ML20030A142

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Transmittal Email Background Information for Feb 13, 2020 Pre-submittal Meeting EPRI Data Validation Topical Report
ML20030A142
Person / Time
Site: Nuclear Energy Institute
Issue date: 01/30/2020
From: Vaughn S
Nuclear Energy Institute
To: Joseph Holonich
Licensing Processes Branch
Holonich, 415-7297
References
Download: ML20030A142 (2)


Text

From: VAUGHN, Stephen To: Holonich, Joseph Cc: kcrytzer@epri.com

Subject:

[External_Sender] Background Information in Support of the 2/13 Pre-submittal Meeting "DVR Topical Report" Date: Thursday, January 30, 2020 9:50:06 AM Attachments: DVR Topical Report NRC Summary_Final.pdf

Joe, Please find the attached summary of the Data Validation and Reconciliation (DVR) Topical Report to support a 2/13 pre-submittal meeting. We hope that the details in the summary will 1) help the NRC technical staff gain a more detailed understanding of the DVR methodology and 2) help inform which NRC branches and technical disciplines will be needed to support the Topical Report review.

In support of objective 2) above, we also gathered some licensing guidance that we believe the DVR topical report will interface with and also technical capabilities and regulatory experience that will support the review process:

Licensing guidance:

RG 1.197 Emphasis is on Type D Category 3 items Recalibration of Measurement Devices M&TE for 2% Core Power Uncertainty RG 1.105 At this point the methodology does not create a new reactor trip, nor changes the biases, uncertainties for equipment that is important for reactor setpoints. As such, do not envision changes to licensees FSAR related to safeguards.

RG 1.152 SQA Life Cycle of Software RG 1.173 Life Cycle of software RG 1.181 Not anticipating, but for some licensees there could be potential changes to Sections 7 and 15 of FSAR and would need to evaluate prior to implementation RIS 2002-03 Some licensees may want to use DVR for MUR BTP 7-14, Revision 5 Sections A.3.1, A.3.2, and B.3.3 Technical Capabilities/Review Experience:

Statistics Linear Algebra Numerical Analysis Balance of plant (BOP) Systems and Thermal Performance Core Thermal Power (CTP) Calculations, Ultrasonic Flow Meter (UFM)/Leading Edge Flow Meter (LEFM) Systems/Calculations, Measurement Uncertainty Recapture (MUR) Licensing Reviews Instrumentation, Calibrations, and Measurement Uncertainty

Regards, Steve STEPHEN J. VAUGHN l SENIOR PROJECT MANAGER, ENGINEERING AND RISK 1201 F Street, NW, Suite 1100 l Washington, DC 20004 P: 202.739.8163 M: 202.256.5393 sjv@nei.org This electronic message transmission contains information from the Nuclear Energy Institute, Inc. The information is intended solely for the use of the addressee and its use by any other person is not authorized. If you are not the intended recipient, you have received this communication in error, and any review, use, disclosure, copying or distribution of the contents of this communication is strictly prohibited. If you have received this electronic transmission in error, please notify the sender immediately by telephone or by electronic mail and permanently delete the original message. IRS Circular 230 disclosure: To ensure compliance with requirements imposed by the IRS and other taxing authorities, we inform you that any tax advice contained in this communication (including any attachments) is not intended or written to be used, and cannot be used, for the purpose of (i) avoiding penalties that may be imposed on any taxpayer or (ii) promoting, marketing or recommending to another party any transaction or matter addressed herein.

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