RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies

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Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies
ML19365A172
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 12/31/2019
From: Krakuszeski J
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML19365A171 List:
References
RA-19-0479 FS1-0047695, Rev. 1
Download: ML19365A172 (16)
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Text

John A. Krakuszeski Vice President Brunswick Nuclear Plant 8470 River Rd SE Southport, NC 28461 Enclosure 1 Contains Proprietary Information o: 910.832.3698 Withhold in Accordance with 10 CFR 2.390 December 31, 2019 Serial: RA-19-0479 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies

Reference:

Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, dated October 11, 2018, ADAMS Accession Number ML18284A395.

Ladies and Gentlemen:

By letter dated October 11, 2018 (i.e., Reference), Duke Energy Progress, LLC (Duke Energy),

submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP),

Unit Nos. 1 and 2. The proposed license amendment revises Technical Specification 5.6.5.b to allow application of Advanced Framatome Methodologies for determining core operating limits in support of loading Framatome fuel type ATRIUM 11.

Framatome has identified a coding error in the RODEX4 software which was used in analyses supporting the Advanced Framatome Methodologies LAR. Enclosure 1 contains a report that describes the identified issue and evaluates the impact on the LAR analyses. As shown in , impacts to the analyses provided to the NRC as part of the Advanced Framatome Methodologies LAR are negligible and no methodology topical reports are impacted by the error. contains information considered proprietary to Framatome. The proprietary information in this report has been denoted by brackets. As owner of the proprietary information, Framatome has executed the affidavit contained in Enclosure 3 which identifies the information as proprietary, is customarily held in confidence, and should be withheld from public disclosure in accordance with 10 CFR 2.390. Enclosure 2 provides a non-proprietary version of this report.

No new regulatory commitments are contained in this letter.

U.S. Nuclear Regulatory Commission Page 3 of 3 cc (with all Enclosures):

U. S. Nuclear Regulatory Commission, Region II ATTN: Ms. Laura Dudes, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Gale Smith, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon 11555 Rockville Pike Rockville, MD 20852-2738 cc (with Enclosures 2 and 3 only):

Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net Mr. W. Lee Cox, III, Section Chief (Electronic Copy Only)

Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645 lee.cox@dhhs.nc.gov

RA-19-0479 Enclosure 2 FS1-0047695, Brunswick LAR Supplement for RODEX4 Axial PCMI Onset Error (Non-Proprietary), Revision 1

IDENTIFICATION REVISION FS1-0047695 1.0 Framatome Fuel TOTAL NUMBER OF PAGES: 8 Brunswick LAR Supplement for RODEX4 Axial PCMI Onset Error (Non-Proprietary)

ADDITIONAL INFORMATION:

PROJECT DISTRIBUTION TO PURPOSE OF DISTRIBUTION HANDLING Restricted Framatome EIR - Engineering CATEGORY Information Report STATUS This document is electronically approved. Records regarding the signatures are stored in the fsanpexp EDRMS object Id. : 0901216780e21106 Documentum docbase. Any attempt to modify this file may subject employees to civil and criminal penalties. Released date (YYYY/MM/DD) : 2019/12/31 20:04:05 Role ROLES This text shall NAMES Name no be visible - Adjust frames DATESover to ensure signature ORGANIZATIONS block will completely Date (YYYY/MM/DD) cover this Organization text SIGNATURES Writer DAVIS Tanner 2019/12/31 18:03:54 Framatome Inc.

Reviewer AUTHOR TINKLER DAVIS Daniel Tanner 2019/12/31 18:18:20 Framatome Inc.

Approver MEGINNIS Alan 2019/12/31 19:23:34 Framatome Inc.

REVIEWER Approver TINKLER Dan QUICK Kevin 2019/12/31 20:03:32 Framatome Inc.

