ML20126F575

Amends 47 & 36 to Licenses NPF-76 & NPF-80,respectively, Changing App a TS by Incorporating Programmatic Controls for Radiological Effluents & Radiological Environ Monitoring in Administrative Controls Section

ML20126F575
Person / Time
Site:	South Texas
Issue date:	12/21/1992
From:	Black S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126F577	List: ML20126F575 ML20126F579
References
NUDOCS 9212300411
Download: ML20126F575 (53)

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- UNITED STATES F

E NUCLEAR REGULATORY COMMISSION 1 I

WASHINGTON, D.C. 20666 =

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HOUSTON LIGHTING & POWER COMPANY-CITY'PUBLIC SERVICE BOARD OF-SAN ANTONIO.

CENTRAL POWER AND LIGHT-COMPANY CITY OF AUSTIN. TEXAS.

DOCKET'NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE

. Amendment No.T47 License No. NPF 76.

1.

The Nuclear Regulatory Commission-(the Commission). has found that:L 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' June 26, 1991,.

as: supplemented-by. letters dated January 24,:1992 and June 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 set forth in 10 CFR Chapter I; B.

The facility will operate 11n conformity with the-application, 'as amended, the-provisions of. the: Act, and the rules and regulations ofJ -

the Commission;--

C.

There is reasonable assurance: -(i) thatLthe activities authorized by--

this-amendmentLean be conducted without endangering the health and ~

safety of the public, :and (ii) that such 'a'ctivities will_.be conducted inL eompliance.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-Service Board of San Antonio, Central Power and Light Company and City of L

Austin, Texas 'and has exclusive responsibility;and control over the physical Lconstructionnoperation and maintenance of the facility.

9212300411'921221 PDR :ADOCKj05000498

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. 2.

Accordingly, the license is amended by changes to the Technical.

Specifications 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. 47, 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 to be implemented within 15 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION m

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Suzanne'C. Black, Director Project Directorate IV-2 Division of Reactor Projects III/lV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

December 21, 1992

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'6 UNITED STATES I

1 NUCLEAR REGULATORY COMMISSION

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W ASHINGTON, D, C. 20555 S

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110VSTON 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 FACILITY OPERATING LICENSE Amendment No. 36 License No. NPF-80 1.

The Nuclear Regulatory Commission (the Comission) 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 June 26, 1991,-

as supplemented by letters dated January 24, 1992 and June 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 set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations;-

D.

The issuance of this license amendment will not be inimical to the comon 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 Comission'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 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.

" 2.

Accordingly, the license is amended by changes to the Technical Specifications 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 Specifications The Technical Specifications contained in Appendix A, as revised' through Amendment No. 36, 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 to be implemented within 15 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION q

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Suzanne"C. Black, Director Project Directorate IV-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 21, 1992

ATTACHMENT TO LICENSE AMENDMENT NOS. 47 AND 36 FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS. 50-498 AND 50-499 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

EMQVI INSERT 11 11 vi vi xi xi xii xii xvi xvi xix xix XX Xx l-4 1-4 1-5 1-5 1-6 1-6 1-7 1-7 3/4'3-36 3/4 3-36 3/4 3-79 3/4 3-80 3/4 3-81 3/4 3-82 3/4 3-83 3/4 3-84 3/4 3-79 3/4 3-85 3/4 3-80 3/4 3-86 3/4 3-81 3/4 3-87 3/4 3-82

-3/4 3-88 3/4 3-83 3/4 3-89 (Unit 1) 3/4 3-84 (Unit 1) 3/4 3-89 (Unit 2) 3/4 3-84 (Unit 2) 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-4 3/4 11-1 3/4 11-5 3/4 11-6 3/4 11-7 3/4 11-8 3/4 11-9 3/4 11-2 3/4-11-10 3/4 11-3 3/4 11-11 3/4 11-12 3/4 11-13 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-3

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4 INDEX -

1.0 DEFINITIONS SECTION PAGE 1.1 CTION........................................................

1-1 A

1.2 ACTUATION LOLIC TE5T......

1-1 1.3 ANALOG CHANNEL OPERATIONAL TE5T...............................

1-1 1.4 AXIAL FLUX DIFFERENCE.........................................

1-1 1.5 CHANNEL CALIBRATION...........................................

1-1 1.6 CHANNEL CHECK.................................................

1-1 1.7 CONTAINMENT INTEGRITY.........................................

1-2

1. 8 CONTROLLED LEAKAGE............................................

1-2 1.9 CORE ALTERATIONS..............................................

1-2 1.9a CORE OPERATING LIMITS REP 0RT..................................

1-2 1.10 DIGITAL CHANNEL OPERATIONAL TE5T..............................

1-2 1.11 DOSE EQUIVALENT I-131.........................................

1-2 1.12 E-AVERAGEDISINTEGRATIONENERGY...............................

1-3 1.13 ENGINEERED SAFETY FEATURES RESPONSE TIME......................-

1-3 1.14 FREQUENCY N0TATION............................................

1-3 1.15 GASEOUS WA5TE PROCESSING SY5 TEM...............................

1-3 1.16 I D E N T I F I E D L E A KAG E............................................

1-3 1.17 MASTER RELAY TE5T.............................................

1-4 1.18 MEMBER (5) 0F THE PUBLIC.......................................

1-4 1.19 0FFSITE DOSE CALCULATION MANUAL...............................

1-4 1.20 O P E RAB LE - O P E RABI LITY........................................

1-4 1.21 O P E R AT I O N A L MOD E - M0D E.......................................

1-4 1.22 PHYSICS TEST5.................................................

1-4 1.23 PRESSURE BOUNDARY LEAKAGE.....................................

1-4 1.24 PROCESS CONTROL PR0 GRAM.......................................

1-5 1.25 PURGE - PURGING.................'..............................

1-5 1.26-QUADRANT POWER; TILT RATI0.....................................

1-5 1.27 RATED THERMAL P0WER...........................................

1-5 l-SOUTH TEXA5 - UNITS 1 & 2 i

Unit 1 - Amendment No. 9 t

L Unit 2 - Amendment No. 1 i

I

INDEX DEFINITIONS SECTION PJ.QI 1.28 REACTOR TRIP SYSTEM RESPONSE TIME...

............ 1 1.29 REPORTABLE EVENT.......................-1-5 l'.30 ' SHUTDOWN MARGIN..............

...-...... 1-5 1.31 SITE BOUNDARY......................... 1-6 l.32 SLAVE RELAY TEST

.............-,......... 1-6

-1.33 DELETED 1.34 ' SOURCE CHECK......................

=,.11-6 1.35 STAGGERED TEST BASIS

.-1-6 1.36 THERMAL POWER..............,,.........

