ML20114D820

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Amends 43 & 32 to Licenses NPF-76 & NPF-80,respectively, Changing App a TS in Sections 3/4.9 & 5.6 Re Prevention of Criticality in Spent Fuel Pool
ML20114D820
Person / Time
Site: South Texas  
Issue date: 08/25/1992
From: Black S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20114D821 List:
References
NUDOCS 9209090373
Download: ML20114D820 (26)
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[N UNITED STATES

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NUCLEAR REGULATORY COMMISSICN

  • hgW WASHINoTON. D C,20M6 q.m liOUSTON 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 FACIllTY OPERATING LICENSE Amendment No. 43 License No. NPF-76 1.

The Nuclear Regulatory Commission (tne Comission) has found that:

A, The applicacioi. for amendment by Houston Lightin'g & Power Company *

(HLtP) 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 May 26, 1992, as s",,pplemented by letter dated June 3,1992, complies with the standards h d requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations sct forth in 10 CFR Chapter I; B.

1he f acility sill operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the 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 authorizea 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 constructicn, operation and maintenance of the facility.

9209090373 920825 PDR ADOCK 05000498 F

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2-2.

Accordingly, the license is amended by changes to the Technical Spacifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facilit Operating License No. f.DT-76 is hereby amended to read as follows:

2.

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

43, and the Environmentai 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 P.lan.

3.

The license amendment is effective as of its date of issuance and is to be implemented within ten days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 25, 1992-ur T'W

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v UNITED STATES l'

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NUCLEAR REGULATORY COMMISSION ei WASm4CTON D. C. 20555 s,.,

HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CitiTRAL POWER AND LIGHT COMPANY

[JTY OF AUSTIN. TEXA3 DOCKET NO. 50-499 SOUTH TEXAS DROJECT._ VNITJ atQiDMENT TO FAClllTY OPERAlltiLUCENSE Amendment No. 32 License No NPF-80 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Houston Lighting & Power Company' (HL&P) acting on behalf cf 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 May 26, 1992, as

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supplemented by letter dated June 3,1992, complies with the standards and requirement: of the Atomic Energy Act of 1954, as amended (tne Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate ir conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the 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 issur.nce of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable raquirements have been satisfied.

1

  • Houston Lighting & Power Company is authorized to act for the City Public Service Board of San Antonio, Central Power and Light Compny and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

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Accordin' fly, 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 f acility Operating Liter:se No. f4Pf-80 is hereby amended to read as follows:

2.

Ighnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

32, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance and is to be implemented within ten days of issuance.

FOR THE NUCLEAR REGULATORY COMMISS10f4 1*Q ' q. ([ /,$k ( I.-

u Suzanne C. Bli.ek, Director Project Directorate IV-2 Division of Reactor Projects Ill/lV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 25, 1992

1 ATTACHMENT TO LICENSE AMENDMENT N05. 43 AND 32 FACILITY OPERATING LICENSE N05. NPF-76 AND NPF-80

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DQ(EET N05. 50-498 AND 50-499 i

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 correr.ponding overleaf pages are also provided to maintain dotament completeness.

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INSERT xi xi xv xv xvii xvii 3/4 9-17 8 3/4 9-3 B 3/4 9-3 5-6 5-6 5-7 5-7 5-6 5-8 5-9 5-9 5-10 5-11 5-12 5-13 5-14

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INDfX llMITING CONDITIONS FOR OPERATION AND SURVrill ANCE Rf 0VIREMENTS ped SECTION 3/4.9.11 WATER LEVEL - STORAGE POOLS Spent fuel Pool........................................

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

3/4 9-13 3/4.9.12 FUEL HANDLING BUILDING EXHAUST AIR SYSTEM..............

3/4 9-14 3/4.9.l?

SPENT FUEL POOL MINIMUM BOR0f1 CONCEllTRATION............

3/4 9-17 J/4.10 _SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN HARGIN........................................

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LlHITS.

