ML051940457

Technical Specifications, Technical Specification 5.6.5, Core Operating Limits (COLR)

ML051940457
Person / Time
Site:	Comanche Peak
Issue date:	07/13/2005
From:	Thadani M NRC/NRR/DLPM/LPD4
To:	Blevins M TXU Power
Thadani M, NRR/DLPM, 415-1476
Shared Package
ML051950461	List: ML051470195 ML051940457
References
TAC MC4972, TAC MC4973
Download: ML051940457 (2)

Text

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 Core Operating Limits Report (COLR) (continued) allowing use of 100.6 percent of rated power in safety analysis methodology when the LEFMVI is used for feedwater flow measurement.

The approved analytical methods are described in the following documents:

1) WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (W Proprietary)

2) WCAP-10216-P-A, Revision 1A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F0 SURVEILLANCE TECHNICAL SPECIFICATION," February 1994 (W Proprietary).

3) RXE-90-006-P-A, "Power Distribution Control Analysis and Overtemperature N-1 6 and Overpower N-1 6 Trip Setpoint Methodology," June 1994.

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

5) RXE-88-102-P, Sup. 1, "TUE-1 DNB Correlation - Supplement 1,"

December 1990.

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

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

8) RXE-91-002-A, "Reactivity Anomaly Events Methodology,"

October 1993.

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

(continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0-33 Amendment No. 119

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 Core Operatiiq Limits Report (COLR) (continued)

10) TXX-88306, "Steam Generator Tube Rupture Analysis,"

March 15,1988.

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

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

13) RXE-95-001 -P-A, "Small Break Loss of Coolant Accident Analysis Methodology," September 1996.

14) Caldon, Inc. Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power level Using the LEFMJ System," Revision 0, March 1997 and Caldon Engineering Report - 160P, "Supplement to Topical Report ER-80P; Basis for a Power Uprate With the LEFMl m System," Revision 0, May 2000.

15) ERX-2001-005-P, "ZIRLOW Cladding and Boron Coating Models for TXU Electric's Loss of Coolant Accident Analysis Methodologies," October 2001.

16) WCAP-1 0444-P-A, "Reference Core Report VANTAGE 5 Fuel Assembly," September 1985.

17) WCAP-15025-P- A, "Modified WRB-2 Correlation, WRB-2M, for Predicting Critical Heat Flux in 17x17 Rod Bundles for Modified LPD Mixing Vane Grids," April 1999.

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. 119