1-6

=

1-6 1.37 TRIP ACTUATING DEVICE _ OPERATIONAL TEST 1.38-UNIDENTIFIED LEAXAGE-............-........

11 1,39 UNRESTRICTED AREA....................... 1-6 l

1.40 VENTING...........................

1-7 TABLE 1.1 FREQUENCY NOTATION _.............._..

... 1-8 TABLE 1.2 OPERATIONAL-MODES

........ 1.

SOUTH TEXAS - UNITS 1.&:2 11-Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36

k INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2,1 AXIAL FLUX DIFFERENCE.....................................

3/4 2-1 FIGURF. 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL P0WER......................................

Deleted l

3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F (2).....................

3/4 2-5 q

FIGURE 3.2-2 K(Z) - NORMALIZED F (Z) AS A FUNCTION OF CORE HEIGHT.

Deleted l-g 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR.................

3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATI0................................

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 REACTOR TRIP SYSTEM-INSTRUMENTATION RESPONSE TIMES....

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 SETP0!NTS...........................

3/4 3-29 TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES.............

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 t-

- 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 Movable Incore Detectors.................................

3/4-3-54 l

Seismic Instrumentation..................................

3/4 3-55 I

TABLE-3.3-7 SEISMIC MONITORING INSTRUMENTATION....................

3/4 3-56 l-L

- SOUTH TEXAS - UNITS 1 & 2 v

Unit 1 - Amendment No. 27 Unit 2 - Amendment No. 17 l

L

4 E!DU l_lMITING CONDITIONS FOR OPERATI0ff At1D SURVfill ANCE Rf 0VIREMf f4TS 1f.C11011 IME TABLE 4.3-4 SEISMIC MNITOR!i1G lilS1RUMENTATION SURVEILLAllCE

}

REQUIRLiiEriTS 3/4 3-57 Meteorological Instrumentation 3/4 3-58 TABLE 3.3-8 METEOROLOGICAL MONITORll1G INSTRUMEllTATION 3/4 3-59 t

TABLE 4.3-5 METEOROLOGICAL M0lllTORING INSTRUMEllTATION SURVEILLANCE

}

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

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

3/4 3-62 i

TABLE 4.3-6 REMOTE SHUTDOWN MONITORING lilSTRUMENTATION 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 TABLE 3.3-11 (This table number is not used)...........

3/4 3-77 Radioactive Liquid Effluent Monitoring Instrumentation DELETED

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TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION DELETED 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 SURVEILLANCE REQUIREMENTS................

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

3/4 3-84 r

SOUTH TEXAS - UNITS 1 & 2 vi Unit 1 - Amendment No. 47 l

Unit 2 - Amendment No. 36 l

W INDEX t IMITitJG C0t1DITiotis FOR OPERATION AtJD SURVfit L At4Cf REQUIREMENTS 1EIl103 fMI 3/4.9.11 WATER LEVEL - STORAGE POOLS Spent f uel Pool.....................

3/4 9-12 In-Containment Storage Pool...............

3/4 9-13 3/4 9.12 FUEL llAllDLING BUILDING EXHAUST AIR SYSTEM........

3/4 9-14 3/4.9.13 SPElli FUEL POOL MINIMUM BORON C0!1CENTRAT10!1.......

3/4 9-17 3/4.10 SPECIAL T QT EXCEPT103 3/4.10.1 SHUIDOWil MARGIN.....................

3/4 10-1 3/4.10.2 GROL? HEIGHT, INSERT 10fi, AND POWER DISTRIBUT10!1 LIMITS 3/4 10-2 3/4.10.3 PHYSICS T ESTS......................

3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS..................

3/4 10-4 3/4 10.5 POSIT 10fi lilDICATION SYSTEM - SHUTDOWN..........

3/410-5 3/4.11 RADIDACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUEllTS Concentration DELETED Dose DELETED Liquid Waste Processing System DELETED Liquid Holdup Tanks.................,.

3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS Dose Rate DELETED Dose - Noble Gases DELETED Dose - lodine-131, lodine-133. Tritium, and Radioactive Material in Particulate form DELETED Gascous Waste Processing System DELETED Explosive Gas Mixture..................

3/4 11-2 Cas Storage Tanks....................

3/4 11-3 3/4.11.1 SOLID RADIDACTIVE WASTES DELETED 3/4.11.4 TOTAL DOSE DELETED SOUTH TEXAS - UNITS 1 & 2 xi Unit 1 - Amendment No. 43, 47 Unit 2 - Amendment No. BB, 36

it&lX llMITING C0flDIT10NS FOR 0PERATION AND SURVElllANCE REQUIREMENTS SECTION pffi 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING............

3/4 12-1 3/4.12.1 MONITORING PROGRAM DELETED 3/4.12.2 LAND USE CENSUS DELETED 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM DELETED SOUTH TEXAS - UNITS 1 & P.

xii Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36

IliDil BASES fMI I

SECTION 3/4.7.10 SEALED SOURCE CONTAMINATION........................... B 3/4 7-6 3/4.7.11 (Not used) 3/4.7.12 (Not used)

B 3/4 7-6 3/4.7.13_

AREA T EMPERATURE MONIT ORING............................

B 3/4 7 6 3/4.7.14 ESSENTIAL Chill.ED WATER SYSTEM.........................

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and B 3/4 B-1 DNSIT E POWER DI ST RIBUT ION.............................

3/4.B.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................ B 3/4 B-3 3/4.9 REFUELING OPERATIONS B 3/4 9-1 3/4.9.1 BORON CONCENTRATION....................................

B 3/4 9-1 l

3/4.9.2 INSTRUMENTATION........................................

1 B 3/4 9-1 3/4.9.3 DECAY TlHE.............................................

3/4.9.4 CONTAINHENT BUILDlHG PENETRAT IONS...................... B B 3/4 9-1 3/4.9.5 COMMUNICATIONS.........................................

3/4.9,6 REFUELING MACHINE......................................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING.................. B 3/4 9 3/4.9.B RESIDUAL HEAT REMOVAL AND COOLANT-CIRCULATION.......... B 3/4 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM...............

B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REFUELING CAVITY andB 3/4 9 STORAGE POOLS..........................................

3/4.9.12 FUEL HANDLING BUILDING EXHAUST AIR SYSTEM.............. B 3/4 9-3 3/4.9.13 SPENT FUEL POOL HINIMUM BORON CONCENTRATION............ B 3/4 9 3/4.10 SPECIAL TEST EXCEPTIONS

-3/4.10.1 SHUTDOWN MARGIN........................................ B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LlHITS..B 3/4.10-1 B 3/4 10-1 3/4.10.3 PH Y S I C S T E ST S.........................................

