ML18152B142
| ML18152B142 | |
| Person / Time | |
|---|---|
| Issue date: | 06/04/2018 |
| From: | Michael Case NRC/RES/DSA |
| To: | Mirela Gavrilas NRC/NRR/DSS |
| Yarsky P | |
| Shared Package | |
| ML18152B127 | List: |
| References | |
| NRR-2016-009 | |
| Download: ML18152B142 (2) | |
Text
OFFICIAL USE ONLY - PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 4, 2018 MEMORANDUM TO: Mirela Gavrilas, Director Division of Safety Systems Office of Nuclear Reactor Regulation FROM: Michael J. Case, Director /RA/
Division of Systems Analysis Office of Nuclear Regulatory Research
SUBJECT:
DELIVERY OF FINAL DELIVERABLE ASSOCIATED WITH MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+) ANTICIPATED TRANSIENT WITHOUT SCRAM WITH INSTABILITY (ATWS-I) CONFIRMATORY ANALYSIS FOR BRUNSWICK STEAM ELECTRIC PLANT (BSEP) UNDER USER NEED NRR-2016-009 By memorandum dated May 19, 2016 the Office of Nuclear Reactor Regulation (NRR) requested that the Office of Nuclear Regulatory Research (RES) perform confirmatory analyses to support the licensing of Brunswick Steam Electric Plant (BSEP) license amendment request (LAR) to operate with the Maximum Extended Load Line Limit Analysis Plus (MELLLA+)
expanded operating domain (ADAMS Accession No. ML16088A106). In this request, NRR asked that RES perform calculations using the TRACE/PARCS code system of select Anticipated Transient without SCRAM (ATWS) scenarios leading to core instability (ATWS-I).
RES responded to the request via memorandum dated June 22, 2016 and tracks this user need under the identifier: NRR-2016-009 (ADAMS Accession No. ML16169A180).
The enclosed report is Part 2 of a series of reports that describe the confirmatory analyses performed by the RES staff. The Part 1 report was previously transmitted to your staff by memorandum dated April 26, 2018 (ADAMS Accession No. ML18116A497) and Part 1 provides the RES staff confirmatory analysis of the three highest priority cases identified in the confirmatory analysis case matrix for this user need. The base case (Case 1) was run to establish a base line which is compared to two sensitivity cases. The sensitivity cases (Case 2-1 and 2-2) study the effect of feedwater temperature response and manual operator action timing.
Part 2 is enclosed and this supplemental report covers the balance of the confirmatory analysis case matrix requested by your staff. Part 2 is a companion report to Part 1 and describes the balance of the case matrix analyses, namely Cases 3-1, 3-2, 3-3, 3-4, and 4. The Case 3-X sensitivity calculations were performed to quantify the sensitivity of the peak cladding temperature (PCT) to analysis parameters associated with the fuel assembly design. Case 4 addresses the difference in turbine bypass capacity between BSEP Unit 1 and Unit 2.
Enclosure transmitted herewith CONTACT: Peter Yarsky, RES/DSA/CRAB contains Official Use - Proprietary (301) 415-2384 Information. When separated from Enclosure this transmittal document is decontrolled.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
ML18152B127 OFFICE RES/DSA/CRAB RES/DSA/CRAB RES/DSA/CRAB RES/DSA/CRAB NAME P. Yarksy T. Zaki J. Staudenmeier C. Gingrich DATE 5/11/18 5/11/18 5/9/18 5/8/18 OFFICE RES/DSA BC:RES/DSA/CRAB D:RES/DSA NAME S. Bajorek C. Hoxie M. Case DATE 5/21/18 5/7/18 6/4/18