAMETERS............................................. 3/4 2-II 3 /4. 3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION........................

3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION.....................

3/4 3-2 TABLE 3.3-2 (This table number not used)............................

3/4 3-9 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................................

3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............................................

3/4 3-16 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION...........................................

3/4 3-18 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS.......................'......

3/4 3-29 TABLE 3.3-5 (This table number not used)............................

3/4 3-37 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEIL LANCE REQUIREMENTS..................

3/4 3-42 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations.................. 3/4 3-50 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION i

FOR PLANT OPERATIONS....................................... 3/4 3-51 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS.......................

3/4 3-53 Mova bl e Incore Detectors................................... 3/4 3-54 Seismic Instrumentation.................................... 3/4 3-55 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION......................

3/4 3-56 SOUTH TEXAS - UNITS I & 2 v

Unit I - Amendment No. N, 50 Unit 2 - Amendment No. H, 39 9306100343 930525 PDR ADOCK 05000498 p

PDR

)

i i

i IND~X LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS j

SECTION EMif TABLE 4.3-4 SEISHIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-57 Meteorological Instrumentation.............

3/4 3-58 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION......

3/4 3-59 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-60 Remote Shutdown System.................

3/4 3-61 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM................

3/4 3-62 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-66 Accident Monitoring Instrumentation...........

3/4 3-67 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.........

3/4 3-68 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................

3/4 3-73 Chemical Detection Systems 3/4 3-75 TAB'.E 3.3-11 (This table number is not used)...........

3/4 3-77 Radioactive Liquid Effluent Monitoring Instrumentation

, DELETED TABLE 3,3-12 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION DELETED TABLE 4.3-8 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DELETED Explosive Gas Monitoring Instrumentation........

3/4 3-79 TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION......

3/4 3-80 TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.....'...........

3/4 3-82 3/4.3.4 TURPINE OVERSPEED PROTECTION...............

3/4 3-84 SOUTH TEXAS - UNITS 1 & 2 vi Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36 e --

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 Chapter 16 in the Updated Final Safety Analysis Report (UFSAR).

APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE RE0VIREMENTS 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 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 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 i

SOUTH TEXAS - UNITS 1 & 2 3/4 3-1 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 39 i

TABLE 3.3-1 8$

REACTOR TRIP SYSTEM INSTRUMENTATION m

MINIMUM h

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1.

Manual Reactor Trip 2

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

b.

Low Setpoint 4

2 3

1#N, 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#N, 2 3

6.

Source Range, Neutron Flux a.

Startup 2

1 2

2N 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 g %

9.

Overpower AT 4

2 3

1, 2 6

" " 10.

Pressurizer Pressure--Low 4

2 3

1 6

(Interlocked with P-7)

Qg" 11.

Pressurizer Pressure--High 4

2 3

1, 2 6

x1

• 3 12.

Pressurizer Water Level--High 4

2 3

1 6

2 (Interlocked with P-7)

5. 5

TABLE 3.3-2 (This table number not used)

SOUTH TEXAS - UNITS 1 & 2 3/4 3-9 Unit 1 - Amendment No. 34,50 Unit 2 - Amendment No. 45,39

D l

TABLE 3.3-2 (Continued)

(This table number not used) 1 1

l l

l SOUTH TEXAS - UNITS 1 & 2 3/4 3-10 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 39 t-

TABLE 4.3-1 (Continued)

TABLE NOTATIONS (Continued)

(10) Setpoint verification is not applicable.

(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(12) OPERABILITY shall be verified by a check of memory devices, input ac-curacies, Boron Dilution Alarm setpoints, output values, and software functions.

(13)

(Not used)

• (14) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the l

OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

(15) local manual shunt trip prior to placing breaker in service.

(16) Automatic undervoltage trip.

(17)

Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.

(18) The surveillance frequency and/or MODES specified for these channels in Tacle 4.3-2 are more restrictive and, therefore, applicable.

l

• Complete verification of operability of the shunt trip relay circuitry shall be initially implemented for each unit prior to the affected unit's startup from the first planned or unplanned shutdown occurring after May 19, 1992.

SOUTH Tens - UNITS 1 & 2 3/4 3-15 Unit 1 - Arens.,ent No. 37 Unit 2 - Amendment No. 28

INSTRUMENTATION J.f4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION tIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be GPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Chapter 16 in the UFSAR.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a.

With an ESFAS Instrumentation or Interlock Trip Setpoint trip 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 3.3-4, adjust the Setpoint consistent with the Trip Setpoint

value, b.

With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Allowable Value column of Table 3.3-4, either:

1.

Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-4, 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 s&tisfied for the affected channel, or 2.