3/4.10,4 REACTOR COOLANT LOOPS.................................-

B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN.................-

B 3/4 10-1..

l Unit 1. Amendment No. - 43 SOUTH TEXAS - UNITS 1 & 2 xv Unit 2 - Amendment' No.- 32 l

l l

9 l@fl BASES SECTION PADI 3/4.11 RADIDACTIVE EFFLUENTS B 3/4 11-1 3/4.11.1 LIQUID EFFLUENTS B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.3 DELETED 3/4.11.4 DELETED 1/4.12 RADIOLOGICAL ENVIR0tiMENTAL M0111TORING 3/4.12.1 DELETED 3/4.12.2 DELETED-3/4.12.3 DELETED o

SOUTH TEXAS - UNITS 1.&'2 xvi Unit 1 - Amendment No. 47-Unit 2 - Amendment No. 36-

___:_____..______..___'i

DiDil ADMINISTRATIVE CONTROIS

\\

SECTION PAGE 6.5.2 HUCLEAR SAFETY REVIEW BOARD (NSRB).............

6-9 Function..........................

6-10 f

Composition................_.........

6-10 Alternates.........................

6-10 6-10 Consultants 6-10 Meeting frequency Quorum.........................._.

6-10 Review...........................

6-10 Audits...........................

6-11 6-12 Records 6.5.3 TECHNICAL REVIEW AND CONTROL Activities.........................

6-12 6-13 6.6 REPORTABIE EVENT ACTION 6.7 SAFETY LIMIT VIOLATION.............-.......

6-13 6-14 5.8 PROCEDyRES AND PROGRAMS 6.9 REPORTING REQUIREMENTS 6-18 6.9.1 ROUTINE REPORTS Startup Report.......................

6-18 Annual Reports.......................

6,

Annual Radiological Environmental Operating Report......

6-20 Semiannual Radioactive Effluent Release Report...._...

6-20 6-21 Honthly Operating Reports Core Operating Limits Report.-....-,..........

6-21

+

6.9.2 SPECIAL REPORTS 6-23 6-23 6.10 RECORD RETENTION..,................,.. -.

SOUTH TEXAS - UNITS 1 & 2 xix Unit '1:- Amendment No. 9, 47, 47 Unit 2 - Amendment No. 4, +7, 36-

+

9 INDEX j

i ADMINISTRATIVE CONTROL 5 SECTION EMI l

i 6.11 RADIATION PROTECTION PROGRAM 6-24

-6.12 HIGH RADIATION AREA.....................

6 ]

6.13 PROCESS CONTROL PROGRAM (PCP) 6-26 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6-23 t

i t

4 SOUTH TEXAS - UNITS 1 a.2 xx Unit 1 - Amendment No. 47 Unit' 2 - Amendment No. 36-a..

....a-

a QEflNIT10_NS E - AVERAGE DISINTEGRATION ENERGY 1.12 E shall be the average (weighted in proportion to the concentration of each radionuclide in the semple) of the sum of the average beta and gamma energies-per disintegration (HeV/d) for the isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

ENGINEERED _ SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be'that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).

Times shall include diesel generator starting and sequence loading delays where applicable, FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspend to the intervals defined in Table 1.1.

GASEOUS WASTE PROCESSING SYSTEM 1.15 A GASEOUS WASTE PROCESSING SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off gases from the Reactor Coolant System and providing for-delay or holdup for the purpose of reducing the total radioactivity priorito-release to the environment.

IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be:

a.

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump-seal or valve packing leaks that are captured and conducted to a sump _

a or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either_not to interfere with the operation of Leakage Detection Systems or not to be_ PRESSURE: BOUNDARY LEAKAGE, or c.

Reactor Coolant System leakage through a steam generator to'the Secondary Coolant System.

SOUTH TEXAS - UNITS 1 & 2 1-3

+,

- - ~ -

g mw

L DiflNITIONS i

r MASTER RELAY TEST

~

1.17 A MASTER RELAY TEST shall be the energization of each master relay and' verification of OPERABILITY of each relay.

The MASTER RELAY TEST shall i

include a continuity check of each associated slave relay.

MEMBER (S) 0F THE PUBLIC 1.18 MEMBER ($) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant.

This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. T',is category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (ODCM). shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous.and liquid. effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain i

(1) the Radioactive Effluent Controls and Radiological Environmental descriptions of the Monitoring Programs recuired by Section 6.8.3 and (2)iological Environmental information that should be included in the Annual Rad Operating and Semiannual Radioactive Effluent Release Reports required by Specification 6.9.1.3 and 6.9.1.4.

OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are.

required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s)..

OPERATIONAL MODE - MODI i

1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor _-

coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 4

10 CFR 50.59, or (3) otherwise approved by the Commission, i.

PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

SOUTH TEXAS - UNITS 1 & 2 1-4 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36

DfFINITIONS PROCESS CONTROL PROGRAM

{

l.24 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that i

processing and packaging of solid radioactive wastes based on demonstrated i

processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71. State.

regulations, burial ground requirements, and other requirements governing the i

disposal of solid radioactive waste.

i l

EURGE - PURGING 1.25 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

@AQRANT POWER TILT RATIO 1.26 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum-lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average, j

RATED THERMAL POWER 1.27 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3800 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.28 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor-until lou of stationary gripper coil-voltage.

. REPORTABLE EVENT 1.29 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of-10 CFR Part 50.

t SHUTDOWN MARGIN

- 1.30 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be-subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest.

reactivity worth which is assumed to be fully withdrawn.

i SOUTH TEXAS - UNITS 1 & 2 1-5 Unit 1 - Amendment No. - 47 Unit 2 - Amendment No. 36 a

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h DEFINITIONS SITE BOUNDARY 1.31 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee..

SLAVE REtAY TEST 1,32 A SLAVE RELAY 1EST shall be the energiration of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include 3

a continuity check, as a minimum, of associated testable actuation devices.

l SOURCE CHECX 1.34 A SOURCE CHECK shall be the qualitative assessment of channel response i

when the channel sensor is exposed to a source of increased radioactivity, STAGGERED TEST BASIS 1.35 A STAGGERED TEST BASIS shall consist of:

-)

a.

A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER

(

l.36 ' THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

IRIP ACTUATING DEVICE OPERATIONAL TEST 1.37 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying.0PERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall. include adjustment, as necessary, of the Trip Actuating Device-so that it actuates at the required Setpoint within the required accuracy.

UNIDENTirlED LEAKAGE 1.38 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

UNRESTRICTED AREA 1.39 An UNRESTRICTED AREA shall be-any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or. any area within the SITE BOUNDARY used for residential quarters or. for industrial, commercial,. institutional, and/or recreational purposes.