3/4 10-2 3/4.10.3 PHYS ",5 TESTS.........................................

3/4 10-3 3/4.10.4 RE AC T 0R C OO L AN T LOO P S...................................

3/4 10-4 3/4 10.S POSIT ION INDIC AT ION SYST EM - SHUTDOWN.................. 3/4 10-5 3/4.11 RAD 10AC11VE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration..........................................

3/4 11-1 3/4 11-2 Dose...................................................

3/4 11-3 Liquid Waste Processing System.........................

Liquid Holdup Tanks....................................

3/4 11-4 3/4 11.2 GASEOUS EFFLUENTS 3/4 Il-S Dose Rate..............................................

Do s e - N obl e G a s e s..................................... 3/4 11-6 Dose - lodine-131, Iodine-133, Tritium, ar.d Radioactive Material in Particulate form........................... 3/4 11-7 Gaseous kaste-Processing System........................

3/4 11-8 Explosive Gas Mixture..................................

3/4 11-9

. Gas Storage Tanks......................................

3/4 11-10 3/4.11.3 SOLID RADI0 ACTIVE WASTES.............................. 3/4 11-11 3/4.11.4 TOTAL DOSE.............................................

3/4 11-13 I

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

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

,PAGE SEC110N 3/4.12 RADIOLOGICAL ENVIR0tiMENTAL MONITORING 3/4 12-1 3/4.12.1 MONITORING PR0 GRAM.......................................

3/4 12-3 3/4.12.2 LAND USE CEN50s..........................................

3/4 12-5 3/4.12.3 INT E RL ABOR ATORY COMP ARI SON PROGR AM.

1 xii SOUTH TEXA5 - UNITS 1 & 2

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- - - - - - - - - ~, -. _ _ _ _ _ _ _ _ _ _ _ _ _.

If4DEX BAsf5 PHf 1ECTION B 3/4 /-6 3/4.7.10 S E AL E0 SOURC E C ONT AMIN AT ION............................

3/4.7.11 (Not used) 3/4.7.12 (Not used) 3/4.7.13 AR E A T EMP E RAT URE MON I T OR! flG............................B 3/4 7-6 3/4.7.14 ESSENTI AL CHILLED WAT ER SYST EM......................... B 3/4 7-6 3/4.8 f,LECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and Ot4 SITE POWER DISTRIBUTION............................. B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................

B 3/4 8-3 E4. 9 REFUELING OPERAT10t15 3/4.9.1 BOR0tl 00t4CENTRAT10N.................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION........................................ B 3/4 9-1 B 3/4 9-1 3/4.9.3 DECAY TIME.............................................

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.....................

B 3/4 9-1 3/4.9.5 00KMUNICAT10NS.........................................

B 3/4 9-1 3/4.9.6 REFUELING KACHINE......................................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING..................

B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND C00LAt4T CIRCULATION.......... B 3/4 9-2 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 and ST O RA G E P OO L S..........................................

B 3/4 9-3 3/4.9.12 FUEL HANDLitlG BUILDING EXHAUST AIR SYSTEM..............

B 3/4 9-3 3/4.9.13 SfTNT FUEL POOL MINIMUM BORON CONCEN1 RAT 10N............

B 3/4 9-3 3 /4.10__SPALLJ ST EXCEPTI.QNS 3/4.10.1 SHUTDOWN KARGIN........................................

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.

B 3/4 10-1 3/4.10.3 PHYSICS TESTS.........................................

B 3/4 10-1 3'4.10.4 REACTOR COOLANT LOOPS.................................

B 3/4 10-1 3/4.10.5 POSITION INDICAT ION SYST EM - SHUTDOWN.................

B 3/4 10-1 SOUTH TEXAS - UNITS 1 & 2 xv Unit 1 - Amendment ho. 43 Unit 2 - Amendment No. 32

INDEX QAffi PAGE SECTION 3/4.11 RAD 10 ACTIVE EFFLUENTS B 3/4 11-1 3/4.11.1 LIQUID EFFLUENTS.................'........................

