ML022520325

Technical Specification Pages 4.0-1 & 5.0-34

ML022520325
Person / Time
Site:	Comanche Peak
Issue date:	09/04/2002
From:	NRC/NRR/DLPM
To:
References
TAC MB3101, TAC MB3102, TAC MB4740, TAC MB4741
Download: ML022520325 (2)

Text

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The site area is approximately 7,700 acres located in Somervell County in North Central Texas. Squaw Creek Reservoir (SCR), established for station cooling, extends into Hood County. The site is situated along Squaw Creek, a tributary of the Paluxy River, which is a tributary of the Brazos River. The site is over 30 miles southwest of the nearest portion of Fort Worth and approximately 4.5 miles north-northwest of Glen Rose, the nearest community.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of Zircaloy or ZIRLOTM clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing or that contain Westinghouse ZIRLOTM fuel rod cladding may be placed in non-limiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies. The control material shall be silver-indium-cadmium as approved by the NRC.

(continued)

COMANCHE PEAK - UNITS 1 AND 2 4.0-1 Amendment No. 95, 99

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Core Operating Limits Report (COLR, (continued)

10) RXE-88-102-P-A, "TUE-1 Departure from Nucleate Boiling Correlation", July 1992.

11) RXE-88-102-P, Sup. 1, "TUE-I DNB Correlation - Supplement 1", December 1990.

12) RXE-89-002-A, "VIPRE-01 Core Thermal-Hydraulic Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications", September 1993.

13) RXE-91-001-A, "Transient Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications", October 1993.

14) RXE-91-002-A, "Reactivity Anomaly Events Methodology", October 1993.

15) ERX-2000-002-P, "Revised Large Break Loss of Coolant Accident Analysis Methodology", March 2000.

16) TXX-88306, "Steam Generator Tube Rupture Analysis", March 15, 1988.

17) RXE-91-005-A, "Methodology for Reactor Core Response to Steamline Break Events," February 1994.

18) RXE-94-001-A, "Safety Analysis of Postulated Inadvertent Boron Dilution Event in Modes 3,4, and 5," February 1994.

19) RXE-95-001-P-A, "Small Break Loss of Coolant Accident Analysis Methodology,"

September 1996.

20) Caldon, Inc. Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power level Using the LEFMV System,"

Revision 0, March 1997 and Caldon Engineering Report - 160P, "Supplement to m System,"

Topical Report ER-80P: Basis for a Power Uprate With the LEFMV' Revision 0, May 2000.

21) ERX-2001-005-p, "ZIRLO'M Cladding and Boron Coating Models for TXU Electric's Loss of Coolant Accident Analysis Methodologies," October 2001.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-34 Amendment No. 89, 99