SOUTH TEXAS - UNITS 1 & 2 1-6 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36

ii DEFINITIONS YENTING 1.40 VEN11NG shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not i

provided or required during VEllTING.

' lent used in system names, does not i

imply a VENTING process.

i 1

r SOUTH TEXAS UNITS 1 & 2 1-7 Unit 1 - Amendment'No 47-l-

Unit 2

-Amendment No. 36 1

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TABLE 1.1 l

_ FREQUENCY NOTATION j

NOTATION FREQUENCY

-f 5

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once p'er 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.-

4 SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A.

Not applicable.

P Completed prior to each release.

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. SOUTH _ TEXAS - UNITS 1 & 2 118

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TABLE 3.3-4 (Continued)

- v, c!

52 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS U!.

TOTAL SENSOR ERROR

- d; FUNCTIONAL UNIT ALLOWANCE-(TA)

Z (5)

TRIP SETPOINT ALLOWABLE VALUE

.$ 11.

FHB HVAC (Continued) 25 i

' U!

b.

Automat 1c Actuation N.A.

N.A.

N.A.

N.A.

N.A.

. Logic and Actuation

e. -

Relays c.-

Safety' Injection See Item 1. above for all Safety. Injection Trip Setpoints and Allowable Values.

L d.

Spent Fuel Pool Exhuast 3.1x10

• 1.8x10

• 1.3x10 *

<5.0x10 4

<6.4x10 *

. g, Radioactivity - High pCi/cc pCi/cc pCi/cc pCi/cc pCi/cc 6s I

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4 TABLE 3.3-4 (Continued)

TABLE NOTATIONS l

l

• Time constants utilized in the lead-lag controller for Steam Line-Pressure-Low are r, 2 50 seconds and 7, s 5 -seconds.

CHANNEL CAllBRATION shall-ensure that these time constants are adjusted to these values.

• • The time constant utilized in the-rate-lag controller for Steam Line Pressure-Negative Rate-High is greater than or equal to 50 seconds.

CHANNEL CAllBRATION shall ensure that this time constant is adjusted to this value.

1. 2.0% span for Steam Generator Level; 0.2% span for Reference Lag.RTDs.

1. 1. Until resolution of the Veritrak transmitter uncertainty issue, the^ trip setpoint will be set at 21869 psig, with the allowable value at 2 1861 psig.

r

1. 1. 1. This setpoint value may be increased up to the equivalent. limits-of ODCH Control 3.11.2.1 in accordance with the methodology and parameters of the ODCM during containment purge or vent for pressure control, ALARA and-respirable air quality considerations for personnel entry.

h I

l 4

SOUTH-TEXAS - UNITS 1.&:2 3/4 3-36 Unit 1 - Amendment No. 4,4, 47 -

l Unit 2-AmendmentNo.38 J

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]NSTRUMENTATION EXPLOSlVE GAS MONITORING INSTRUMENTATIOJJ j

llMITING CONDITION FOR OPERATION 3.3.3.11 The explosive gas monitoring instrumentation channels shown in-Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a.

With an explosive gas monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-13.

b.

With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

T SURVEll1ANCE REQUIRfMEMiS 4.3.3.11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CAllBRATION and ANALOG CHANNEL OPERATIONAL TEST or DIGITAL CHANNEL OPERATIONAL TEST, as applicable, at the frequencies shown in Table 4.3-9.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-79 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36

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TABLE 3.3-13 (Continued)

IABLEil0 TAT 10flS

• -(flot Used)

• • During CASE 0VS WASTE PROCESSIllG SYSTEM operation.

ACT10ft STATEMENTS ACTI0li 47 - (Not used)

ACTION 48 - (flot used)

ACTION 49 - (Not used)

I ACTION 50 - (Not used)

ACTION 51 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this GASE0US WASTE PROCESSING SYSTEM may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 holms.

ACTION 52 - (Not used)

ACTION 53 - (Not used) l L

2 l

SOUTH TEXAS - UNITS 1 & 2 3/4 3-81

-Unit 1 - Amendment No, 47 Unit 2 - Amendment No. 36-a.

TABLE d.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS A5 ANALOG OR m

DIGITAL MODES FOR CHANNEL WHICH c-CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE f3 CHECK CHECK _

CALIBRATION TEST IS REQUIRED Di INSTRUMENT o-N 1.

GASEOUS WASlE PROCESSING SYSTEM Explosive Gas Monitoring System D

N.A.

Q(5)

M Oxygen Monitor (Process)

R a

5 WW

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- i TABLE 4.3-9 (Continued) l TABLE NOTATIONS i

(Not used)

During GASEOUS WASTE PROCESSING SYSTEM operation.

(1)

(Not Used)

(2)

(Not Use'd)

_ l (3)

(Not Used) l_

(4)

(Not Used)

(5) The CHANNEL CAllBRATION shall include the use of a standard gas sample containing a nominal two volume percent oxygen, balance nitrogen.

t 9

4 SOUTHLTEXAS.- UNITS 1 & 2

- 3/4 3-83 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36 w

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4 INSTRUMENTATIOS 3/4.3.4 TURBINE OVER$ PEED PROTECTION L1HITING CONQlTION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With one stop valve or one governor valve per high pressure turbine a.

steam line inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line ino>erable, restore the inoperable valve (s) to OPERABLE status wit 11n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.

With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.

SVRVEILtANCE RE0VIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:

a.

At least once per 31 days in MODES 1 and 2 when the main turbine is operating by cycling each of the following valves through at least one complete cycle from the running position:

1)

Four high pressurc turbine stop. valves,_

2)

Four high pressure turbine governor valves, 3)

Six low pressure turbine reheat stop valves, and 4)

Six low pressure turbine reheat intercept valves, b.

At least once per 31 days in MODES I and 2 when the main turbine is operating by direct observation of the movement of each of the above valves through one complete cycle from the running position, c.

At least once per 18 months by performance of a CHANNEL CAllBRATION on the Tur'ine Overspeed Protection Systems, and d.

At least once per 40 months by disassembling at least one of each of the above valves and. performing a visual and~ surface ins pection of valve seats, disks, and stems and verifying no unacceptaale flaws or excessive corrosion.

If unacceptable flaws or excessive corrosion are found, all other valves of that type shall_ be inspected *

• sassembly and inspection of the low pressure turbine reheat intercept valves are not required prior to the end of the first 40 month interval.

Unit I valves will be disassembled and inspected in the Unit 1 fifth refueling outage, following a one-time extension of the inspection interval from 40 rnonths (50 months with the 25% grace period) to approximately. 52 months.

