ML15268A020

Attachment 3, Fuel Thermal Conductivity Degradation Evaluation (Non-Proprietary)

ML15268A020
Person / Time
Site:	Waterford
Issue date:	09/23/2015
From:	Chisum M Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15268A013	List: ML15268A020 W3F1-2015-0062, Control Element Assembly Drop Times Submittal Request for Additional Information
References
CAW-15-4272, W3F1-2015-0062
Download: ML15268A020 (5)

Text

Attachment 3 to W3F1 -2015-0062 NON-PROPRIETARY - Fuel Thermal Conductivity Degradation Evaluation Contains 4 Pages to W3F1 -2015-0062 Page 1 of 4 Westinghouse Proprietary Class 2 Enclosure 3 to LTR-SCC-15-044 Attachment 2 of CE-15-284-NP, Revision 1 "Fuel Management Adjustment to [ ]*, to Reserve Margin for Thermal Conductivity Degradation" (3 pages not including this page) to W3FI1-2015-0062 Page 2 of 4 Westinghouse Non-Proprietary Class 3 0E-15-284-NP, Revision 1, Attachnm ent 2 Page 1 of 3 While FATES3B and its associated methods include margins to offset thermal conductivity degradation (TOD),

significant time and effort to quantify those margins would be required. In order to expedite the licensing process, the Waterford Unit 3 core design will retain margin to the [ ]jG used in non-LOCA and LOCA safety analyses.

The [ ],,c used in core design will be based on the FATES3B [I ]V, with an adjustment f J]C, The [ ],

will be determined[

]aas sumunarized in Table 1. This [ ]'

to account for the bumup dependent effects of TCD. The [ ]"' will be applied as[

j',' shown in Figure 1. All fuel loaded in future reloads will be shown to meet the[

]8.C listed in Table 1 compared to the bounding analysis.

These [I ]"x will be applied until a new licensing basis -long term fuel methodology is approved Waterford Unit 3. Upon NRC approval of a new long term fuel evaluation model and associated methods that explicitly account for thermal conductivity degradation (TCD) that is applicable to Water'ford Unit 3 design, Entergy will, within 6 months:

a. Demonstrate that Waterford Unit 3 safety analysis remain conservatively bounded in licensing basis analyses when compared to the NRC-approved new long term fuel evaluation model that is applicable to Waterford Unit 3 design, and/or

b. Provide a schedule for re-analysis using the NRC-approved new long term fuel evaluation model that is applicable to Waterford Unit 3 design for any affected licensing basis analyses.

Because there are differences in the predicted rod internal pressures between ZrB2 and U02 rods, the FATES3B

[ ]*' are different. Both [ ]"' will be [ ]"' to account for TOD, and examples of the required core design [ ]"' using the Table 1 [I ]V, based on the currently applied [ ]"' are included in Figures 2 and 3.

Table 1 a,c Core Engineering Memo Template Version 1-0 to W3F1 -201 5-0062 Page 3 of 4 Westinghouse Non-Proprietary Class 3 CE-15-284-NP, Revision 1, Attachment 2 Page 2 of 3 Figure 1 a,c Figure 2 a~c Core Engineering Memo Template Version 1-0 to W3F1 -2015-0062 Page 4 of 4 Westinghouse Non-Proprietary Class 3 CE-1S-284-NP, Revision 1, Attachment 2 Page 3 of 3

-Figure 3 aSc Core Engineering Memo Template Version 1-0