B 3/4 11-2 3/4.11.2 GASEOUS EFFLUENT 5........................................

B 3/4 11-6 3/4.11.3 SOLID RADI0 ACTIVE WASTE5.................................

B 3/4 11-6 3/4.11.4 TOTAL 005E...............................................

3/4.11 RADIOLOGICAL ENVIRONMENTAL MONITORING B 3/4 12-1 3/4.12.1 MONITORING PR0 GRAM.......................................

3 3/4 12-1 3/4.12.2 LAND USE CENSUS.................

B 3/4 12-2 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM...............

SOUTH TEXAS - UNITS 1 & 2-xvi

i INDEX DFSIGN FEATURFS PAGE SECTION 5.1 SITE 5-1 5.1.1 EXCLUSION AREA...........................................

5-1 1

5.1.2 LOW POPULATION ZONE.,.....................................

5.1.3 MAP DEFINING UNRESTRICTED (dEAS AND SITE BOUNDARY FOR5-1 RADI0 ACTIVE GASE0US AND LIQUID LFFLUENTS..................

5.2 CONTAINMENT 5-1 5.2.1 CONFIGURATION.............................................

5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE...........................

5-2 FIGURE-5.1-1 EXCLUSION AREA.....................................

5-3 FIGURE 5.1-2 LOW POPULATION ZONE................................

FIGURE 5.1-3 UNRESTRICTED AREA AND SITE B0UNDARY FOR RADI0 ACTIVE 5-4 GASE0US EFFLUENTS..................................

FIGURE 5.1-4 UNRESTRICTED AREA AND SITE BOUNDARY FOR RADIDACTIVE 5-5 LIQUID EFFLUENTS...................................

5.3 REACTOR CORE 5-6 5.3.1 FUEL ASSEMBLIES..........................................

5-6 5.3.2 CONTROL R0D ASSEMBLIES....................................

5.4 REACTOR COOLANT SYSTEM 5-6 5.4.1 DESIGN PRESSURE AND TEMPERATURE...........................

5.4.2 VOLUME.................................................... 6-5-6 5.5 METEOROLOGICAL TOWER LOCATION................................

5.6 FUEL STORAGE 5-6 5.6.1 CRITICALITY...............................................

5-9 5.6.2 DRAINAGE..................................................

5-9 5.6.3 CAPACITY..................................................

FIGURE 5.6.1 MINIMUM BURNUP FOR CATEGORY 2 FUEL................. 5-10 FIGURE 5.6-2 MINIMUM IFBA CONTENT FOR CATEGORY 3 FUEL...........

5-11 FIGURE-5.6-3

' MINIMUM BURNUP FOR CATEGORY 3 FUEL.................

5-12 FIGURE 5.6-4 MINIMUM BURNUP FOR CATEGORY 4 FUEL.................

5-13 FIGURL 5.6-5 REGION 1 CLOSE PACKED AND CHErXERBOARD FUEL STORAGE......................................

5-14 FIGURE 5.6-6' REGION 2 CLOSE PACKED ANF CHECKERBOARD 5-15 FUEL STORAGE.....................................

5-16 5.7 COMPONENT CYCL IC OR TRANSIENT L IMIT.........................

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1ABLE 5.7-11 COMPONENT CYCLIC OR TRANSl[NT ' IMITS..............

5-17 SOUTH TEXAS - UNITS 1 & 2 xvii Unit 1 - Amendment No i, 43 Unit 2 - Amendment No. 32 i

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P INDEX ADMINISTRATIVE CONTROLS PAGE SECTION

- 6.1 RESPONSIBILITY................................................

6-1 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONS11E ORGANIZATIONS............................

6-1 6.2.2 UNIT STAFF..................................................

6-1 i

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION-TWO UNITS WITH TWO SEPARATE CONTROL R00MS................................

