Annotated Technical Specification and Bases Pages

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Attachment 4 ST-NOC-AE-000205*

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Annotated Technical Specifications and Bases Page1!

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Annotated Technical Specification and Bases Pages

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INDEX'

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LIMITING CONDITIONS FOR OPERATION AND SURVElltANCE RE0VIREMENTS

SECTIONP.!LGE

3/4.2 POWER DISTRIBUTION LIMITS -

3/4.2.1 AXIAL FL X DIFFERENCE ..'.................................... 3/4 2-1FIGURE 3.2.1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF

RATED THERMAL POWER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Del e t ed

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 2-93/4.2.4 QUADRANT POW 2R TILT RATIO . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 2-103/4.2.5 DNB PARAMETERS ............................................. 3/4 2-11

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3/4.3 INSTRUMENTATION

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION ........................ 3/4 3-1TABLE 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

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REQUIREMENTS ............................................... 3/4 3-113/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM

INSTRUMENTATION ............................................ 3/4 3-16~

TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM

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

INSTRUMENTATION TRIP SETPOINTS ............................. 3/4 3-29TABLE 3.3-5 (Th i s t abl e number not used) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-37 >

TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM

INSTRUMENTATION SURVEILLANCE REQUIREMENTS .................. 3/4 3-423/4.3.3 MONITORING INSTRUMENTATION

Radiation Monitoring for Pl ant Operations . . . . . . . . . . . . ... . . . . 3/4 3-50TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION

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

OPERATIONS SURVEILLANCE REQUIREMENTS ....................... 3/4 3-53Movabl e Incore Detectors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-54'......[.......~.......................................... :|' : :: -

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SOUTH TEXAS - UNITS 1 & 2 v Unit 1 - Amendment No. N, 50Unit 2 - Amendment No. H , 39

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INDEX-.

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS

SECTIONPAGE -

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. . . . . . . . . . . 3/4 3-57Meteorological Instrumentation

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TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION. . . . . . 3/4 3-59

TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCEREQUIREMENTS

. . . . . . . . . . . . . . . . . . . . . . 3/4 3-60Remote Shutdown System

. . . . . . . . . . . . . . . . . 3/4 3-61TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM . . . . . . . . . . . . . . . . 3/4 3-62

TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATIONSURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . 3/4 3-66Accident Monitoring Instrumentation . . . . . . . . . . . 3/4 3-67

TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTS 10N . . . . . . . . . 3/4 3-68

TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCEREQUIREMENTS

. . . . . . . . . . . . . . . . . . . . . . 3/4 3-73Chemical Detection Systems ^

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TABLE 3.3-11 (This table number is not used) . . . . . . . . . . . 3/4 3-77Radioactive Liquid Effluent Monitoring Instrumentation

DELETED

TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION DELETED

TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIONSURVEILLANCE 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 -

i SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . 3/4 3-82

3/4.3.4 TURBINE OVERSPEED PROTECTION . . . . . . . . . . . . . . . 3/4 3-84,

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SOUTH TEXAS - UNITS I & 2 vi Unit I - Amen'...it No. 47Unit 2 - An..ndment No. 36

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APPLICABILITY: At all times.'

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a. With one or more of the above required seismic monitoring instrumeinoperable for more than 30 days, prepare and submit a SpecialReport to the Commission pursuant to Specification 6.9.2 within enext 10 days outlining the cause of the malfunction and the p sfor restoring the instrument (s) to OPERABLE status. This AC ONmay be applicable to both units simultaneously.

b. The provisions of Specification 3.0.3 are not applicab .

SURVEILLANCE REQUIREMENTS

4.3.3.3.1 Each of the above required seismic monitori instruments shall bedemonstrated OPERABLE by the performance of the CHAN CHECK, CHANNEL CALI-BRATION, and ANALOG CHANNEL OPERATIONAL TEST at th. requencies shown in

| Table 4.3-4.1

4.3.3.3.2 Each of the above required seismi onitoring instruments actuatedduring a seismic event shall be restored to PERABLE status within 24 hours and

;a CHANNEL CALIBRATION performed within 1 ays following the seismic event.Data shall be retrieved from actuated truments and analyzed to determine themagnitude of the vibratory ground mo on. A Special Report shall be preparedand submitted to the Commission pu uatt to Specification 6.9.2 within 14 days,

| describing the magnitude, frequ y spectrum, and resultant effect upon facilityfeatures important to safety.

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)e instrumentation may be shared with additional units at a common site^

provided seismic instrumentation and corresponding Technical Specificationsmeet the recommendations of Regulatory Guide 1.12, Revision 1, April 1974.

50llTH TEXAS - UNITS 1 & 2 3/4 3-55 Unit I - Amendment No. 4

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TABLE 3.3-7 7SEISMIC MONITORING INSTRUMENTATION-

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MINIMUMINSTRUMENTS AND SENSOR LOCATIONS MEASUREMENT INSTRUMENTS(Unit 1 only) RANGE OPERABLE |

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1. Triaxial Time-History Accelerometers ***,

a. Free Field 13g 1'

b. Containment Bldg. Foundation 13g 1 )(Tendon Gallery E1. -36'9") i

c. Outside Face Containment Shell 13g 1(Reactor Containment Building El. 68'0")

d. Steam Generator Upper Lateral Support 13g 1(Reactor Containment Building El. 66'7 ")

e. Fuel Handling Building Foundation i3g 1(Fuel Handling Building El. -29'0")

f. Mechanical Electrical Auxiliary Building 13g 1(Mechanical Electrical AuxiliaryBuilding El. 35'0")

