ML18018A867: Difference between revisions
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| issue date = 01/09/2018 | | issue date = 01/09/2018 | ||
| title = 01-09-17 NRC NEI Supplementary Response to NRC RAIs on EPRI Report 10229. | | title = 01-09-17 NRC NEI Supplementary Response to NRC RAIs on EPRI Report 10229. | ||
| author name = Cummings K | | author name = Cummings K | ||
| author affiliation = Nuclear Energy Institute (NEI) | | author affiliation = Nuclear Energy Institute (NEI) | ||
| addressee name = Benney B | | addressee name = Benney B | ||
| addressee affiliation = NRC/NRR/DLP/PLPB | | addressee affiliation = NRC/NRR/DLP/PLPB | ||
| docket = PROJ0689 | | docket = PROJ0689 | ||
| license number = | | license number = | ||
| contact person = Benney B | | contact person = Benney B | ||
| case reference number = 1022909 | | case reference number = 1022909 | ||
| package number = ML18018A852 | | package number = ML18018A852 | ||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:KRISTOPHER W. | {{#Wiki_filter:KRISTOPHER W. CUMMINGS Sr. Project Manager, Used Fuel & | ||
Decommissioning Programs 1201 F Street, NW, Suite 1100 Washington, DC 20004 P: 202.739.8031 kwc@nei.org nei.org January 9, 2017 Mr. Brian J. Benney Senior Project Manager Licensing Processes Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | |||
, NW, Suite 1100 Washington, DC 20004 P: 202.739. | |||
-0001 | |||
==Subject:== | ==Subject:== | ||
Supplementary Response to Request for Additional Information Regarding EPRI Report 1022909, | Supplementary Response to Request for Additional Information Regarding EPRI Report 1022909, Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty Project Number: 689 | ||
==Dear Mr. Benney:== | |||
On behalf of the nuclear energy industry, the Nuclear Energy Institute (NEI) 1 is providing a supplementary response to the Request for Additional Information Questions related to EPRI Report 1022909 that were provided by the NRC to NEI via letter dated February 4, 2016 [Ref. 1]. This EPRI Report supports the guidance provided in NEI 12-16, Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants, Revision 2, which was submitted to the NRC on January 9, 2017 [Ref. 2] | |||
On behalf of the nuclear energy industry, the Nuclear Energy Institute (NEI)1 is providing a supplementary response to the Request for Additional Information Questions related to EPRI Report 1022909 that were provided by the NRC to NEI via letter dated February 4, 2016 [Ref. 1]. This EPRI Report | 1 The Nuclear Energy Institute (NEI) is the organization responsible for establishing unified industry policy on matters affecting the nuclear energy industry, including the regulatory aspects of generic operational and technical issues. NEI's members include all entities licensed to operate commercial nuclear power plants in the United States, nuclear plant designers, major architect/engineering firms, fuel cycle facilities, nuclear materials licensees, and other organizations and entities involved in the nuclear energy industry. | ||
-Water Reactor Power Plants | |||
, Revision 2 | |||
, which was submitted to the NRC on January 9, 2017 [Ref. 2] | |||
NEI's members include all entities licensed to operate commercial nuclear power plants in the United States, nuclear plant designers, major architect/engineering firms, fuel cycle facilities, nuclear materials licensees, and other organizations and entities involved in the nuclear energy industry. | |||
Mr. Brian J. Benney January 9, 2017 Page 2 We look forward to receiving the draft SER for these reports to support inclusion in the final version of NEI 12- | |||
: 16. EPRI plans to make available updated versions of EPRI Reports 1022909 and 1025203 no later than February 2017. I look forward to continuing to work with the NRC staff to finalize this important guidance document in the first quarter of 2017. Please do not hesitate to contact me at any time with questions. | |||
I look forward to continuing to work with the NRC staff to finalize this important guidance document in the first quarter of 2017 | Sincerely, Kristopher W. Cummings | ||
. Please do not hesitate to contact me at any time with questions. | |||
Sincerely, | |||
==References:== | ==References:== | ||
[1] Request for Additional Information Related to | [1] Request for Additional Information Related to Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty and Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation (ML16007A034) | ||
