ML20096E861

Proposed Tech Specs,Providing Approved Revs to TS 6.9.1.9 to Incorporate Anticipated Revs to TRs DPC-NE-3000P-A & DPC-3002-A

ML20096E861
Person / Time
Site:	Catawba
Issue date:	01/19/1996
From:	DUKE POWER CO.
To:
Shared Package
ML20096E849	List: ML20096E845 ML20096E861
References
NUDOCS 9601230055
Download: ML20096E861 (1)

Text

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i ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 5.

DPC-NE-20llP-A, " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," March, 1990 (DPC Proprietary).

(Methodology for Specifications 2.2.1 - Reactor Trip System l

Instrumentation Setpoints, 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)

6.

DPC-NE-300lP-A, " Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," November 1991 (DPC Proprietary).

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coeffi-cient, 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)

7.

DPC-NF-2010A, " Duke Power Company McGuire Nuclear Station Catawba Nuclear l

Station Nuclear Physics Methodology for Reload Design," June 1985 (Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, Specification 4.7.13.3 - Standby Makeup Pump Water Supply

(

Boron Concentration, and Specification 3.9.1 - RCS and Refueling Canal Boron Concentration, and Specification 3.9.12 - Spent Fuel Pool Boron Concentration.) (l6 VIS/ W 1

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3 8.

DPC-NE-3002A "FSAR Chapter 15 System Transient Analysis Methodology,"

"e.e. kr 1901. 56R ABfd.bmgg /1g (Methodology used in the system thermal-hydraulic analyses which determine the core operating limits)

& 86V19N.f DPC-NE-3000P-A,4"ThermaT-Hydra.)lic Transient Analysis Methodology,"

9.

u A;5ust 19WSSR b/)TEb b6CFA0Ck 19W (Modeling used in the system thermal-hydraulic analyses) k CATAWBA-UNITS 1k2 6-19a Amendment No.138 (Unit 1) 9601230055 960119 Amendment No. 132 (Unit 2)

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