SOUTH TEXAS - UNITS 1 & 2 3/4 3-84 Unit 1 - Amendment.No. 40,47

i

=

i TABLE 4.3-9 (Continued)

TABLE t10 TAT 10t15 l

(Not used)

During GASEOUS WASTE PROCESSING SYSTEM operation.

(1)

(flot Used) l (2)

(Not used)

(3)

(Not Used) l (4)

(Not Used)-

(5) The CHANflEL CAllBRAT10ft shall include the use of a standard gas sample containing a nominal two volume percent oxygen, balance nitrogen.

4 L

i SOUTH TEXAS - UNITS 1 & 2 3/4 3-83 Unit 1 - Amendment No. 47.

Unit 2 - Amendment No. 36.

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1!{1TRUMENT AT10N 3/4.3 4 TUR8INE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.

t APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With one stop valve or one governor valve per high pressure turbine a.

steam line inoperable and/or with one reheat stop valve or one reheat intercept valve per low 3ressure turbine steam line inoperable, restore the inoperaale valve (s) to OPEPABLE status wit 11n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.

With the above require 6 Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.

SURVElltANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:

At least once per 31 days in MODES'1 and 2 when the main turbine is a.

operating by cycling each of the following valves through at least one complete cycle from the running position:-

1)

Four high pressure turbine stop valves, 2)

Four high pressure turbine governor valves, 3)

Six low pressure turbine reheat-stop valves, and 4)

Six low pressure turbine reheat intercept valves, b.

At least once per 31 days in MODES I and 2 when the main turbine is operating.by di. rect observation of the movement of each of the above valves through one complete cycle from the running position, i

c.

At least once per 18 months by-performance of a CHANNEL CAllBRATION on the Turbine Overspeed Protection Systems,-and 1

d.

At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of-valve seats, disks, and stems and verifying no unacceptable flaws or-excessive corrosion.

If unacceptable flaws or excessive. corrosion are found, all other valves of that-type shall be inspected *

• Disassembly and inspection of the low pressure turbine reheat intercept valves are not required prict to the end of the first 40 month interval.

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

a 4

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 L10VID EFFLUENTS L10010 HOLDUP TANKS

• LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each unprotected outdoor tank shall be limited to less than or equal to 10 Curies, excluding -

tritium and dissolved or entrained nobic gases.

MPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any unprotected outdoor tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.4.

b.

The provisions of Specification 3.0.3 are not applicable.

SVRVElll ANCE Rf0VIREMENTS 4.11.1.4 The quantity of radioactive material contained in each unprotected outdoor tank shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

• Tanks included in this specifTeation are those autdoor tanks that are either not surrounded by liners, dikes, or walls -capable of-holding the tank contents or that do not have tank overflows and surrounding area drains connected to the Liquid Waste Processing System.

SOUTH TEXAS - UNITS 1.& 2 3/4 11-1 Unit 1 - Amendment No. 4, 47 Unit 2 - Amendment No. 36

l uit nu R6D10 ACTIVE [FFLUENTS

}/4.11 2 GASEOUS EFELUll(IS EXPLOSlVE CAS MIX 10EE ilMITING COND1110N FOR OPERAT10ii 3.11.2.5 The concentration of oxygen in the GASEOUS WASTE PROCESSING SYSTEM inlet shall be limited to less than or equal to 3% by-volume.

APPLICABillTY: At all times.

ACTION:

a.

With the concentration of oxygen in the GASEOUS WASTE PROCESSING SYSTEM inlet exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.

The provisions of Specification 3.0.3 are not applicable.

SLRVE1Lt ANCE REQUIREMENTS 4.11.2.5 The concentration of oxygen in the CASE 0VS WASTE PROCESSING-SYSTEM shall be determined to be within the above limits by continuously monitoring-_

the waste gases entering the GASEOUS WASTE PROCESSING SYSTEM with the oxygen monitor required OPERABLE by Table 3.3-13 of Specification 3.3.3.11.

SOUTH TEXAS - UNITS'1 & 2 3/4 11-2 Unit 1 - Amendment No.l47 l:

Unit 2 - Amendment No. 36--

__...u...s

l RADIDACTIVE EFFlVENIS CAS STORAGE TANKS llMITING CONDIT10f1 FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank 5

shall be limited to less than or equal to 1.0 x 10 Curies of noble gases (considered as Xe-133 equivalent).

APPLICABillTY: At all times.

ACTION:

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.4.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVElltANCE REQUIREMENTS 4.11.2.6 The cuantity of radioactive material contained in each gas storage tank shall be cetermined to be within the above limit at least once per 24-hours when radioactive materials are being added to the tank.

SOUTH TEXAS - UNITS 1 & 2 3/4 11-3 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36 I

e

+

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e 1

litTENTIONALLY BLANK F

SECTION 3/4.12 DELETED IN ITS ENTIRETY i

I

+

I SOUTH TEXAS - UNITS 1 & 2 3/4 12-1

-Unit 1 - Amendment No. 47 i

Amendment No. 36 Unit 21 -

.. ~. - ~.

.. ~..

INSTRUMENTATION

?!Lui REMOTE SHUTDOWN SYSTE,M (Continued)

L h-The OPERABILITY of the Remote Shutdown System ensures that a fire will not preclude achieving safe shutdown.

The Remote Shutdown System instrumentation, 4

antrol, and powet circuits and transfer switches necessary to eliminate effects the fire and allow operation of instrumentation, control and power circuits

- *1 to achieve and maintain a safe shutdown condition are independent of

.nere a fire could damage systems normally used to shut down the reactor.

.opability is consistent with General Design Criterion 3 and Appendix R d

';FR Part 50.

.vg 3.3.6 ACCIDENT MONITORING INSTRUMENTATION ne OPERABILITY of the accident monitori g instrumentation ensures that suf; -ient information is available on selected plant parameters to mor e.>

und casess these varir les following an accident.

This capability is c~

s-tent with the recommendations of Regulatory Guide 1.97, Revision 2, "Ih ser-g tation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Condc;. ion i

During and Following an Accident," December 1980 and NUREG-0737, " Clarification

.h of TMI Action Plan Requirements," November 1980.

The instrumentation listed in Table 3.3-10 corresponus tc' the Category 1 instrumentation for which selection, design, qualification and display criteria Lre described in Regulatory Guide 9

1.97, <tevision 2.

3/4.3.3.7 CHF '

DETECTION SYSTEMS The OPERABILITY of the Chemical Detection Systems ensures that sufficient cacb11ity is available to promptly detect and initiate protective action in the avant of an accidental chemical rtlease.

