RBG-47168, Report of Changes and Errors to 10CFR50.46
| ML11221A163 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/04/2011 |
| From: | Clark J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-47168 | |
| Download: ML11221A163 (3) | |
Text
SEntergy Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775
-,M -~
-O A1-7 Joseph A. Clark Manager, Licensing August 4, 2011 RBG-47168 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 Report of Changes and Errors to 1 OCFR50.46
References:
- 1. Letter RBG-47055, "Report of Changes and Errors to 10CFR50.46," dated July 20, 2010.
- 2. Letter RBG-46943, ""Supplement to Amendment Request Changes to Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," dated August 12, 2009.
Dear Sir or Madam:
In accordance with 10 CFR 50.46 (a)(3)(ii), River Bend Station (RBS) is required to report to the Commission, at least annually, the estimated effect on the limiting Emergency Core Cooling System (ECCS) analysis caused by changes to or errors discovered in acceptable ECCS evaluations for information.
With the cumulative sum of the absolute magnitude being greater than 50°F this report is also submitted in accordance with 10 CFR 50.46 (a)(3)(i).
RBG-47168 Page 2 of 3 There have been two notices of changes or errors associated with the RBS ECCS analysis since the last 10CFR50.46 report provided to the NRC [Reference 1]. The table below summarizes the effects on the current ECCS analysis performed by General Electric - Hitachi Nuclear Energy (GEH) using their NRC approved SAFER/GESTR - LOCA methodology.
Estimated PCT Effect Notification Nature of change A10 GE14 GNF2 NL-2011-02 Impact of database error for heat deposition on 25 25 25 the Peak Cladding Temperature (PCT) for 10x1O fuel bundles NL-2011-03 Impact of updated formulation for gamma heat
-40
-40
-40 deposition to channel wall for 9x9 and 1 Ox1 0 fuel bundles Sum of absolute magnitude of errors during this period 65 65 65 Cumulative sum of absolute magnitude of errors prior to this period 0
0 0
Cumulative sum of absolute magnitude of errors including this 65 65 65 period 65 65 65 Since the last 10 CFR 50.46 report provided to the NRC [Reference 1], RBS loaded a new fuel type (GNF2). The RBS core is now comprised of ATRIUM-10 (A10), GE14, and GNF2 fuel types. However, the ATRIUM-10 fuel remains the limiting fuel type with a licensing basis PCT <1810°F as reported in Reference 2, which is well below the 2200°F acceptance criterion of 10 CFR 50.46.
RBS remains in compliance with 10 CFR 50.46 as these two errors / changes result in a net reduction in PCT. Therefore, there is no need for re-analysis.
This letter does not contain any commitments.
For further information, contact me at (225) 381-4157.
Sincerely, Manager, Licensing River Bend Station - Unit 1 JAC/bmb
RBG-47168 Page 3 of 3 cc: Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS 0-8 B1 Washington, DC 20555-0001 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section JiYoung Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312