APPROVER QUICK Kevin; MEGINNIS Alan This text shall no be visible - Adjust frames over to ensure signature block will completely cover this text Classification Export AL: 0E001 ECCN: 0E001 RELEASE DATA: Les marchandises portant la désignation "AL inégal N" sont soumises la réglementation européenne ou allemande en matire de contrle des exportations au sein ou hors de l'UE. Les marchandises portant la désignation "ECCN inégal N" sont soumises la réglementation américaine. Les marchandises portant les désignations "AL:N" ou "ECCN:N" peuvent, selon la destination ou l'utilisation finales du produit, également tre soumises autorisation.

Export classification AL: 0E001 ECCN: 0E001 Goods labeled with AL not equal to N are subject to European or German export authorization when being exported within or out of the EU. Goods labeled with ECCN not equal to N are subject to US reexport authorization. Even without a label, or with label AL: N or ECCN: N, authorization may be required due to the SAFETY RELATED DOCUMENT: Y final whereabouts and purpose for which the goods are to be used.

Exportkennzeichnung AL: 0E001 ECCN: 0E001 CHANGE CONTROL RECORDS: France: N Die mit "AL ungleich N" gekennzeichneten Güter unterliegen bei der Ausfuhr aus der EU bzw.

This document, when revised, must be USA: Y innergemeinschaftlichen Verbringung der europischen bzw. deutschen Ausfuhrgenehmigungspflicht. Die mit "ECCN ungleich N" gekennzeichneten Güter unterliegen der US-Reexportgenehmigungspflicht. Auch ohne reviewed or approved by following regions: Germany: N Kennzeichen, bzw. bei Kennzeichen "AL: N" oder "ECCN: N", kann sich eine Genehmigungspflicht, unter anderem durch den Endverbleib und Verwendungszweck der Güter, ergeben.

CW01L Rev. 5.2 - 24/08/18

N° FS1-0047695 Rev. 1.0 Brunswick LAR Supplement for RODEX4 Axial PCMI Onset Error Handling:

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Restricted Framatome REVISIONS REVISION DATE EXPLANATORY NOTES See 1st page New document 1.0 release date This is the non-proprietary version of FS1-0047694 ATRIUM is a trademark or registered trademark of Framatome or its affiliates, in the USA or other countries.

Framatome - Fuel This document is subject to the restrictions set forth on the first or title page

N° FS1-0047695 Rev. 1.0 Brunswick LAR Supplement for RODEX4 Axial PCMI Onset Error Handling:

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Restricted Framatome TABLE OF CONTENTS

1. INTRODUCTION ............................................................................................................................ 4
2. ISSUE DESCRIPTION.................................................................................................................... 4
3. ISSUE IMPACT EVALUATION ...................................................................................................... 4 3.1. STEADY-STATE OPERATION (LHGR LIMITS) ..................................................................................... 5 3.2. ANTICIPATED OPERATIONAL OCCURRENCES (LHGR SET DOWNS) ............................................ 5 3.3. STABILITY METHODOLOGY AND ATWS-I ........................................................................................... 5 3.4. AURORA-B LOCA ................................................................................................................................... 6 3.5. AURORA-B AOO ..................................................................................................................................... 6 3.6. AURORA-B CRDA ................................................................................................................................... 6 3.7. MASS AND ENERGY RELEASE EVENTS ............................................................................................. 7 3.8. AURORA-B OVERPRESSURIZATION ................................................................................................... 7
4. CONCLUSIONS ............................................................................................................................. 8
5. REFERENCES ............................................................................................................................... 8 Framatome - Fuel This document is subject to the restrictions set forth on the first or title page

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1. INTRODUCTION An issue has recently been identified that has minimal impact on reports (References 1 - 6) which have been provided in support of the Brunswick (BSEP) License Amendment Request (LAR) (Reference 7) and plant specific reload licensing campaign to utilize Framatome advanced methods in support of loading ATRIUM 11 fuel. [ ]
2. ISSUE DESCRIPTION
3. ISSUE IMPACT EVALUATION While the purpose of this report is to evaluate the impacts on the BSEP Advanced Framatome Methods LAR, many of the impacts are being quantified with respect to the first BSEP unit and operating cycle containing reload quantities of ATRIUM 11 which is BSEP Unit 1 Cycle 23 (B1C23) as the cycle-specific analyses go beyond the methods demonstration contained in the BSEP Advanced Framatome Methods Framatome - Fuel This document is subject to the restrictions set forth on the first or title page

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Restricted Framatome LAR. As shown in the sections below, the negligible impacts for B1C23 demonstrate that this error does not impact the representative nature of the demonstration reports provided in the LAR.

