RA06-026, Cycle 12 Core Operating Limits Report: Difference between revisions

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| issue date = 04/15/2006
| issue date = 04/15/2006
| title = Cycle 12 Core Operating Limits Report
| title = Cycle 12 Core Operating Limits Report
| author name = Landahl S R
| author name = Landahl S
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:ExeIkDn, Exelon Generation Company, LLC www.exeloncorp.com LaSalle Ccunty Station Nuclear 2601 North 21V Road Marseille<., IL 61341-9757 RA06-213 April 15, 2006 United States Nuclear Regulatory Commission Attention:
{{#Wiki_filter:Exelon Generation Company, LLC     www.exeloncorp.com ExeIkDn, LaSalle Ccunty Station                                                             Nuclear 2601 North 21V Road Marseille<., IL 61341-9757 RA06-213 April 15, 2006 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Unit 1 Facility Operating License No. NPF-1 I NRC Docket No. 50-373 Subjec4::           Unit 1 Cycle 12 Core Operating Limits Report (COLR)
Document Control Desk Washington, D.C. 20555 LaSalle County Station, Unit 1 Facility Operating License No. NPF-1 I NRC Docket No. 50-373 Subjec 4:: Unit 1 Cycle 12 Core Operating Limits Report (COLR)The purpose of this letter is to advise you of the Exelon Generation Company, LLC (EGC)review and approval of the LaSalle Unit 1 Cycle 12 reload under the provisions of 10 CFR 50.59, "Changes, tests and experiments," and to transmit the Core Operating Limits Report (COLR) for Cycle 12, consistent with Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits From Technical Specifications." This report is being submitted in accordance with LaSalle County Station Technical Specification 5.6.5, "Core Operating Limits (COLFR)," item d.The reload licensing analyses performed for Cycle 12 utilized NRC approved methodologies.
The purpose of this letter is to advise you of the Exelon Generation Company, LLC (EGC) review and approval of the LaSalle Unit 1 Cycle 12 reload under the provisions of 10 CFR 50.59, "Changes, tests and experiments," and to transmit the Core Operating Limits Report (COLR) for Cycle 12, consistent with Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits From Technical Specifications." This report is being submitted in accordance with LaSalle County Station Technical Specification 5.6.5, "Core Operating Limits (COLFR)," item d.
The Unit 1 Cycle 12 core, which consists of NRC approved fuel designs developed by Global Nuclear Fuel (GNF) and Framatome Advanced Nuclear Fuel, Inc. (i.e., Framatome), was designed to operate within approved fuel design criteria provided in the Technical Specifications and related Bases. The core operating characteristics are bounded by the Updated Final Safety Analysis Report (UFSAR) allowable limits.EGC has performed a review of the relevant reload licensing documents, associated Bases, and references in accordance with 10 CFR 50.59. The review process concluded that the reload does not require NRC review and approval.Should you have any questions concerning this submittal, please contact Mr. Terrence W.Simpkin, Regulatory Assurance Manager, at (815) 415-2800.Respectfully, Susan R. Landahl Site Vice President LaSalle County Station Attachment cc: Regional Administrator  
The reload licensing analyses performed for Cycle 12 utilized NRC approved methodologies.
-NRC Region Ill NRC Senior Resident Inspector  
The Unit 1 Cycle 12 core, which consists of NRC approved fuel designs developed by Global Nuclear Fuel (GNF) and Framatome Advanced Nuclear Fuel, Inc. (i.e., Framatome), was designed to operate within approved fuel design criteria provided in the Technical Specifications and related Bases. The core operating characteristics are bounded by the Updated Final Safety Analysis Report (UFSAR) allowable limits.
-LaSalle County Station 4 OJ}}
EGC has performed a review of the relevant reload licensing documents, associated Bases, and references in accordance with 10 CFR 50.59. The review process concluded that the reload does not require NRC review and approval.
Should you have any questions concerning this submittal, please contact Mr. Terrence W.
Simpkin, Regulatory Assurance Manager, at (815) 415-2800.
Respectfully, Susan R. Landahl Site Vice President LaSalle County Station Attachment cc:       Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - LaSalle County Station                       4   OJ}}

Latest revision as of 20:04, 23 November 2019

Cycle 12 Core Operating Limits Report
ML061240359
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 04/15/2006
From: Landahl S
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA06-026
Download: ML061240359 (1)


Text

Exelon Generation Company, LLC www.exeloncorp.com ExeIkDn, LaSalle Ccunty Station Nuclear 2601 North 21V Road Marseille<., IL 61341-9757 RA06-213 April 15, 2006 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Unit 1 Facility Operating License No. NPF-1 I NRC Docket No. 50-373 Subjec4:: Unit 1 Cycle 12 Core Operating Limits Report (COLR)

The purpose of this letter is to advise you of the Exelon Generation Company, LLC (EGC) review and approval of the LaSalle Unit 1 Cycle 12 reload under the provisions of 10 CFR 50.59, "Changes, tests and experiments," and to transmit the Core Operating Limits Report (COLR) for Cycle 12, consistent with Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits From Technical Specifications." This report is being submitted in accordance with LaSalle County Station Technical Specification 5.6.5, "Core Operating Limits (COLFR)," item d.

The reload licensing analyses performed for Cycle 12 utilized NRC approved methodologies.

The Unit 1 Cycle 12 core, which consists of NRC approved fuel designs developed by Global Nuclear Fuel (GNF) and Framatome Advanced Nuclear Fuel, Inc. (i.e., Framatome), was designed to operate within approved fuel design criteria provided in the Technical Specifications and related Bases. The core operating characteristics are bounded by the Updated Final Safety Analysis Report (UFSAR) allowable limits.

EGC has performed a review of the relevant reload licensing documents, associated Bases, and references in accordance with 10 CFR 50.59. The review process concluded that the reload does not require NRC review and approval.

Should you have any questions concerning this submittal, please contact Mr. Terrence W.

Simpkin, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, Susan R. Landahl Site Vice President LaSalle County Station Attachment cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - LaSalle County Station 4 OJ