6-4 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

Function................................................... 6 Composition................................................

6-6 Responsibilities.................................

6-6 Records....................................................

65 6.2.4 SHIFT TECHNICAL ADVIS0R.....................................

6-6

6. 3 - (Not Used) 6.4 TRAINING......................

6-7

6. 5 REVIEW AND AUDIT..............................................

6-7 6.5.1 PLANT OPERATIONS REVIEW C0KMITTEE (PORC)

Function................

6-7 Composition................................................

6-7 Alternates.................................................

6-7 Meeting Frequency..........................................

6-7 6-7 Quorum.....................................................

R e s p e n s o i l i t i e s............'...............................

6-8 Records....................................................

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l SOUTH TEXAS - UNITS 1: & 2 xviii Unit 1 - Amendment No. 3,4

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REFUELING OPEB.ATy$

3/4.9. Q SPEil_F3EL POOL MINIMUM BORON CONCENTRATION Q1TINGCOND,lTIONFOROPERATjN_

3.9.13 The borois concentratic.i of the spent fuel pool water shall be maintained greater than or equal to 700 ppm.

APPLICABILITY: -Whenever one or more fuel asse, blies are stored in the spent fuel pool racks.

6 1 1011' a.

With the requirements t t-specificLtion not satisfied, immediately suspend

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nvolving movement of fuel assemblies in the spt

,6orage pool and initiate action to restore the boron con *. ation in the speat fuel pool to greater than or equal to 700 ppm.

~.e provisioni of Specification 3.0.3 are not applicable.

b.

i Sygyr11lANCFRF001RFMFNis 4.9.13 The boron concentration of the spent fuel pool shall be determined by chemical analysis at least once per 7 days.

SOUTH '.EXAS - ohlTS 1 & 2 3/4 9-17 Unit 1 - Arandment No. 43 Unit 2 - Amendment No. 32 a

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REFUEllNG OPERATIONS Bf5ES 3/4.9.10 and 3/4.9.11 WATER LEVEL - REFUELING CAVITY AND STORAGE POOLS The restrictions on minim" water level ensure that sufficient water depth is available to remove 99% of i.e assumed 10% iodine gap activity released from the rupture of an irradiated fu91 assembly. The minimum water depth is consistent with the assumptions of the safety analysis.

1 & 9.17 FUEL HANDLING BUILDING EXHAUST AIR SYSTEM

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The limithtion:. on the fuel Handling Building Exhaust Air System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to Operation of the systen with the heaters operating for at least the atmosphere.

10 continuous hours in a 31-day period is sufficient to reduce the buildup of The OPERABILITY of this system and moistu'*e on the adsorbers and HEPA filters.

the resulting iodine removal capacity are consistent with the assumptions of the

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safety analyses. ANSI N510-1980 will be used as a procedural guide for surveillance testing.

3/4.9.13 SPENT FUEL POOL MINIMUM B E N c0NCF#iRAT10N The restrictions on the boron conceatration of the spent fuel pool ensures that the rack K,, is maintained less than oc equal to 0.95 in the event that one or more fuel, assemblies are improperly loaded in the a ent fuel pool storage racks (with respect to Specification 5.6).

Since the presence of boron is ensured, will be maintained less than or equal to 0.95 in the event of the rack K ' ding of fuel assemblies. This b on concentration is more than improperINa adequate to ensure the K,, limit of 0.PI, specified in Specification 5.6.1.1.a, will not be violated und,er the following scenarios:

r (1) in Region 1, any misloading of Cuegory 1, 2, 3, and 4 assemblies: or

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in Region 2, the misloading of one Category 1 assembly into the center (2) of a fully loaded checkerboard area also containing Category 1 assem-blies; or,

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(3) the misloading of a Category 1 assembly in a Region 1 rack adjacent to a Category 1 assembly in a Region 2 rack.

