ML070520035

Tech Spec Pages for Amendments 181 and 168 Regarding Technical Specification 5.6.5, Core Operating Limits Report.

ML070520035
Person / Time
Site:	LaSalle
Issue date:	02/15/2007
From:	NRC/NRR/ADRO/DORL/LPLIII-2
To:
Sands S,NRR/DORL, 415-3154
Shared Package
ml062220400	List: ML070520035
References
TAC MD1356, TAC MD1357
Download: ML070520035 (2)

Text

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

4. The Rod Block Monitor Upscale Instrumentation Setpoint for the Rod Block Monitor-Upscale Function Allowable Value for Specification 3.3.2.1.

5. The OPRM setpoints for the trip function for SR 3.3.1.3.3.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. XN-NF-524(P)(A), "ANF Critical Power Methodology for Boiling Water Reactors."

2. ANF-913(P)(A), "COTRANSA 2: A Computer Program for Boiling Water Reactor Transient Analysis."

3. ANF-CC-33(P)(A), "HUXY: A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option."

4. XN-NF-80-19(P)(A), "Advanced Nuclear Fuel Methodology for Boiling Water Reactors."

5. XN-NF-85-67(P)(A), "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel."

6. EMF-CC-074(P)(A), Volume 4 - "BWR Stability Analysis:

Assessment of STAIF with input from MICROBURN-B2."

7. XN-NF-81-58(P)(A), "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model."

8. XN-NF-84-105(P)(A), "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis."

(continued)

LaSalle 1 and 2 5.6-3 Amendment No181 168

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

9. EMF-2209(P)(A), "SPCB Critical Power Correlation."

10. ANF-89-98(P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs."

11. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel."

12. NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods."

13. EMF-85-74(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model."

14. EMF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2."

15. NEDC-33106P, "GEXL97 Correlation for Atrium-i0 Fuel."

16. EMF-2245(P)(A), "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel."

17. EMF-2361(P)(A), "EXEM BWR-2000 ECCS Evaluation Model."

18. NEDO-32465-A, "BWR Owners' Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications," August 1996.

19. ANF-1358(P)(A), "The Loss of Feedwater Heating Transient in Boiling Water Reactors."

(continued)

LaSalle 1 and 2 5.6-4 Amendment No.1 81 / 1 68