ML20059E616
| ML20059E616 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 12/21/1993 |
| From: | Hallman G DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9401120066 | |
| Download: ML20059E616 (4) | |
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Duke Fbwer Company Electric Center j
R0 Bat 1006 1
1 Charlotte, N C 28201 1006 DUKEPOWER December 21,1993 l
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
McGuire Nuclear Station Units 1&'2 l
Docket Nos. 50-369,370 Catawba Nuclear Station Unit 1 Docket No. 50-413 Topical Reports Related to SG Replacement The replacement of the Steam Generators at McGuire Unit 1 and 2 and Catawba Unit I will require the revision of three approved Duke Power methodology topicals (DPC-NE-3000-PA, Thermal-Hydraulic Transient Analysis Methodology, DPC-NE-3001-PA, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology, and DPC-NE-3002-A, FSAR Chapter 15 System Transient Analysis Methodology). One new Duke Power methodology topical will be developed and used to support analysis required for the steam generator replacement (DPC-NE-3004, Mass and l
Energy Release and Containment Response Methodology). These topical repons will be submitted for review in June of 1994, and approval will be requested by June of 1995.
l The following is a brief description of the expected topical revisions and the new topical:
DPC-NE-3000-PA-Thermal-Hydraulic Transient Analysis Methodology This revision updates the RETRAN-02 models for McGuire and Catawba to reflect the changes in the nodalization necessary to model the replacement Babcock & Wilcox steam generators. The original steam generators are of the preheater design, and the replacement steam generators are of the feedring design. A summary of changes in plant r
operating conditions that will be implemented with the replacement steam generators will be given.
DPC-NE-3001-PA-Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology 9401120066 931221 Q(
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1 U.S. Nuclear Regulatory Commission December 21,1993 Page 2 This revision updates the FSAR Chapter 15 steam line break analysis to reflect the 3
changes in the steam generator design (feedring vs. preheater, change in heat transfer suface area, different initial conditions, etc.). Other than the physical changes in the steam generator and operating condition, the methodology will not change significantly.
DPC-NE-3002-A-FSAR Chapter 15 Transient Analysis Mehod logy This revision updates the methods for performing conservative analyses of the FSAR Chapter 15 transients to reflect any changes necessary due to the replacement steam generators.
DPC-NE-3004-Mass and Energy Release and Containment Response Methodology i
This topical report presents the methodology for analyzing the mass and energy release from high energy line breaks (LOCA and SLB) and the resulting containment thermal-hydraulic response. The RELAP5 MOD 3.2 code is used for LOCA. The RETRAN-02 MOD 5.1 code is used for SLB. The GOTHIC code is used for the ice condenser containment response. The analysis is performed for both the current Westinghouse Model D and the replacement Babcock & Wilcox steam generators. The GOTHIC code is validated for analysis of the ice condenser containment by comparison to ice condenser test facility data obtained from testing at Battelle Pacific Northwest Laboratories. This topical report will be similar to DPC-NE-3003 which is currently being reviewed by the staff for Oconee Nuclear Station.
Very truly yours, h
G. W. Hallman, Project Manager SGRP MHH
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U.S. Nuclear Regulatory Commission December 21,1993 Page 3 xc:
S. D. Ebneter Regional Administrator R. E. Martin, ONRR V. Nerses, ONRR R. J. Freudenburger Senior Resident Inspector (CNS)
G. S. Maxwell Senior Resident Inspector (MNS) i l-
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U.5. Nuclear Regulatory Commission December 21,1993 j
Page 3 l
xc:
M. S.. Tuckman A. V. Carr C. F. Robinson l
D. V. Ethington G. B. Swindlehurst T. R. Niggel M. E. Henshaw D. L. Rehn (CNS) l I
M. E. Patrick (CNS)
Z. L. Taylor (CNS)
M. S. Sills (CNS)
T. C. McMeekin (MNS) i l
M. R. Robinson (MNS)
R. O. Sharpe (MNS)
File; CN-1201.37-27 MC-1201.37-27 i
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