ML20035H500
| ML20035H500 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 04/26/1993 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20035H499 | List: |
| References | |
| NUDOCS 9305050160 | |
| Download: ML20035H500 (4) | |
Text
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ATTACHMENT 2 i
DUKE POWER COMPANY NCGUIRE NUCLEAR STATION PROPOSED TECHNICAL SPECIFICATION AMENDNENT REQUEST t
1 l
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9305050160 930426 PDR ADOCK 05000369 P
- ADMINISTRATIVE CONTROLS
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CORE OPERATING LIMITS REPORT 4.
BAW-101"oD Rev. 1, "B&W Loss-of-Coolant isccident Evaluation Model for Recircu g Steam Generator Plants," September, 1989 (B&W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor. )
5.
DPC-NE-2011P, " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," March, 1990 (DPC Proprietary).
2,, _ pe,g,c y, Sy,m,gg,,,,,,,yg g,,y,,
g (Methodology for Specification 3.1.3.5 - Shutdown Rod Insertion Limits, I
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.
OPC-NE-3001P, "Hultidimensional Reactor Transients and Safety Analysis l
Physics Parameter Methodology," March,1991 (DPC. Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coet'fi-cient, 3.1.3.5 - Shutdown-Rod Insertion Limits, 3.1.3.6 - Control Bank i
Insertion Limits, 3.2.1 - Axial FTux Difference, 3.2.2 - Heat Flu _x Hot,
Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Chann' l Factor.)
e 7.
DPC-NE-2010P, " Duke Pcwer Company McGurie Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design," April,1984 (DPC. Proprietary).
l (Met hodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)
i 8.
DPC-NE-3002, "FSAR Chapter 15 Syst'em Transient Analysis Methodology,"
l August 1991.
(Methodology used in the system' thermal-hydraulic analyses which determine the core operating limits) 9.
OPC NF-3000, Rev. 1, " Thermal-Hydraulic Transient Analysis Methodology,"
May 1989.
l (Modeling used in the system therma'l-hydraulic analyses) i The core operating limits shall be determined 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.
l The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upcn issuance, for each reload cycle.
to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.
McGUIRE - UNITS 1 and 2 6-21a Am t
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Amen 110 (Unit 2) a 1
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ATTACHMENT 3 DUKE POWER COMPANY CATAWBA NUCLEAR STATION PROPOSED TECHNICAL SPECIFICATION AMENDMENT REQUEST l
4 1
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F ADMINISTRA VE CONTROLS
. CORE OPERAT ING LIMITS REPORT * (Continued)
Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -
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tuclear Enthalpy Rise Hot Channel Factor.)
b 2.
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION " June 1983 (W Proprietary).
(Methodology for Specifications 3.2.1 - Axial. Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for F Methodology.)
q 3.
WCAP-10266-P-A Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL i
USING BASH CODE," March 1987, (}{ Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
4.
BAW-10168PA, Rev.1, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," January 1991 (BtW Proprietary). ~
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
5.
DPC-NE-2011P-A, " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors,"' March,1990 (DPC Proprietary) 1.%.I - Reuche 77ji Syste-,2asfemM:n cet.dx l
(Methodology for Specifications (3.1:3.5 - Shutdown Rod Insertion Limits, 8
l 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-3001P-A, " Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," November 1991 (DPC Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Tet.perature 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-2010P-A, " Duke Power Company McGuire Nu' clear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design," June 1985 (DPC Proprietary).
i (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)
CATAWBA - UNITS 1 & 2 6-19 Ame mot N a (Unit 1) 97 (Unit 2)
Amen F.
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