ML20069H075

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Proposed TS Page 6-19a,including Two Addl DPC Topicals Used in Reload Analysis Methodology & Ref All Applicable TS Parameters Determined Using Methodology
ML20069H075
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 05/31/1994
From:
DUKE POWER CO.
To:
Shared Package
ML20069H062 List:
References
NUDOCS 9406100298
Download: ML20069H075 (2)


Text

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ATTACII.TIENT I PROPOSED TECIINICAL SPECIFICATION CIIANGES FOR CATAWilA b

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CORE OPERATING LIMITS REPORT (Continued) 7.

OPC-NF-2010P-A, " Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design," June 1985 (DPC Proprietary).

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)

8.

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

November 1991.

(Methodology used in the system thermal-hydraulic analyses which determine the core operating limits) 9.

DPC-NE-3000P-A, Rev. 1, " Thermal-Hydraulic Transient Analysis Methodology," November 1991.

(Modeling used in the system thermal-hydraulic analyses)

10. DPC-NE-1004A, " Design Methodology Using CASMO-3/ Simulate-3P," November 1992.

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)

The core operating limits shall be deterni.7ed so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supple-ments thereto, shall be provided upon issuance, for each reload cycle, to the NRC in accordance with 10 CFR 50.4.

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CATAWBA - UNITS 1 & 2 6-19a Amendment No. 1 (Unit 1)

Amendment No.

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