ML20065A924
| ML20065A924 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/28/1994 |
| From: | TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20065A912 | List: |
| References | |
| NUDOCS 9404010111 | |
| Download: ML20065A924 (2) | |
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ATTACHMENT 3 to TXX-94057 AFFECTED TECHNICAL SPECIFICATION PAGE (NUREG - 1468)
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9404010111 940328 PDit ADOCK 05000445 P
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r 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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