This capability is required to protect control room,ersonnel and i consistent with the recommendations of Regulatory a J oe 1.78, " Assumption-for Evaluating the Habitability of a Nuclear Power Piarc & crol Room During a ios'ulated Hazardous Chemical Release," June 1974 Provision in the Action Statement is included for n nditions whereby the inoperability of the Chemical Detection System precludes the use of makeup as required for Action Statement a. for MODES 5 and 6 of Technical Specification 3.7.7 or Table 3.3-3, Item 10, ACTION 27, 28.

The automatic actuation of the Control Room HVAC makeup mode while in the Action Statement for the Chemical Det,ection System does not constitute a violaticq of Technical Specification 3.3.3.7 ACTION a. or b. because this actuation protects the operators from a radiological event.

3/4.3.3.8 (Not Used)

SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-5 AMENOMENT N05.15 AND 5

+

IfflSTRUMEtiTAT10N BASES

\\

3/4.3.3.9 (Not Usedl 3/4.3.3.10 DELETED 3/4,3.3.11 EXPLOSlVE GAS MONITORING INSTRUMENTATION This instrumentation incudes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the GASE0US WASTE PROCESSING SYST!!i.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine t. peed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from e

turbine excessive overspeed is required since excessive overspeed of the g

turbine could generate potentially damaging missiles which cou'id impact and damage safety-related components, equipment, or structures.

SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-6 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36

e 3/4.11 RADI0 ACTIVE-EFFLUENTS BASES' 3/4.11'.1 110VID EFFLUENTS.

3/4.11.1.1 DELETED 3/4.11.1.2 DELETED 3/4.11.1.3 DELETED 3/4.11.1.4 L10VID HOLDUP TANKS The tanks covered by this specification include all those outdoor 1

radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding '

area drains connected to the Liquid Waste Processing System.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled-release of the tanks' contents, the resulting concentrations would be-less than the limits of 10 CFR Part 20, Appendix B, Table. II, Column 2, at the nearest potable water supply and the nearest surface water supply in an JRESTRICTED AREA.

,a 3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DELETED 3/4.11.2.2 DELETED 3/4.11.2.3 DELETED

- 3/4.11.2.4 DELETED 3/4.11.2.5 EXPLOSIVE G83 MIXTURE-This specification is provided to ensure that the concentration of potentially explosive-gas mixtures contained in the GASEOUS WASTE PROCESSING SYSTEM is maintained below the flammability limit of oxygen. The concentration of oxygen in the inlet header to the GASEOUS WASTE PROCESSING SYSTEM is continuously monitored and a high level alarm isolates the GASEQUS-WASTE PROCESSING SYSTEM. Provision is made to manually purge.the system with nitrogen and/or isolate the source.of oxygen. Maintaining the concentration of oxygen below its flanaability limit.(4% by volume) provides assut'ance that-the releases of radioactive materials will be controlled in conformance:with-the requirements of General Design Criterion 60 of Appendix A to _10' CFR Part 50.

Because of analyzer variabilities, a safety margin of ~1%_ by volume is applied. Therefore, the limiting cendition fnr operation is-maintaining

- oxygen concentration below 3% by volume.

SOUTH TEXAS - UNITS 1 & 2 B 3/4-11-1 Unit 1 - Amendment No. 4,47

_ Unit 2 - Amendment No. 36 Y

4 9

RADIOACTIVE EFFLUENTS BASES

-3/4.11.2.6 GAS STORAGE' TANKS The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification.

Restricting the quantity of radioactivity-contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consistent with Standard Review Plan 11.3, Branch Technical-Position ETSB 11-5, " Postulated Radioactive Releases Duc to a Waste Gas System -

Leak or Failure," in NUREG-0800, July 1981.

Since only the gamma body dose factor (DFB ) is used in the analysis, the Xe-133 equivalent is determined from the DFb, value for Xe-133 as compared to the composite DFB, for the actual mixture in the tank.

3/4.11.3 DELETED 3/4.11.4 DELETED

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1 l

l l

SOUTH TEXAS - UNITS 1 & 2 B 3/4 11-2 Unit 1 - Amendment No. 47 Unit 2 - Amendment No 36

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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 DELETED 3/4.12.2 DELETED 3/4.12.3 DELETED SOUTH. TEXAS - UNITS 1 & 2 B 3/4 12-1 Unit 1 - Amendment No. 4, 47 Unit 2 - Amendment No. 36 i

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@JJ1 g TRATIVE CONTROLS

- PROCEDURES AND PROGRAMS (Continued) 1)

Preventive maintenance and periodic visual inspection requirements',:

and 2)

Integrated leak test requirements for each system at-refueling cycle intervals or less.

b.

In-Plant Radiation Monitoring A program which will ensure-the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

1)

Training of personnel, 2)

Procedures for monitoring, and 3)

Provisions for maintenance of sampling and analysis equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit.

steam generator tube degradation. -This program shall include:

1)

Identification of a sampling schedule for the critical variables and control points for these variables, 2)

Identification of the procedures used to measure the values of.

~

the critical. variables, 3)

Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps:for evidence of condenser in-leakage, 4)

Procedures for the recording and management of data, 5)

Procedures defining corrective actions for all off-control point chemistry conditions, and.

6)

A procedure identifying:

(a) the authority respoasible for the interpretation of the data, and (b) the sequence-and timing of administrative events required tolinitiate corrective action, d.

Post-Accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident-conditions.

The program shall include the following:

1)-

Training of personnel, 2)

Procedures for sampling and analysis, and 3)

Provisions for' maintenance of sampling and analysis equipment.

SOUTH TEXAS - UNITS 1 & 2 6-15

- - ~..

~-

t

-?

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continuedt

-e,-

Accident Monitorina Instrumen.tation A program which will ensure the capability to monitor plant variables and systems operating status'during and-following an accident. This program shall-include those instruments provided to indicate system operating status and furnish information regarding the release of r'adioactive materials (Category 2-and 3 instrumentation as defined in Regulatory Guide 1.97, Revision 2) and-a provide ~the following:

1)

Preventive maintenance and periodic surveillance of instru-mentation, 2)

Pre-planned operating procedures and backup instrumentation to be used if one or more monitoring instruments become inoper-able, and 3)

Administrative procedures for returning inoperable instruments to OPERABLE status as soon as practicable, f.

Comoonent (y11ic or Transient limit The Component Cyclic and Transient Limit Program provides controls?

to track cyclic / transient plant conditions-to-assure that the cumulative fatigue usage factor-does not exceed 1.0 for those components for which' fatigue analysis was performed in accordance with Section III of the American Society of_ Mechanical Engineers Boiler and Pressure Vessel Code.

The cyclic and transient limits-used in the design are identified in the Updated Final-Safety Analysis Report, g.