This boron concentration limit is the value necessary to enrure that the 0.95 K,,, limit for rack criticality will not be violated in the event of a Category 1 assembly dropped in the gap between the pool wall and a Region 2 rack module.

SOUTH TEXAS - UNITS 1 & 2 B 3/4 9-3 Unit 1 - Amendment No. 43 f--_____-_-___-_______________

Unit 2 - Amendment No. 32

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I SOUT11 TEXAS PRf1 JECT UNITS 1 & 2 s.

FIGURE 5.1-4 UNRESTRICTED F ** AND SITE BOUNDARY FOR RADI0 ACTIVE LIQUID EFFLUENTS

1 DESIGN FEATURES

- L.} REACTOR CORE FUEL A!SEMBLIES b.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad eith Zircaloy-4.

Each fuel rod sh ll have a nominal active fuel length of 168 inches. The initial core loading shall have a maximum enrichment of 3.5 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment I

of 4.5 uight percent U-235.

l CONTROL R00 ASSEMBLIES 1

5.3.2 The core shall contain 57 full-length control rod assemblies. The full-

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length control rod assemblies shall contain a nominal 158.9 inches of ab:orber a

material. The absorber material within each assembly shall be silver-indium-cadmium or hafnium. Hixtures of hafnium and silver-indium-cadmium are not permitted within a bank. Al' control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

In accordance with the Code requirements specified in Section 5.2 of a.

the FSAR, with allowance for normal degradatinn pursuant to the applicable Surveillance Requirements, b.

For a pressure of 2485 psig, and For a temperature of 650*F, except for the pressurizer which is 680'F.

c.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,814 i 100 cubic feet at a nominal.m of SEl'F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological towers shall be located as shown on Figure 5.1-1.

Lf FUEL STORAGE 5.6.1 CRITICALITY 5.6.1.1 The _ spent fuel storage racks are designed and shall be maintained with:

l SOUTH TEXAS - UNITS 1 & 2 5-6 Unit 1 - Amendment No. 2, 20, 16, 43-i Unit 2 - Amendment No. 2. E, 32

DESIGN FEATURES equivalent to less than or equal to 0.95 when flooded with A k,,, ted water.

a.

This requirement shall be met by storing fuel in the unbora spent fuel storage racks according to Specifications 5.6.1.3, 5.6.1.4.,

Additionally, credit may be taken for the presence of and 5.6.1.5.

soluble boron in the spent fuel pool water, per Specification 3.9.13, to mitigate the misloading of one or more fuel as:emblies, as described in Specification 5.6.1.6.

A nominal 10,95 inches center to center distance between fuel b.

assemblies in Region 1 of the storage racks and a nominal 9.15 inches center to center distance between fuel assemblies in Region 2 of the storage racks, Neutron absorber (Boraflex) installed between spent fuel assemblies in c.

the storage racks in Region 1 and Region 2.

Prior to insertion into the spent fuel storage racks, each fuel 5.6.1.2 assembly shall be categorized by reactivity, as discussed below, or be desig-All fuel enrichment values are initial nated as a Category 1 fuel.ssembly.

.ominal uranium-235 enrichments. The reactivity categories are:

CATEGORY h Fuel in Category 1 shall have an init tal nominal enrichment of less than or equal to 5.0 w/o.

CATEGORY 2:

Fuel in Category 2 shall meet at least one of the following criteria:

1)-

a maximum initial nominal enrichment of 4.0 w/o; or, a minimum burnup as shown on Figure 5.6-1; or, a minimum number of Westinghouse Integral fuel Burnable Absorber pins, 5,

as shown on Figure 5.6-2, or a K g of less than or equal-to 1.445.

The fuel assembly X shall he based on a unit assembly configuration (infinite in the lakgeral and axial extent) in the reactor core geome-try, assuming-unborated water at 68'F.

TheIFBArodrequirementsshowninFigure5.6-2arebgsedonanIF6AlinearB' For higher IFBA linear B loadings, the required 8

-loading of 1.57 mg-B"/1nch.

mber of IFBA rods'per assembly may be reduced by the ratio of the increased ny0 loading to the nominal 1.57 mg-B / inch loading.

