ML20065A924

Proposed TS Section 6.9.1.6b,reflecting Addition of Slb Methodology Topical Rept RXE-91-005 & Deletion of WCAP-9220-P-A

ML20065A924
Person / Time
Site:	Comanche Peak
Issue date:	03/28/1994
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20065A912	List: ML20065A909 ML20065A924
References
NUDOCS 9404010111
Download: ML20065A924 (2)

Text

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ATTACHMENT 3 to TXX-94057 AFFECTED TECHNICAL SPECIFICATION PAGE (NUREG - 1468) l

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Yttachment3toTXX-94057 Page 1 of 1 ADMINISTRATIVf CONTROLS CORE OPERATING LIMITS REPORT (Continued) 5). WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL F SURVEIL-LANCE TECHNICAL SPECIFICATION," June 1983 (M Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor (W(z) surveillance requirements for F Methodology).)

6). WCAP-10079-P-A, "NOTRUMP, A NODAL TRANSIENT SMALL BREAX AND GENERAL NETWORK CODE," August 1985, (M Proprietary). l 7). WCAP-10054-P-A, " WESTINGHOUSE SMALL BREAK ECCS EVALUATION MODEL USING )'

THE NOTRUMP CODE", August 1985, M Proprietary). l 8). WCAP-11145-P-A, " WESTINGHOUSE SMALL BREAX LOCA ECCS EVALUATION MODEL GENERIC STUDY WITH THE NOTRUMP CODE", October 1986, M Proprietary). l 9). RXE-90-006-P, " Power Distribution Control Analysis and Overtemperature N-16 and Overpower N-16 Trip Setpoint Methodology," February 1991.

(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 -

Heat Flux Hot Channel Factor.)

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

January 1989.

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

December 1990.

12). RXE-89-002, "VIPRE-01 Core Thermal-Hydraulic Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications", June 1989.

13). RXE-91-001, " Transient Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications", February 1991.

14). RXE-91-002, " Reactivity Anomaly Events Methodology", May 1991.

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion t.imit, 3.1.3.6 -

Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 -

Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)

15). RXE-90-007, "Large Break Loss of Coolant Accident Analysis Methodology", December 1990.

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

deference 17)isforUnit1o l, 17).(WCAP-9220-P-A,"WESTINGHOUSEECCSEVALUATIONMODEL, February 1978 (rsion," February 1978(XProprietary). _ ,

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sw l.nz b e< rz E ve n +s , " May , sM L COMANCHE PEAX - U $ M 2 " M nit 1 - Amen % ent No. 4,6,H ,48,21 Unit 2 - Amendment No. 4,7

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