ML030360017
| ML030360017 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/04/2003 |
| From: | Macon W NRC/NRR/DLPM/LPD3 |
| To: | Skolds J Exelon Generation Co, Exelon Nuclear |
| Macon W, NRR/DLPM/LPDIII-02, 415-3965 | |
| References | |
| TAC MB6333, TAC MB6334 | |
| Download: ML030360017 (1) | |
Text
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
(continued)
- 10.
RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation
- Model, XN-NF-81-58(P)(A).
- 11.
XCOBRA-T:
A Computer Code for BWR Transient Thermal Hydraulic Core Analysis, XN-NF-84-105(P)(A).
- 12.
Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model, ANF-91-048(P)(A).
- 13.
SPCB Critical Power Correlation, EMF-2209(P)(A).
- 14.
Generic Mechanical Design Criteria for BWR Fuel Designs, ANF-89-98(P)(A).
- 15.
NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel."
- 16.
Commonwealth Edison Topical Report NFSR-0085, "Benchmark of BWR Nuclear Design Methods."
- 17.
Commonwealth Edison Topical Report NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods."
- 18.
ANFB Critical Power Correlation Application for Coresident Fuel, EMF-1125(P)(A).
- 19.
ANFB Critical Power Correlation Determination of ATRIUM-9B Additive Constant Uncertainties, ANF-4125(P)(A).
- 20.
RODEX2A (MWR)
Fuel Rod Thermal-Mechanical Evaluation
- Model, EMF-85-74(P)(A).
- 21.
Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, EMF-2158(P)(A).
The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).
(continued)
Amendment No. 159/145 5.6-4 LaSalle 1 and 2