RBG-47902, Report of Changes and Errors to 10CFR50.46

Report of Changes and Errors to 10CFR50.46

ML18256A223
Person / Time
Site:	River Bend
Issue date:	09/13/2018
From:	Schenk T Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RBG-47902
Download: ML18256A223 (3)

Text

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Entergy Operations, Inc.

River Bend Station 5485 U.S. Highway 61 N St. FrancIsville. LA 70775 Tel 225*38t-4177 Timothy A. Schenk Manager, Regulatory Assurance September 13, 2018 RBG-47902 U.S. Nuclear Regulatory Commission Attn : Document Control Desk Washington , DC 20555

Subject:

Report of Changes and Errors to 10CFR50.46 River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 Reference : 1. Letter RBG-45789, "Report of Changes and Errors to 10CFR50.46,"

dated September 27,2017

Dear Sir or Madam :

There has been no notice 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.

Since the last 10 CFR 50.46 report provided to the NRC, RBS is currently in Cycle 20 with the RBS core composed of the GNF2 and GNF3 fuel types .

GNF3 is the limiting fuel type with a PCT of 1830°F incorporating 10 CFR 50.46 error notifications up to and including NL-2017-02. As can be seen the PCT for the GNF3 fuel remains well below the 2200 0 F acceptance criteria of 10 CFR 50.46.

RBG-47902 Page 2 of 3 Notification Nature Of Change I Error Estimated PCT Letter Effect (OF)

GNF2 GNF3 Previous Periods , '", . -;\~', ";'~" .\:

NL-2017-02 Inputs for fuel rod plenum temperature modeling 0 0 are updated to be reflective of current 10 x1 0 fuel bundle rod design without a getter included in the fuel rod plenum.

NL-2017-01 Input error in GNF2 fuel channel & LTP interface 0 NA features, leaving default input for backflow leakage through these paths not consistent with GNF2 design .

NL-2014-04 SAFER04A E4 - Bundle I Lower Plenum CCFL 0 0 Head NL-2014-03 SAFER04A E4 - Minimum Core DP Model -15 -15 NL-2014-02 SAFER04A E4 - Mass Non-Conservatism 0 0 NL-2014-01 SAFER04A E4 - Maintenance Update Changes 0 0 NL-2012-01 PRIME Fuel Properties Implementation for Fuel Rod 45 45 TIM Performance, replacing GESTR Fuel Properties NL-2011-03 Impact of updated formulation for gamma heat -40 -40 deposition to channel wall for 9x9 and 1Ox1 0 fuel bundles NL-2011 -02 Impact of database error for heat deposition on the 25 25 Peak Cladding Temperature (PCT) for 1Ox1 0 fuel bundles Net of errors I changes 15 15 Sum of absolute magnitude of changes I errors 125 125 This letter does not contain any commitments.

If you have any questions or require additional information , please contact Mr. Tim Schenk at (225) 381-4177 or tschenk@entergy.com .

TAS/bj

RBG-47902 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission Region IV 1600 E. Lamar Blvd.

Arlington, TX 76011-4511 U.S. Nuclear Regulatory Commission Attn : Ms. Lisa M. Regner, Project Manager 09-0-14 One White Flint North 11555 Rockville Pike Rockville, MO 20852 NRC Senior Resident Inspector Attn: Mr. Jeff Sowa 5485 U.S. Highway 61 , Ste. NRC St. Francisville, LA 70775 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312 Public Utility Commission of Texas Attn: PUC Filing Clerk 1701 N. Congress Avenue P. O. Box 13326 Austin , TX 78711-3326 RBF1-18-0181