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CATEGORY 3:

Fuel in Category 3 shall hve the minimum assembly burnup shown on rigure 5.6-3.

L CATEGORY 4:

L Fuel in Category 4 shall have the minir!m assembly burnup shown on Figure i

5.6-4.

Data points for the curves presented in Figures 5.6-1 through 5.6-1 are Linear interoolation between

-presented in tables on the respective figures.

table-values may be used for intermediate points.

SOUTH TEXAS - UNITS 1 & 2 5-7 Unit 1 - Amendment No. 7, 43 Unit 2 - Amendment No. 32

DESIGN FFATURES 5.6.1.3 Region 1 racks may be used to store Category 1, 2, 3, and 4 fuel.

Category 1 fuel shall be stored in a checkerboard pattern configuration with Category 3 or 4 fuel, alternating fuel assemblies as shown in Figure 5.6-5.

Category 2, 3, and 4 fuel may be stored in a close packed arrangement.

Empty water cells may be substituted for fuel assemblies in all cases.

fuel 5.6.1.4 Region 2 racks may be used to store Category 1, 2, 3, and 4 fuel, in Categories 1, 2, and 3, shall be stored in a checkerboard pattern configuration alternating fuel assemblies with empty water cells in a 2 out of 4 pattern, as shown in Figure 5.6-5.

Category 4 fuel may be stored either in a close packed arrangement or in the checkerboard pattern described above.

Empty water cells may be substituted for fuel assemblies in all cases.

5.6.1.5 Storage Configuration Interface Requirements.

The transition schemes described below shall be used at the interface of two storage configuration areas in the spent fuel racks. Empty water cells may be substituted for fuel assemblies in all cases.

l Internal Interfaces in Reaion 1 Racks The interface between a closed packed fuel storage area in Region 1 and a checkerboarded storage area also in Region 1 shall be such that either:

Category 3 or 4 fuel assemblies in the checkerboard pattern are 1,

carried into the first row of the close packed storage area of fuel, as shown in Figure 5.6-5; or, 2.

at least one row of empty water cells separate a close packed fuel storage ares.wd a checkerboarded storage area.

Internal Interf aces in Reaion 2 Rach The interface between a close packed fuel storage area in Region 2 and a checkerboarded storage area in Region 2 shall De such that either:

1.

there is a one row carryover of alternating empty celis from the checkerboard area-into the first row of the close packed area with the remaining cells of the row filled with Category 4 assemblies, as shown in Figure 5.6-6; or, 2.

at least one empty row of cells separates the checkerboard pattern area and the close packed storage area.

Reaion 1 Close Packed Storace Area Adjacent to Reaion 2 Close Packed Area There are no restrictions on the interface between Region 1 close packed stt age areas and-adjacent close packed storage areas in Region 2.

SOUTH TEXAS - UNITS 1 & 2 5-8 Unit 1 - Amendment No. 43 Unit 2 - Amendment No. 32 m-Y-'F

DESIGN FEATURES Reaion 1 Checkerboard Storaae Area Ad_iacent to Reaion 2 The interface between a checkerboarded storage area in Region 1 and any Region 2 rack storage area shall be such that either:

1.

the Region I checkerboard pattern is carried to the Region 1 boundary, but the last row at the Region 1 boundary leaves the Category 1 fuel assembly positions _ vacant; or, 2.-

at least one row of empty water cells in either Region 1 or Region 2 racks separate the Region 1 checkerboarded storage area and the Region 2 rack storage area.

Reaion 2 C.h_e_ckerboard Storaae Area Ad_iacent to Reaion 1 The interface between a checkerboarded storage area in Region 2 and any Region I L

rack storage area shall be such that at least one row of empty water cells in either Region 1 or Region 2 racks separate the Region 2 checkerboarded storage area and the Region 1 rack storage area.