Radioactive Effluent Controls Proaram -

A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses-to MEMBERS OF-THE PUBLIC from radioactive effluents as low as-reasonably achievable. The program (1)' shall be contained in the ODCM,- (2) shall be implemented by operating arocedures, and (3)-

shall include remcjial actions to be_ taken wienever the program -

limits are exceeded.. The program shall include the following.

elements:

1)

Limitations on the. operability of radioactive liquid and -

gaseous monitoring instrumentation including surveillance tests and-setpoint determination in accordance with the methodology-in the ODCM, SOUTH TEXAS - UNITS 1 & 2 6-16 Unit 1 - Amendment No.

46, 47-Unit 2.- Amendment No.

35, 36-

e

. ADMINISTRATIVE CONTROLS FROCEDURES AND PROGRAMS 1 Continued) 2)

Limitations on the concentrations of radioactive material-released in. liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20,- Appendix 8,' Table II, ' Column 2, 3)

Monitorim, sampling, and analysis of radioactive liquid and' gaseous effluents in accordance with 10 CFR 20.106 and with.the methodology and parameters in the ODCM, 4)

Limitations on the annual and quarterly doses or dose _.

commitment to a MEMBER OF THE PUBLIC from the radioactive materf als in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I-to 10 CFR Part 50, 9

5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar; quarter and-current calendar year in-accordance with the_ methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use of the-liquid and.

gaseous effluent treatment systems to ensure that'the appropriate portions of these systems are used_to_ reduce releases of radioactivity when the projected doses in a 31-day-period would exceed 2 percent of.the. guidelines for the annual dose or dose commitment. conforming to Appendix I to 10 CFR Part 50, 7)

Limitations on the dose rate resulting from radioactive material released in gaseous: effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20,- Appendix B, -Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting,

from noble gases released in gaseous effluents _from each-unit to areas beyond the SITE BOUNDARY conforming to_ Appendix _-I to 10 CFR Part 50, 9)

Limitations on the. annual and quarterly doses to a MEMBER OF THE PUBLIC-from Iodine-131, Iodine-133, tritium,-and all: radio-o L

nuclides in particulate form with half-lives greater than 8

^

days in' gaseous effluents released from each unit.to areas -

beyond the SITE BOUNDARY conforming to Appendix I to 10-CFR Part 50, and 10)

Limitations on-the-annual dose or dose commitment to any MEMBER OF THE PUBLIC due to_ releases of radioactivity'and to radiation-from uranium fuel cycle sources conforming-to:40 CFR Part-190.

E I'

L ji SOUTri TEXAS - UNITS 1 & 2 6-17 Unit l'--Amendment No. 47-Unit 2 - Amendment No. 36-y e

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) h)

Radioloaical Environmental Monitorina Prcoram A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and.(2) verificatio_n of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program-shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE B0UNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and 3)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

6.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTVP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall P

be' submitted following:

(1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

L The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured

=

values of the operating conditions or characteristics obtained during tLe test

~

SOUTH TEXAS - UNITS 1 & 2 6-18 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36

. ADMINISTRATIVE CONTROLS-STARTUP REPORT (Continued) program and a comparison of these values with design predictiono and specifi-cations. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments _ shall be included in this report.

Startup Resorts -shall be submitted within:

(1) 90 days following completion of tae Startup Test Program, (2) 90 days following resumption or_-

commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS

• 6.9.1.2 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March I of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to_ work and job functions ** (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance], waste processing, and refueling).

The dose assignments to various duty functions may~be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements.

Small exposures _ totalling-less than 20%-of the individual total dose need not be accoonted for.

In the aggregate, at least 80% of the total whole-body dose received from external sources should be assigned to specific major work functions; and b.

The results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4-8. - The following_

information shall be included:

(1) Reactor power history starting

• A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the-station.

P

• • lhis taoulation supplements the requirements of 920.407 of 10 CFR Part 20.

SOUTH TEXAS - UNITS 1 & 2 6-19 Unit 1 - Amendment No. 47 ~

Unit 2 - Amendment No. 36

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ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sampic in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results _ of one.

analysis af ter the radioiodine activity was reduced to less than limit.

Each result should include date and time of sampling and:

the radiciodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration (pci/gm) and one other radiciodine isotope concentration (yci/gm) as a function of time for the duration-of the specific activity abova the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORI*

6.9.1.3 Routine Annual Radiological Eny'..unmentai Operating Reports covering the operation of the unit during the prey!ous calendar year shall be submitted prior.to May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of.the Radiological Environmental Monitoring Program for.the reporting period. The material provided shall be consistent with the objectives outlined in (1) the-0DCM ~and (2) Sections IV.B.2, IV.B.3,' and IV.C of Appendix I to 10 CFR Part 50.

SEMIANNUAL RADI0 ACTIVE rFFLUENT RELEASE REPORT **

6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 moriths of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents, and solid waste released from the unit. The material provided shall be.(1) consistent with the objectives outlined in the ODCM and-PCP'and (2) in conformance with 10'CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

• A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

• • A_ singic submittal may be made for a multiple unit station.

The submittal should ccabine those sections that are common to all units at the station; howevers for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SOUTH-TEXAS - UNITS 1 & 2 6-20 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36

ADMINISTRATIVE CONTROLS' MONTHLY OPERATING REPORIS.

6.9.1.5 Routine-reports of operating statistics and shutdown experience,.

including documentation of all-challenges to the PORVs or cafety valves, shall be submitted on a monthly basis to the Director, Office of Resource Manage-ment, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Administrator of the Regional Office of the NRC.- no later than the 15th_ of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.6.a Core operating limits shall be established and documented in the-CORE OPERATING LIMITS REPORT before each reload cycle -or any part of a reload cycle for the following:

1. _. Moderator Temperature Coefficient BOL and E0L limits, and 300 ppm surveillance limit for Specification 3/4.1.1.3, 2.

Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.

Control _ Bank Insertion Limits for Specification 3/4.1.3.6, 4.

Axial Flux Difference limits and target band for Specification 3/4.2.1,

~

Heat Fg) Hot Channel Factor, K(Z), Power' Factor Multiplier, 5.

and (F for Specification 3/4.2.2, and y

6.

Nuclea* Enthalpy Rise Hot Channel Factor, and Power Factor Multiplier for Specification 3/4.2.3.

The CORE OPERATING LIMITS REPORT shall-be maintained available in the Control Room.

6.9.1.6.b The analytical methods used to determine the core-oper_ating-limits shall be those previously reviewed and-approved by the NRC in:

1.

WCAP'9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY", July,1985 (H Proprietary).