Declare the channel inoperable and apply the applicable ACTION statement requirements of Table 3.3-3 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 s TA Where:

2 The value from Column 2 of Table 3.3-4 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 3.3-4 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 3.3-4 for the affected channel.

c.

With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-16 Unit 1 - Amendment No.50 Unit 2 - Amendment No.39

1

-INSTRUMENTATION SURVEILLANCE RE0VIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the. automatic acutation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in-Table 4.3.2.

4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function I

shall be demonstrated to be within the limit at least once per 18 months. - Each i

test shall include at least one train so that:

=

a.

Each logic train is tested at least once per 36 months, b.

Each actuation train is tested at least once per 54 months *, and c.

One channel per function so that all channels are tested at least once per N times 18 months where N is the total number of redundant

~

channels in a specific ESFAS function as shown in the " Total No. of' Channels" column of Table 3.3-3.

1 I

• If an E5FAS instrumentation channel is inoperable due to response times exceeding the required limits, perform an engineering evaluation to determine if the test failure is a result of degradation of the actuation relays.

If degradation of the actuation relays is determined to be the cause, increase the ENGINEERED SAFETY FEATURES ~ RESPONSE TINE surveillance frequency such that all trains are tested at least once per 36 months.

i SOUTH TEXAS - UNITS 1 & 2 3/4 3-17 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 39 i

s v

TABLE 3.3-3 ENGINEERED SAILTY IIATURf5 ACTUATION SYSTEM INSTRUMENTATION m

h MINIMUM TOIAL NO.

CilANNELS CilANNELS APPLICABLE e FUNCTIONAL UNIT OF CllANNEI5 5

~

10 TRIP OPERABLE MODES ACTION d

1.

Safety Injection (Reactor Trip, Feedwater Isolation, Control Room Emergency e.

Ventilation, Start Standby m

Diesel Generaters, Reactor Containment Fan Coolers, and Essential Cooling Water).

a.

Manual Initiation 2

1 2

1,2,3,4 19 w

b.

Automatic Actuation g

logic 2

1 2

1,2,3,4 14 c.

Actuation Relays 3

2 3

1,2,3,4 14 d.

Containment 3

2 2

1,2,3,4 15 Pressure--High-1 e.

Pressurizer 4

2 3

1, 2, 3#

20

{

Pressure--Low F

f.

Compensated Steam 3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

15 Line Pressure-Low any steam line in each steam g

line A

M l

)

h

.s TABLE 3.3-5 (This table number not used) h v

SOUTH TEXAS - UNITS 1 & 2 3/4 3-37 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 39

.o TABLE 3.3-5 (Continued) 4 (This table number not used)

SOUTH TEXAS - UNITS 1 & 2 3/4 3-38 Unit 1 - Amendment No. 4, 50 Unit 2 - Amendment No. 39

s 5

TABLE 3.3-5 (Continued)

(This table number not used) 1 i

SOUTH TEXAS - UNITS 1 & 2 3/4 3-39 Unit 1 - Amendment No. 50 l

Unit 2 - Amendment No. 39

i TABLE 3.3-5 (Continued) e (This table number not used) d 1

SOUTH TEXAS - UNITS 1 & 2 3/4 3-40 Unit 1 - Amendment No. I, ', 50 Unit 2 - Amendment No. 39 j

1

g&

TABLE 3.3-5 (Continued)

(This table number not used) l i

,i SOUTH TEXAS - UNITS 1 & 2 3/4 3-41 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 39

TABLE 4.3-7 O

$f ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVLILLANCL REQUIREMLN(S

_4 m

hk OlGITAL OR TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH c_

35 CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

-; rVNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED ~

l

1. Safety Injection (Reactor Trip, Feedwater Isolation, Control Room Emergency Ventilation, Start Standby Diesel Generators.' Reactor Containment Fan Coolers, and Essentiai Cooling Water) s

((

a. Manual Initiation N.A.

N.A.

N.A.

R N.A.

N.A.

N.A.

1,2,3,4 9

$5

b. Automatic Actuation N.A.

N.A.

N.A.

N.A.

M(1)

N.A.

N.A.

1,-2, 3, 4 Logic

c. Actuation Relays N.A.

N.A.

N.A.

N.A.

M.A.

M(6)

Q(4,5) 1, 2, 3, 4

![

d. Containment Pressure-S R

M

.N.A.

N.A.

N.A.

N.A.

1, 2,'3, 4 High-1

~

e. Pressurizer Pressure-S R

M N.A.

N.A.

N.A.

N.A.

1, 2,'3 y

low e

E

f. Compensated Steam Line S R

M N.A.

N.A.

N.A.

'N.A.

1, 2, 3 Pressure-Low r

NO i

4 I

1

'i

.l t'

r

.