ML20236M638

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Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual
ML20236M638
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 07/06/1998
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20236M633 List:
References
NUDOCS 9807140172
Download: ML20236M638 (7)
v • d • e


Text

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. Attachment 4 ST-NOC-AE-000205 Annotated Technical Specifications and Bases Page1 I

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Annotated Technical Specification and Bases Pages i

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9907140172 990706 PDR ADOCK 05000499 P PDRy E__--__---___-__-_-__--------____----- -- A -- - - - - - - - _ - - - - - -

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVElltANCE RE0VIREMENTS SECTION P.!LGE 3/4.2 POWER DISTRIBUTION LIMITS -

3/4.2.1 AXIAL FL X DIFFERENCE ..'.................................... 3/4 2-1 FIGURE 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 2-9 3/4.2.4 QUADRANT POW 2R 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 l '

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS ............................................... 3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM

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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 (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 3-42 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Pl ant 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

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

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- INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PAGE

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2."': "^":T^^ " '"""""E"" 0" C'""' :' ' "?T :

N ......... . . . . . . . . . . . 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 INSTRUMENTS 10N . . . . . . . . . 3/4 3-68 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

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

3/4 3-75 TABLE 3.3-11 (This table number is not used) . . . . . . . . . . . 3/4 3-77 Radioactive Liquid Effluent Monitoring Instrumentation DELETED TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTAT TABLE 4.3-8 RADI0 ACTIVE 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 -

i SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . 3/4 3-82 3/4.3.4 TURBINE OVERSPEED PROTECTION . . . . . . . . . . . . . . . 3/4 3-84, SOUTH TEXAS - UNITS I & 2 vi Unit I - Amen'...it No. 47 Unit 2 - An..ndment No. 36 L_ - - - - - _ - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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APPLICABILITY: At all times.

, ACTION:

a. With one or more of the above required seismic monitoring instrume inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within e next 10 days outlining the cause of the malfunction and the p s for restoring the instrument (s) to OPERABLE status. This AC ON may 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 be demonstrated OPERABLE by the performance of the CHAN CHECK, CHANNEL CALI-BRATION, and ANALOG CHANNEL OPERATIONAL TEST at th. requencies shown in l Table 4.3-4.

1 4.3.3.3.2 Each of the above required seismi onitoring instruments actuated during a seismic event shall be restored to PERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and  ;

a CHANNEL CALIBRATION performed within 1 ays following the seismic event.

Data shall be retrieved from actuated truments and analyzed to determine the magnitude of the vibratory ground mo on. A Special Report shall be prepared and submitted to the Commission pu uatt to Specification 6.9.2 within 14 days l describing the magnitude, frequ y spectrum, and resultant effect upon facility features 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 Specifications meet 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 u----------------------------------------

J TABLE 3.3-7 7 SEISMIC MONITORING INSTRUMENTATION MINIMUM INSTRUMENTS 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 (Tendon Gallery E1. -36'9")

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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 Auxiliary Building El. 35'0")
2. Triaxial Peak Accelerographs
a. Spent Fuel Pool Heat Exchanger 3g 1 (Inlet Line Fuel Handling Building E1. 64'5k")
b. Reactor Vessel 13g 1 (Reactor Containment Building Eli 68'0")
c. Cold Leg of RC Piping 3g 1 (Reactor Containment Building E1. 34'3")
3. Self-Contained Triaxial Accelerograph 13g 1 (At Reactor Containment Building Foundation 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).
  1. Triaxial seismic switch is set at the OBE acceleration level of 0.05g ,

horizontal and 0.033g vertical.

    1. Triaxial seismic trigger is set at 0.02g all axes.

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

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Tn415 PA4F tWTENTISNALLY BLMK TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL INSTRUMENTS AND SENSOR LOCATIONS CHANNEL CHANNEL OPERATIONAL (Unit 1 only) CHECK CALIBRATION TEST

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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 SA Building (Mechanical Electrical Auxiliary Build!ng El. 35'0")
2. Triaxial Peak Accelerographs
a. Spent Fuel Pool Heat Exchanger N.A. R N.A.

(Inlet Line Fuel Handling Building E1. 64'5k")

b. Reactor Vessel N.A. R N.A.

(Reactor CMitainment Building E1. 68'0")

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

(Reactor Containment Building El. 34'3")

3. Self-Contained Triaxial Accelerograph M R SA (At Reactor Containment Building Foundation 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 in I Unit 2)
    • At seismic monitoring panel in Control Room, Unit 1
      • Accelerometer data is gathered and analyzed by the Response Spectrum Analyzer (Item 6).

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

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INSTRUMENTATION IlaS.ES_

3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

l ForthepurposeofmeasuringF(Z)orFfHafullincorefluxmapisused.

q Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux ma~ or symmetric incore thimbles may be used for monitoring the QUADRANT POWER 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 sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capa-bility is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100. The instrumentation is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earth-l quakes," April 1974. j 3/4.3.3.4 HETEOR0 LOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite meteorological Programs," Februar.v 1972.

l 3/4.3.3.5 REMOTE SHUTDOWN SYSTEM l The OPERABILITY of the Remote Shutdewn System ensures that sufficient capability is available to permit safe shutdown of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.

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7 SOUTH TEXAS - UNITS 1 & 2 8 3/4 3-4 I

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