-If checkerboarded storage areas in both Regions 1 and 2 are adjacent, at least one row of empty water cells in either Region 1 or Region 2 racks shall separate

-the checkertoarded storage areas in the respective racks.

5.6.1.6 The: minimum boron concentration specified by Specification 3.9.13, Spent fuel Pool Minimum Boron Concentration" ensures that the rack K,, limit-in Specification 5.6.1.1.a will not be violated under the following scenarios:

~

1.

in Region _l, any misloading of Category 1, 2, 3, end-4 assemblies; or, 2.

_in Region 2, the misloading of one Category 1 assembly into the center of a fully loaded checkerboard area also containing Category 1 assem-blies;_or, 3.

-the.misloading of a Category 1 assembly in a Region I rack adjacent to

- a Category 1 assembly in a Region 2 rack.

DRAINAGE

-5.6.2_ The spent _ fuel storage pool is designed and shall be maintained to prevent inadvertent _ draining of the pool below elevation 62. feet-6 inches.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity' limited to no more than 1969 fuel assemblies.

i

[

-SOUTH TEXAS - UNITS 1

  • 2-5-9 Unit 1 - Amendment No. 43 Unit 2 - Amendment No. 32

i Minimum Burnup for Category 2 Fuel j

6,000 i

Initial Enrichment Minimum Bumup m

(w/o)

(MWD /MTU)

'D 5,000 7 4.o o

I--2 4.5 2,700

.C 5.0 5,400 3 4,000 t_

s

~

3,000 g

co

-r

-! Acceptable UNACCEPTABLE

- 2,000 g

E q)

U) y 1,000

/

I 4.0 4.2 4.4 -

4.6 4.8 5.0 Initial Enrichment (w/o)

Assemblies with an initial enrichment less than 4.0 w/o are ACCEPTABLE Figure 5.6-1 SOUTH TEXAS - UNITS 1 & 2 5-10 Unit 1 - Anenament No. 43 Unit 2 - Amendment No. 32

p t

f.

Minimum IFBA Content for Category 2 Fuel 100

-~

=-

}

wi.i gr nm.nt uin g g t.nt g

90 y o

{

~

4' 2

t (2

1e 80 O.

,e 43

<(

4e e4 CD 70 I

7 so ao i

/

E

+

60 -

/

O 7

i

/

D /

E EAcceptable

[ U ACCEP

> BLE l

30 E

s 20 7

2 i

/

-j

.l.

g 0-4.0 4.2 4.4 4.6 4.8 5.0 Initial Enrichment (w/o)

Assemblies with an initial enrichment less than 4.0 w/o are ACCEPTABLE s'igure 5.6-2 SOUTH TEXAS - UNITS 1 & 2 5-11 Unit 1 Amendment No. 43 Unit 2 - Amendment No. 32 L

_--___________j

4 Minimum Burnup for Category 3 Fuel 20,000 InitialEnrichment Minimum Bumup (w/c)

(MWD /MTU) -

)

p 2.8 0

f E 15,000 1,800 3.5 6,000 10,000

/

4.0

~

4.5 13,750

~

5.0 17,500

.v a..

@ 10,000 ma co Acceptable UNACCEPTABLE x

l 25

/

I E-5,000

~

g m-W

---<C f.

.5 0

3 4.0 4.5 5.0 3.0 Initial Enrichment (w/o)-

Assemblies with an initial enrichment less than 2.8 w/o are ACCEPTABLE Figure 5.6-3 1

SOUTH TEXAS - UNITS _.1 & 2 5-12 Unit 1 - Amendment No. 43 Unit 2 - Amendment No. 32 w..w

