ML071800155
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| ML071800155 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/28/2007 |
| From: | Mahesh Chawla NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Thomas J. Palmisano Nuclear Management Co |
| Chawla M, NRR/DORL, 415-8371 | |
| Shared Package | |
| ML071800293 | List: |
| References | |
| TAC MD2567, TAC MD2568 | |
| Download: ML071800155 (1) | |
Text
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR') (continued)
- 18. WCAP-7908-A, "FACTRAN - A FORTRAN IV Code for Thermal Transients in a U0 2 Fuel Rod";
- 19. WCAP-7907-P-A, "LOFTRAN Code Description";
- 20. WCAP-7979-P-A, "TWINKLE - A Multidimensional Neutron Kinetics Computer Code";
- 21. WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code";
- 22. WCAP-11394-P-A, "Methodology for the Analysis of the Dropped Rod Event";
- 23. WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores";
- 24. WCAP-12910 Rev. 1-A, "'Pressurizer Safety Valve Set Pressure Shift";
- 25. WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis";
- 26. WCAP-14882-P-A, "RETRAN-02 Modeling and Qualification for Westinghouse Pressurized Water Reactor Non-LOCA Safety Analyses"; and
- 27. WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM)".
Prairie Island Unit 1 - Amendment No. 4-62 4-6 179 Units 1 and 2 5.0-36 Unit 2-Amendment No. 4-53.4-5-8 169