(Methodology for Specification 3.1.1.3 :- Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Rod Insertion Limit, 3.1.3.6 -

Control Bank _ Insertion Limits, 3.2.l' - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel-Tactor, and.3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)

1.A.

WCAP-12942-P-A, " SAFETY EVALUATION SUPPORTING A MORE-NEGATIVE E0L MODERATOR TEMPERATURE COEFFICIENT TECHNICAL SPECIFICATION FOR THE SOUTH-TEXAS PROJECT ELECTRIC GENERATING STATION UNITS'l AND 2."

SOUTH TEXAS - UNITS 1 & 2 6-21

_ Unit -1

- Amendment No. 9, N, M,47 Unit 2 - Amendment No. 4, M, M,136 u

ADMINISTRATIVE CONTR0tS CORE OPERATING LIMITS REPORT (Continued)-

(Methodology for Specification 3.1.1.3 - Moderator Temperature _

Coefficient)-

2.

WCAP 8385, " POWER DISTRIBUTION AND LOAD _FOLLOWING PROCEDURES TOPICAL REPORT", September, 1974 (H Proprietary).-

(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).)

3.

Westinghouse letter NS-TMA-2198, T.M. Anderson (Westinghouse) to K. Kni. (Chief of Core Performan:e Branch, NRC)

January '1, 1980 -

Attachment:

Operation and Safety Analysis Aspects of an Improved Load follow Package.

(Methodology -for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).

Approved by NRC Supplement No. 4 to NUREG-0422 January, 1981 Docket Nos. 50-369 and 50-370.)-

4.

NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory _ _

Commission, Section 4.3, Nuclear Design, July,1981.

Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial ^

Offset Control (CAOC), Rev. 2, July 1981.

(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).)

5.

WCAP 9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 VERSION", February 1982 (H Proprietary).

(

(Methodology for Specification 3.2.2 --Heat Flux Hot Channel Factor.)

6.

WCAP 9561-P-A, ADD. 3. REV.'1, "BART A-1: A COMPUTER CODE FOR-THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS - SPECIAL REPORT: THIMBLE MODELING H; ECCS EVALUATION MODEL",' July,1986 (H Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot channel Factor.)

6.9.1.6.c The core operating limits shall be determined so that ail appli-cable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis' limits) of the safety analysis are met.

6.9.1.6.d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions;or supplements thereto, shall be provided upon issuance, for each reload cycle,1 to the NRC Document Control Desk, witk copies to the Regional' Administrator,and Resident Inspector.

SOUTH TEXAS - UNITS 1.& 1 6-22 Unit l_- Amendment No. G7, as, 47-

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Unit 2_- Amendment No. 14, 26, 36 i

_m, _ -

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be ubmitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.-

6.10 RECORD RETENTION 6.10.1 In addition to_ the applicable record retention requirements of-Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a.

Records and logs of unit operation covering time interval at each power level; b.

Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to-nuclear safety; c.

All REPORTABLE EVENTS; d.

Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; e.

Records of changes made to the procedures required by Specifica-tion 6.8.1; f.

Records of iadioactive shipments; g.

Records-of sealed source and fission detector leak tests and results; and h.

Records ~ of annual physical inventory of all ' sealed source material of record.

6.10.3 The following records shall be retained for the duration of the unit Operating License:

-a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described-in the Final-Safety Analysis Report; b.

Records of new and irradiated fuel inventory, fuel transfers,. and assembly burnup histories; c.

Records of radiation exposure for all individuals entering radia-tion control areas; d.

Records of gaseous and liquid radioactive material released to the environs; SOUTH TEXAS - UNITS 1 & 2 6-23 Unit 1 - Amendment No. 47 Unit 2 - Amendment No. 36 7

ADMINISTRATIVE ~ CONTROLS 6.10 RECORD RETENTION (Continued) e.

Records of-transient or operational cycles for those unit components identified in the UFSAR; f.

Records of reactor tests and experiments; g.

Records of training and ' qualification for current members. of the unit staff; h.

Records of inservice inspections performed pursuant to these Technical Specifications; i.

Records of quality assurance activities required by the Opera-tional Quality Assurance Plan; j.

Records of reviews performed for changes made to procedures or equipmeat or reviews of tests and experiments pursuant to-10 CFR 50.59; k.

Records of meetings of the PORC and the NSRB; 1.

Records of the service lives of all hydraulic and~ mechanical sntbbers required by Specification 3.7.9 including the date at which the service life commences and associated installation and maintenance records; Records of secondary water sampling and water quality; an'd m.

n.

Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy'of the analysis at a later date. This should include procedures effective at specified times and QA records showing that'these procedures were followed, o.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL AND THE PRGCESS CONTROL PROGRAM, 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1-Pursuant to paragraph 20,203(c)(5) of 10 CFR Part 20, in lieu.of the

" control-device" or " alarm signal" required by paragraph 20.203(c),'each high-radiation area, as defined in 10 CFR Part 20, in which the intensity of SOUTH TEXAS - UNITS 1 & 2 6-24 Unit 1 - Amendment No. ~46, 47 Unit 2 - Amendment-No. 35, 36 -

L

m ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such indiviauals may be exempt from the RUP issuance requirement during the-performance of their assigned duties in high radiation arear with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall t,e provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area; or b.

A radiation monitoring device which centinuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowled-geable of them; or c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positivo control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health and Safety Services Manager in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any. surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry,-

and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision.

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. -In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) coatinuous surveillance may be made b ' personnel qualified in radiation protection procedures to-provide. positive exposure control over the activities being performed within the area.

For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h tnat are located within large areas, sch as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around.the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activtted as-a warning device.

SOUTH TEXAS - UNITS 1 & 2 6-25

. Unit 1 - Amendment No. 47-Unit 2 - Amendment No. 36 -

m A

A

- ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:-

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.o.- This documentr. tion shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2) A determinatie that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.

6.14 0FFSITE DOSE CALCVLATION MANUAL (00CM)

Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall: be.

retained as required'by Specification 6.10.3.o.

This documentation shall contain:

1) Sufficient information to support the change'together with the appropriate analyses or evaluations justifying the change (s).-

and

2) A determination that the change will maintain the level of radioactive effluent control-required by 10 CFR 20.106,140-CFR Part 190, 10 CFR 50.36a, and-Appendix 1 to 10 CFR.Part 50 and not adversely impact the accuracy or reliability of effluent,-

dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by the PORC.and the approval of the Plant Manager. '

c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or-concurrent with.

the Semiannual Radioactive Effluent Release Report-for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the datef(e.g., month / year) the-change was implemented.

G0UTH TEXAS - UNITS 1 & 2 6-26 Unit 1 Amendment No. 47 Unit 2 - Amendment 'No. 36

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