[2] Submittal of NEI 12-16, Guidance for Performing Criticality Analyses of Fuel Storage at Light | [2] Submittal of NEI 12-16, Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants, Revision 2 - DRAFT B, dated January 2017 : CASMO-5 95/95 Tolerance Limits for Measure Reactivity Decrement Biases of the EPRI Studsvik Burnup Benchmark (15 pages) : Data Used in EPRI Depletion Benchmark Analysis (61 pages) c: Mr. William M. Dean, NRR, NRC Mr. Brian McDermott, NRR, NRC Mr. Timothy J. McGinty, NRR/DSS, NRC Mr. Robert M. Taylor, NRR/DSS, NRC Mr. Eric Oesterle, NRR/DSS/SRXB, NRC Mr. Robert Lukes, NRR/DSS/SNPB, NRC Mr. Kent Wood, NRR/DSS/SNPB, NRC Mr. Amrit Patel, NRR/DSS/SNPB, NRC}} | ||
-Water Reactor Power Plants, Revision 2 | |||
- DRAFT B, dated January 2017 | |||
Data Used in EPRI Depletion Benchmark Analysis (61 pages) c: Mr. William M. Dean, NRR, NRC Mr. Brian McDermott, NRR, NRC Mr. Timothy J. McGinty, NRR/DSS, NRC Mr. Robert M. Taylor | |||
, NRR/DSS, NRC Mr. Eric Oesterle, NRR/DSS/SRXB, NRC Mr. Robert Lukes, NRR/DSS/SNPB, NRC Mr. Kent Wood, NRR/DSS/SNPB, NRC Mr. Amrit Patel, NRR/DSS/SNPB, NRC}} | |||
Latest revision as of 04:38, 22 October 2019
| ML18018A867 | |
| Person / Time | |
|---|---|
| Site: | Nuclear Energy Institute |
| Issue date: | 01/09/2018 |
| From: | Cummings K Nuclear Energy Institute |
| To: | Brian Benney NRC/NRR/DLP/PLPB |
| Benney B | |
| Shared Package | |
| ML18018A852 | List: |
| References | |
| 1022909 | |
| Download: ML18018A867 (2) | |
Text
KRISTOPHER W. CUMMINGS Sr. Project Manager, Used Fuel &
Decommissioning Programs 1201 F Street, NW, Suite 1100 Washington, DC 20004 P: 202.739.8031 kwc@nei.org nei.org January 9, 2017 Mr. Brian J. Benney Senior Project Manager Licensing Processes Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Supplementary Response to Request for Additional Information Regarding EPRI Report 1022909, Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty Project Number: 689
Dear Mr. Benney:
On behalf of the nuclear energy industry, the Nuclear Energy Institute (NEI) 1 is providing a supplementary response to the Request for Additional Information Questions related to EPRI Report 1022909 that were provided by the NRC to NEI via letter dated February 4, 2016 [Ref. 1]. This EPRI Report supports the guidance provided in NEI 12-16, Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants, Revision 2, which was submitted to the NRC on January 9, 2017 [Ref. 2]
1 The Nuclear Energy Institute (NEI) is the organization responsible for establishing unified industry policy on matters affecting the nuclear energy industry, including the regulatory aspects of generic operational and technical issues. NEI's members include all entities licensed to operate commercial nuclear power plants in the United States, nuclear plant designers, major architect/engineering firms, fuel cycle facilities, nuclear materials licensees, and other organizations and entities involved in the nuclear energy industry.
Mr. Brian J. Benney January 9, 2017 Page 2 We look forward to receiving the draft SER for these reports to support inclusion in the final version of NEI 12-
- 16. EPRI plans to make available updated versions of EPRI Reports 1022909 and 1025203 no later than February 2017. I look forward to continuing to work with the NRC staff to finalize this important guidance document in the first quarter of 2017. Please do not hesitate to contact me at any time with questions.
Sincerely, Kristopher W. Cummings
References:
[1] Request for Additional Information Related to Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty and Utilization of the EPRI Depletion Benchmarks for Burnup Credit Validation (ML16007A034)
[2] Submittal of NEI 12-16, Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants, Revision 2 - DRAFT B, dated January 2017 : CASMO-5 95/95 Tolerance Limits for Measure Reactivity Decrement Biases of the EPRI Studsvik Burnup Benchmark (15 pages) : Data Used in EPRI Depletion Benchmark Analysis (61 pages) c: Mr. William M. Dean, NRR, NRC Mr. Brian McDermott, NRR, NRC Mr. Timothy J. McGinty, NRR/DSS, NRC Mr. Robert M. Taylor, NRR/DSS, NRC Mr. Eric Oesterle, NRR/DSS/SRXB, NRC Mr. Robert Lukes, NRR/DSS/SNPB, NRC Mr. Kent Wood, NRR/DSS/SNPB, NRC Mr. Amrit Patel, NRR/DSS/SNPB, NRC