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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Dr. Peter C. Riccardella, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | ||
==SUBJECT:== | ==SUBJECT:== | ||
ACRS ASSESSMENT OF THE QUALITY OF SELECTED NRC RESEARCH PROJECTS - FY 2019 | ACRS ASSESSMENT OF THE QUALITY OF SELECTED NRC RESEARCH PROJECTS - FY 2019 | ||
==Dear Dr. Riccardella:== | ==Dear Dr. Riccardella:== | ||
Thank you for the Committees recent {{letter dated|date=May 3, 2019|text=letter dated May 3, 2019}} (ADAMS Accession No. ML19123A246), transmitting the report entitled, ACRS Assessment of the Quality of Selected NRC Research Projects - FY 2018. This annual report assists the NRC staff in evaluating the quality and usefulness of selected programs to support licensing and related regulatory functions of the agency. | |||
Thank you for the Committees recent letter dated May 3, 2019 (ADAMS Accession No. ML19123A246), transmitting the report entitled, ACRS Assessment of the Quality of Selected NRC Research Projects - FY 2018. This annual report assists the NRC staff in evaluating the quality and usefulness of selected programs to support licensing and related regulatory functions of the agency. | |||
The purpose of this letter is to propose NRC research reports for ACRS consideration and review during FY 2019. The research candidate reports are listed here for your consideration: | The purpose of this letter is to propose NRC research reports for ACRS consideration and review during FY 2019. The research candidate reports are listed here for your consideration: | ||
Overview of Nuclear Data Uncertainty in SCALE and Application to | NUREG/CR-7249 Overview of Nuclear Data Uncertainty in SCALE and Application to Light Water Reactor Uncertainty Analysis NUREG/CR-7260 CFD Validation of Vertical Dry Cask Storage System NUREG-1921, Supplement 1 (Pending) | ||
EPRI/NRC-RES Fire Human Reliability Analysis Guidelines - | |||
Qualitative Analysis for Main Control Room Abandonment Scenarios - | |||
Sincerely, | Supplement 1 NUREG/CR-7244 Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions NUREG/CR-7246 Reliability Assessment of Remote Visual Examination NUREG/CR-7255 Seismic Isolation of Nuclear Power Plants using Elastomeric Bearings The RES staff values the Committees review and will use your suggestions to improve our research program. | ||
Sincerely, | |||
Raymond V. Furstenau Director of Nuclear Regulatory Research | /RA/ | ||
Raymond V. Furstenau Director of Nuclear Regulatory Research June 5, 2019 | |||
ML19156A010 OEDO-19-00236 OFFICE RES:FO | ML19156A010 OEDO-19-00236 OFFICE RES:FO RES:PMDA D:RES NAME N. DiFrancesco J. Zabel M. Case for R. Furstenau DATE 6/04/2019 6/04/2019 6/05/2019}} | ||
Latest revision as of 02:07, 5 January 2025
| ML19156A010 | |
| Person / Time | |
|---|---|
| Issue date: | 06/05/2019 |
| From: | Raymond Furstenau Office of Nuclear Regulatory Research |
| To: | Riccardella P Advisory Committee on Reactor Safeguards |
| DiFrancesco N | |
| Shared Package | |
| ML19134A265 | List: |
| References | |
| OEDO-19-00236 | |
| Download: ML19156A010 (2) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Dr. Peter C. Riccardella, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
ACRS ASSESSMENT OF THE QUALITY OF SELECTED NRC RESEARCH PROJECTS - FY 2019
Dear Dr. Riccardella:
Thank you for the Committees recent letter dated May 3, 2019 (ADAMS Accession No. ML19123A246), transmitting the report entitled, ACRS Assessment of the Quality of Selected NRC Research Projects - FY 2018. This annual report assists the NRC staff in evaluating the quality and usefulness of selected programs to support licensing and related regulatory functions of the agency.
The purpose of this letter is to propose NRC research reports for ACRS consideration and review during FY 2019. The research candidate reports are listed here for your consideration:
NUREG/CR-7249 Overview of Nuclear Data Uncertainty in SCALE and Application to Light Water Reactor Uncertainty Analysis NUREG/CR-7260 CFD Validation of Vertical Dry Cask Storage System NUREG-1921, Supplement 1 (Pending)
EPRI/NRC-RES Fire Human Reliability Analysis Guidelines -
Qualitative Analysis for Main Control Room Abandonment Scenarios -
Supplement 1 NUREG/CR-7244 Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions NUREG/CR-7246 Reliability Assessment of Remote Visual Examination NUREG/CR-7255 Seismic Isolation of Nuclear Power Plants using Elastomeric Bearings The RES staff values the Committees review and will use your suggestions to improve our research program.
Sincerely,
/RA/
Raymond V. Furstenau Director of Nuclear Regulatory Research June 5, 2019
ML19156A010 OEDO-19-00236 OFFICE RES:FO RES:PMDA D:RES NAME N. DiFrancesco J. Zabel M. Case for R. Furstenau DATE 6/04/2019 6/04/2019 6/05/2019