ML18121A246

Draft Safety Evaluation for the Electric Power Research Institute (EPRI) Topical Report 3002010613, Benchmarks for Qualifying Fuel Reactivity Depletion Uncertainty Revision 1 and Topical Report 3002010614, Utilization of the EPRI Depletion

ML18121A246
Person / Time
Site:	99902028
Issue date:	05/31/2018
From:	Dennis Morey NRC/NRR/DLP/PLPB
To:	Mccullum R Nuclear Energy Institute
Benney B
Shared Package
ML18121A243	List: ML18121A245 ML18121A246
References
3002010613, 3002010614
Download: ML18121A246 (3)

Text

May 31, 2018 Mr. Rod McCullum, Senior Director, Fuel & Decommissioning Nuclear Energy Institute 1201 F Street, NW, Suite 1100 Washington, DC 20004

SUBJECT:

DRAFT SAFETY EVALUATION FOR THE ELECTRIC POWER RESEARCH INSTITUTE (EPRI) TOPICAL REPORT 3002010613, BENCHMARKS FOR QUALIFYING FUEL REACTIVITY DEPLETION UNCERTAINTYREVISION 1 AND TOPICAL REPORT 3002010614, UTILIZATION OF THE EPRI DEPLETION BENCHMARKS FOR BURNUP CREDIT VALIDATION REVISION 1

Dear Mr. McCullum:

By letter dated January 3, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13004A392), Nuclear Energy Institute (NEI) submitted NEI 12-16, Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants, Revision 0 (ADAMS Accession No. ML130840163) to the NRC for review and endorsement through a regulatory guide.

Subsection 4.2.3, PWR Depletion Bias and Uncertainty, references two reports created by the Electric Power Research Institute (EPRI) detailing methods for validating pressurized water reactor (PWR) criticality calculations that credit depleted fuel in spent fuel pool storage configurations. One report, Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty (ADAMS Accession No. ML18088B397), details the use of flux map data to infer the uncertainty associated with depletion reactivity calculations using Studsvik Scandpowers CASMO-5 and SIMULATE-3 reactor analysis tools. The other report, Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation, relates to the benchmark report by providing eleven calculational PWR depletion benchmarks allowing for determination of an application-specific depletion reactivity bias adjustment (ADAMS Accession No. ML18088B395).

The NRC staff found that the reports provide a sufficient technical basis for the determination of depletion code bias and uncertainty as part of a SFP criticality safety uncertainty analysis application.

Twenty working days are provided for you to provide any factual errors or clarity concerns contained in the SE. The final SE will be issued after making any necessary changes. The NRC staff's disposition of your comments on the draft SE will be discussed in the final SE.

R. McCullum To facilitate the NRC staff's review of your comments, please provide a marked-up copy of the revised draft SE showing proposed changes and provide a summary table of the proposed changes.

If you have any questions, please contact Brian Benney at 301-415-2767.

Sincerely,

/RA/

Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902028

Enclosure:

Draft Safety Evaluation

ML18121A246 (Letter); ML18121A245 (Enclosure);

ML18121A243 (Package); *concurrence via e-mail NRR-106 OFFICE NRR/DLP/PLPB NRR/DLP/PLPB* NRR/DSS/SNPB NRR/DLP/PLPB NAME BBenney DHarrison RLukes DMorey DATE 5/31/18 5/24/18 4/17/18 5/31/18