RBG-45789, Report of Changes and Errors to 10CFR50.46
| ML17270A199 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/27/2017 |
| From: | Schenk T Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-45789 | |
| Download: ML17270A199 (3) | |
Text
Entergy Operations, Inc
~Entergy September 27, 2017 RBG-45789 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Reference:
River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 Report of Changes and Errors to 10CFR50.46 Letter RBG-47710, "Report of Changes and Errors to 10 CFR 50.46,"
dated September 12, 2016
Dear Sir or Madam:
There have been two notices of changes or errors associated with the RBS ECCS analysis since the last 10 CFR 50.46 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. 10 CFR 50.46 error notifications up to and including NL-2017-02 have been incorporated.
GNF3 remains the limiting fuel type with a PCT of 1830°F. The PCT for the GNF3 fuel remains below the 2200°F acceptance criteria of 10 CFR 50.46.
RBG-45789 Page 2 of 3 Notification Letter Current Periods NL-2017-01 NL-2017-02 Previous Periods NL-2014-04 NL-2014-03 NL-2014-02 NL-2014-01 NL-2012-01 NL-2011-03 NL-2011-02 Nature Of Change / Error
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Input error in GNF2 fuel channel & L TP interface features, leaving default input for backflow leakage through these paths not consistent with GNF2 design.
Inputs for fuel rod plenum temperature modeling are updated to be reflective of current 1 Ox1 0 fuel bundle rod design without a getter included in the fuel rod plenum.
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" ",',,:)':t SAFER04A E4 - Bundle I Lower Plenum CCFL Head SAFER04A E4 - Minimum Core DP Model SAFER04A E4 - Mass Non-Conservatism SAFER04A E4 - Maintenance Update Changes PRIME Fuel Properties Implementation for Fuel Rod TIM Performance, replacing GESTR Fuel Properties Impact of updated formulation for gamma heat deposition to channel wall for 9x9 and 1 Ox1 0 fuel bundles Impact of database error for heat deposition on the Peak Cladding Temperature (PCT) for 1 Ox1 0 fuel bundles Net of errors / changes Sum of absolute magnitude of changes / errors This letter does not contain any commitments.
For further information, please contact me at (225) 381-4177.
Sincerely, TAS/aic Estimated PCT Effect (OF)
GNF2 GNF3 J§t~r~~(> (> ':rr':"
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0 NA 0
0
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0 0
-15
-15 0
0 0
0 45 45
-40
-40 25 25 15 15 125 125
RBG-45789 Page 3 of 3 cc: U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.
Arlington, TX 76011-4511 NRC Senior Resident Inspector P. O. Box 1050 S1. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Attn: Ms. Lisa Regner MS 08H04 One White Flint North 11555 Rockville Pike Rockville, MD 20852 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 RBF1-17 -0077