ML070770010

Technical Specifications, Issuance of Amendment Nos. 135 and 135 Revise Listing of LOCA and Non-LOCA Methodologies

ML070770010
Person / Time
Site:	Comanche Peak
Issue date:	03/26/2007
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Donohew J N, NRR/DORL/LP4, 415-1307
Shared Package
ML070770008	List: ML070770009 ML070770010
References
TAC MD0185, TAC MD0186
Download: ML070770010 (1)

Text

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 Core Onemtlna Limits Report LCOLRI (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-OO1 -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-SOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power level Using the LEFM4 System,' Revision 0, March 1997 and Caldon Engineering Report - 160P,

• Supplement to Topical Report ER-80P; Basis for a Power Uprate With the LEFMP" System," Revision 0, May 2000.

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

16) WCAP-10444-P-A, *Reference Core Report VANTAGE 5 Fuel Assembly,' September 1985.

17) WCAP-16025-P-A, NModified WRB-2 Correlation, WRB-2M, for Predicting Critical Heat Flux In 17x17 Rod Bundles for Modified LPD Mixing Vane Grids,* April 1999.

18) WCAP-130W0-P-A- "Westinghouse Fuel Assembly Reconstitution Evaluation Methodology,' July, 1993.

19) ERX-04-004-A, 'Replacement Steam Generator Supplement To TXU Power's Large and Small Break Loss Of Coolant Accident Analysis Methodologies,' Revision 0, March 2007.

20) ERX-04-005-A, 'Application of TXU Power's Non-LOCA Transient Analysis Methodologies to a Feed Ring Steam Generator Design,' Revision 0, March 2007.

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 Iirdts) of the safety analysis are met.

d. The COLR, Including any midoycle 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. 419.423 05