ML20134N784
| ML20134N784 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/21/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20134N777 | List: |
| References | |
| NUDOCS 9611270110 | |
| Download: ML20134N784 (2) | |
Text
',
Reporting Requirements l
5.6 5.6 Reporting Requirements 5.6.5 Core Operatina Limits Report (COLR) (continued)
- 10. XN-NF-85-74(P)(A), "RODEX2A (BWR): Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA.
- 11. XN-CC-33(P)(A),-"HUXY: A Generalized Multirod Heatup Code with 10CFR50 Appendix K Heatup Option," Exxon Nuclear Company, Inc., Richland, WA.
- 12. XN-NF-825(P)(A), "BWR/6 Generic Rod Withdrawal Error Analysis, MCPR, for Plant Operation Within the Extended Operating Domain," Exxon Nuclear Company, Inc., Richland, WA.
- 13. XN-NF-81-51(P)(A), "LOCA-Seismic Structural Response of an Exxon Nuclear Company BWR Jet Pump Fuel Assembly,"
Exxon Nuclear Company, Inc., Richland, WA.
- 14. XN-NF-84-97(P)(A), "LOCA-Seismic Structural Response of an ENC 9x9 BWR Jet Pump Fuel Assembly," Advanced Nuclear Fuels Corporation, Richland, WA.
- 15. XN-NF-86-37(P), "Ge.tric LOCA Break Spectrum Analysis for BWR/6 Plants," Exxon Nuclear Company, Inc., Richland, WA.
- 16. XN-NF-82-07(P)(A), " Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, Inc.,
Richland, WA.
i
- 17. XN-NF-80-19(A), Volumes 2, 2A, 28, & 2C, " Exxon Nuclear Methodology for Boiling Water Reactors EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA.
- 18. XN-NF-79-59(P)(A), " Methodology for Calculation for Pressure Drop in BWR Fuel Assemblies," Exxon Nuclear Company, Inc., Richland, WA.
- 19. NEDE-240ll-P-A, General Electric Standard Application for Reactor Fuel (GESTAR-II) with exception to the misplaced fuel bundle analyses as discussed in GNR0-96/00087 and the generic MCPR Safety Limit analysis as discussed in GNR0-96/00100, letters from C. R. Hutchinson to USNRC.
- Items 19 and 20 of TS 5.6.5.b are applicabile only for Cycle 9 operation.
(continued)
GRAND GULF 5.0-20 Amendment No. 420, 131 9611270110 961121 PDR ADOCK 05000416 P
Reporting Requirements 5.6 o
5.6 Reporting Requirements 5.6.5 Core Operating Limits Report (COLR) (continued)
- 20. Jil-02863SLMCPR, Revision 1, "GGNS Cycle 9 Safety Limit l
'MCPR Analysis."
c.
The core operating limits shall be determined such that all l
applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
i
- Items 19 and 20 of TS 5.6.5.b are applicabile only for Cycle 9 l
operation.
l i
i 1
4 l
GRAND GULF 5.0-21 Amendment No. -144,131 1
l