+

y-9 g

i Minimum Burnup for Category 4 Fuel 45,000 j

~ Initial Enrichmerit Minimum Bumup

./

j (w]o}

(MWDLMWU)_

~.7 0

40,000

((

1 2.0 7,000 3

2.5

%,500 H

I 3.0 20,000 2 3S'000 -

3.5 25,800

/

L N

4.0 31,600

,/

O 4.5 36.000

/

5.0 42,000 i

g 30,000 7 g

v a 25,000 i

D C

l

/

$ 20,000 :! Acceptable 1 RB M.defe34.aff :lta co I

p 15,000 f 7

E

~

/

8 :c,000 :

j e

<t

[

-I 5,000

~

I'

~

O 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial Enrichment (w/o)

Assemblies with an initial enrichment less than 1.7 w/o are ACCEPTABLE i

Figura 5.6 4

)i l

SOUTH TEXA5 - UNITS i & 2 5-13 Unit 1 - Ame'dment No. 43 Unit 2 - Amendment No. 32

9 3,

y Region 1 Close Packed and Checkerboard Fuel Storage A

close-packed storage 1

_.]

l lI jI lI ll

.,.]

l

!l l

[_.

3 l

)

?>

g i_

J E

a a

k A

G l!

!I II II lI l

ll

}

y checkerboard storage I

m l Oategory 1 cual Assembly N

h CattJory 3 or 4 Fuel Assembly

] 7.ategory 2. 3, or 4 Fues Assembly Figure 5.6-5 5-14 Unit 1 - Amendment No. 43

'30VTH TEXAS - UNITS 1 & 2 Unit 2 - Amendment No. 32 w

i Region 2 Close Packed and Checkerboard Fuel Storage 3

A close-packed storage 1

l l

y,,

f l.

..n -,I

.0 E M R2, L A i

_B B BMi 4

3 ggj e

l T

checkerboard storage T

l

, Category -4 Fuel Assembly Category 1,2, or 3 Fuel Assembly Water Cell Figure 5.6-6 SOUTH TEXx5 - UNITS 1 & 2 5-15 Unit 1 - Amendment No. 43 U. lit 2 - Amendment No. 32 l

l-

s_.....

3 i

DESIGN FEATURES 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT The components identified in Table 5.7-1 are designed and shall be 5.7.1 maintained within the cyclic or transient lim.'ts of Table 5.7-1.

SOUTH TEXAS - UNITS 1 & 2 5-16 Unit 1 - Amendment No. 43 Unit 2 - Amendirent No. 32

  • e i

TABLE 5.7-1

,oy COMPONENT CYCLIC:0R TRANSIENT LIMITS E

' CYCLIC OR DESIGN CYCLE 7

COMPCNENT TRANSIENT LIMIT OR TRANSIENT E

Reactnr Coolant System 200 heatup cycles at < 100*F/h Heatup cycle - T from < 200 F U

- and 200 cocidown cycles at to > 550 F.

"*9

[

' -< 100 F/h.

Cooldown cycle - T-from i

avg

> 550 F to 5 200 F 200 pressurizer cooldovn cycles Pressurizer cooldown cycle at < 200 F/h.

temperatures.from > 650 F to r

_ 200 F.

~

I 80 loss of load cycles, without

> 15% of RATED THERMAL POWER to

' immediate Turbine or Reactor trip.

D% of RATED. THERMAL POWER.

~

w q

- 40 cycles of loss-of-offaite Loss-of-offsite A.C. electrical A.C. electrical power.

E'F Electrica. System.

l 80 cycles of loss of flow in one loss of only one reactor reactor coolant 1(op.

coolant pump.

400 Reactor trip cycles.

100% to 0% of' RATED THERMAL POWER.

m-

- Id auxiliary spray Spray water temperature differential actuation cycles.

> 621 F.

ii EE

g. g 200 leak tests.

Pressurized to >.'485 psig.

&5 gg 10 hydrestatic pressure tests.

Pressurized to > 3110 psig.

r*

55 Secondary Coolant System:

1 steam.line break.

Break in a > 6-inch steam line.

ww"(

10 hydrostatic pressure tests.

Pressurized to > 1600 psig.

w i

n 4

m w

w

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