ML070300425

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Tech Spec Pages for Amendment 173 Regarding Changes to the Analytical Methods Referenced in Technical Specification 5.6.5, Core Operating Limits Report (Colr).
ML070300425
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 02/22/2007
From:
NRC/NRR/ADRO/DORL/LPLIV
To:
Vaidya B, NRR/DORL/LP4, 415-3308
Shared Package
ML070300343 List:
References
TAC MD1496
Download: ML070300425 (3)


Text

(b) SERI is required to notify the NRC in writing prior to any change in (i) the terms or conditions of any new or existing sale or lease agreements executed as part of the above authorized financial transactions, (ii) the GGNS Unit 1 operating agreement, (iii) the existing property insurance coverage for GGNS Unit 1 that would materially alter the representations and conditions set forth in the Staff's Safety Evaluation Report dated December 19, 1988 attached to Amendment No. 54.

In addition, SERI is required to notify the NRC of any -action-by a lessor or other successor in interest to SERI that may have an effect on the operation of the facility.

C. The license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level Entergy Operations, Inc. is authorized to operate the facility at reactor core power levels not in excess of 3898 megawatts thermal (100 percent power) in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 173 are hereby incorporated into this license. Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The Surveillance Requirements (SRs) for Diesel Generator 12 contained in the Technical Specifications and listed below, are not required to be performed immediately upon implementation of Amendment No. 169.

The SRs listed below shall be successfully demonstrated at the next regularly scheduled performance.

SR 3.8.1.9, SR 3.8.1.10, and SR 3.8.1.14 4 Amendment No. 173

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Core OperatinQ Limits Report (COLR) (continued)

10. ANF-524(P)(A), "ANFCritical Power Methodology for Boiling Water Reactors", Advanced Nuclear Fuels Corporation, Richland, WA
11. ANF-913(P)(A), Volume 1, "CONTRANSA2: A Computer Program for Boiling Water Reactor Transient Analysis", Advanced Nuclear Fuels Corporation, Richland, WA.
12. XN-NF-825(P).(A), "BWR/6 Generic Rod- Withdrawal Error Analysis, MCPRp for Plant Operations within the Extended Operating Domain", Exxon Nuclear Company, Inc.,

Richland, WA.

13. ANF-1358(P)(A), "The Loss of Feedwater Heating Transient in Boiling Water Reactors", Advanced Nuclear Fuels Coporation, Richland, WA.
14. EMF-1997(P)(A), "ANFB-1O Critical Power Correlation";

Siemens Power Corporation, Richland, WA.

15. EMF-1997(P) Supplement 1 (P)(A), "ANFB-1O Critical Power Correlation: High Local Peaking Results", Siemens Power Corporation, Richland, WA.
16. EMF-2209(P)(A), "SPCB Critical Power Correlation", Siemens Power Corporation, Richland, WA.
17. EMF-2245(P)(A), "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel", Siemens Power Corporation, Richland, WA.
18. EMF-2361(P)(A), "EXEM BWR-2000 ECCS Evaluation Model,"

Framatome ANP Richland, Inc.

19. Deleted
20. Deleted (continued)

GRAND GULF 5.0-20 Amendment No. 4-4-4, 173

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Core Operating Limits Report (COLR) (continued)

21. Deleted
22. EMF-CC-074(P)(A), Volume 4, "BWR Stability Analysis Assessment of STAIF with Input from MICROBURN-B2",

Siemens Power Corporation, Richland, WA.

23. EMF-2292(P)(A), "ATRIUM-IO Appendix K Spray Heat Transfer Coefficients", Siemens Power Corporation, Richland, WA.
24. NEDE-24011 -P-A, General Electric Standard Application for Reactor Fuel (GESTAR-II) with exception to the misplaced fuel bundle analyses as discussed in GNRO-96/00087 and the generic MCPR Safety Limit analysis as discussed in GNRO-96/00100, letters-from C. R. Hutchinson to USNRC.
c. The core operating limits shall be determined such that all 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.

GRANDGULF 5.0-21 Amendment No. 4-3-1-,4--46, 173