2. Triaxial Peak Accelerographsa. Spent Fuel Pool Heat Exchanger 3g 1

(Inlet Line Fuel Handling BuildingE1. 64'5k")

b. Reactor Vessel 13g 1(Reactor Containment Building Eli 68'0")

c. Cold Leg of RC Piping 3g 1(Reactor Containment BuildingE1. 34'3")

3. Self-Contained Triaxial Accelerograph 13g 1(At Reactor Containment BuildingFoundation Tendon Gallery El. -36'9")

4. Triaxial Seismic Switch * ** # 0.03 to 3g 1

5. Triaxial Seismic Trigger * ** ## 0.003 to 0.3g 1

6. Response Spectrum Analyzer * ** 1 to 32 Hz 1

7. Magnetic Tape Recorders ** 0.1 to 33 Hz 6

8. Playback System ** N.A. 1

*With reactor control room indication and alarm in Unit 1 (Alarm only in,

Unit 2) I'

**At seismic monitoring panel in Control Room, Unit 1*** Accelerometer data is gathered and analyzed by the Response Spectrum

Analyzer (Item 6).# Triaxial seismic switch is set at the OBE acceleration level of 0.05g

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horizontal and 0.033g vertical.## Triaxial seismic trigger is set at 0.02g all axes.

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SOUTH TEXAS - UNITS 1 & 2 3/4 3-56 Unit.1 - Amendment No. 4

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TABLE 4.3-4*

SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

ANALOGCHANNEL

INSTRUMENTS AND SENSOR LOCATIONS CHANNEL CHANNEL OPERATIONAL(Unit 1 only) CHECK CALIBRATION TEST {1. Triaxial Time-History Accelerometers ***

a. Free Field M R SA

b. Containment Bldg. Foundation M R SA(Tendon Gallery El. -36'9")

c. Outside Face Containment Shell M R SA(Reactor Containment Building E1, 68'0")

d. Steam Generator Upper Lateral Support M R SA(Reactor Containment Building El. 66'7 ")

e. Fuel Handling Building Foundation M R SA(Fuel Handling Building E1. -29'0")

f. Mechanica) Electrical Auxiliary M R SABuilding (Mechanical ElectricalAuxiliary Build!ng El. 35'0")

2. Triaxial Peak Accelerographsa. Spent Fuel Pool Heat Exchanger N.A. R N.A.

(Inlet Line Fuel Handling BuildingE1. 64'5k")

b. Reactor Vessel N.A. R N.A.(Reactor CMitainment BuildingE1. 68'0")

c. Cold Leg of RC Piping N.A. R N.A.

(Reactor Containment BuildingEl. 34'3")

3. Self-Contained Triaxial Accelerograph M R SA'

(At Reactor Containment BuildingFoundation Tendon Gallery E1. -36'9")

4. Triaxial Seismic SwitcS* ** M R SA'

5. Triaxial Seismic Trigger * ** M R SA

6. Response Spectrum Analyzer * ** M R SA

7. Magnetic Tape Recorders ** M R SA

8. Playback System ** M R N.A.,

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*With reactor control room indication and alarm in Unit 1 (Alarm only inI Unit 2)

**At seismic monitoring panel in Control Room, Unit 1*** Accelerometer data is gathered and analyzed by the Response Spectrum

Analyzer (Item 6).

| SOUTH TEXAS - UNITS 1 & 2 3/4 3-57 Unit 1 - Amendment No. 4 I

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INSTRUMENTATION*

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3/4.3.3.2 MOVABLE INCORE DETECTORS

The OPERABILITY of the movable incore detectors with the specified minimumcomplement of equipment ensures that the measurements obtained from use ofthis system accurately represent the spatial neutron flux distribution of thecore. The OPERABILITY of this system is demonstrated by irradiating eachdetector used and determining the acceptability of its voltage curve.

| ForthepurposeofmeasuringF(Z)orFfHafullincorefluxmapisused.qQuarter-core flux maps, as defined in WCAP-8648, June 1976, may be used inrecalibration of the Excore Neutron Flux Detection System, and full incore'

flux ma~ or symmetric incore thimbles may be used for monitoring the QUADRANTPOWER TILT RATIO when one Power Range channel is inoperabic.

3/4.3.3.3 6EMWNMNGEiniWiiNEHGE (MQT @

f The OPERABILITY of the seismic instrumentation ensures that sufficientcapability is available to promptly determine the magnitude of a seismic eventand evaluate the response of those features important to safety. This capa-bility is required to permit comparison of the measured response to that usedin the design basis for the facility to determine if plant shutdown is requiredpursuant to Appendix A of 10 CFR Part 100. The instrumentation is consistent

| with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earth-'

quakes," April 1974. j3/4.3.3.4 HETEOR0 LOGICAL INSTRUMENTATION

The OPERABILITY of the meteorological instrumentation ensures thatsufficient meteorological data are available for estimating potential radiationdoses to the public as a result of routine or accidental release of radioactivematerials to the atmosphere. This capability is required to evaluate the needfor initiating protective measures to protect the health and safety of thepublic and is consistent with the recommendations of Regulatory Guide 1.23,"Onsite meteorological Programs," Februar.v 1972.

| 3/4.3.3.5 REMOTE SHUTDOWN SYSTEM

| The OPERABILITY of the Remote Shutdewn System ensures that sufficient'

capability is available to permit safe shutdown of the facility from locationsoutside of the control room. This capability is required in the event controlroom habitability is lost and is consistent with General Design Criterion 19of 10 CFR Part 50. ~

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SOUTH TEXAS - UNITS 1 & 2 8 3/4 3-47

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