3.1. STEADY-STATE OPERATION (LHGR LIMITS)

RODEX4 is used to validate the linear heat generation rate (LHGR) Fuel Design Limit (FDL) for ATRIUM 11 fuel. Evaluations have been performed which showed the variations in results remain within the statistical variation of the method. Therefore the ATRIUM 11 LHGR limits for B1C23 remain applicable and there is no impact on the BSEP Advanced Framatome Methods LAR analyses.

3.2. ANTICIPATED OPERATIONAL OCCURRENCES (LHGR SET DOWNS)

The anticipated operational occurrences (AOO) methodology determines power and flow dependent LHGR set downs (LHGRFACp and LHGRFACf multipliers) to ensure the transient strain and centerline melt criteria are met. While the Reference 1 demonstration analysis did not perform these evaluations, they are included in the B1C23 reload analysis (Reference 6). RODEX4 is used to establish these setdowns and an assessment was performed with the corrected development version of the code. The LHGRFACp cases assessed for fast transients were the limiting BSEP licensing analyses. These evaluations showed [

]. Comparison of the [ ]

the LHGR set downs showed the current ATRIUM 11 limits remain bounding for B1C23. As a result, there is no impact on the BSEP Advanced Framatome Methods LAR analyses.

3.3. STABILITY METHODOLOGY AND ATWS-I The Anticipated Transient without Scram with Instability (ATWS-I) methodology supports the confirmation of the LHGR limits to ensure fuel coolability during the event. The Best-estimate Enhanced Option III (BEO-III) methodology is used to determine minimum critical power ratio (MCPR) limits on a cycle specific basis. The ATWS-I and BEO-III methodologies incorporated a [

], the stability methodology is not impacted, the stability analyses of record are unaffected, and there is no impact on the BSEP Advanced Framatome Methods LAR analyses.

Framatome - Fuel This document is subject to the restrictions set forth on the first or title page

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Restricted Framatome 3.4. AURORA-B LOCA The AURORA-B Loss of Coolant Accident (LOCA) methodology supports the determination of the maximum average planar LHGR (MAPLHGR) limits. Comparisons of S-RELAP5 [

] were performed as part of the AURORA-B LOCA methodology assessment.

This assessment produced an impact of 5 °F for the BSEP ATRIUM 11 peak cladding temperature (PCT). This change in PCT is reportable under 10 CFR 50.46 and will be included in Duke Energys annual 10 CFR 50.46 report. This PCT impact is insignificant as defined by 10 CFR 50.46 and this error results in additional margin to the 2200 °F limit.

3.5. AURORA-B AOO The AURORA-B AOO methodology supports the determination of power-dependent MCPR (MCPRp) limits. The AURORA-B AOO methodology assessment consisted of comparisons of the limiting B1C23 licensing analysis cases with and without the RODEX4 correction. The B1C23 limiting licensing analyses show [ ]. This change is within the criteria defined as insignificant which are given in Section 9.3 of the approved AURORA-B AOO topical report (Reference 8). Based on the evaluations of the B1C23 limiting licensing cases and continuity of assessment cases, the MCPRp limits are not impacted by the change and remain appropriate for use.

The negligible impacts on B1C23 demonstrate the error can have no significant impact on the transient demonstration report (Reference 1) provided with the BSEP Advanced Framatome Methods LAR.

3.6. AURORA-B CRDA The AURORA-B Control Rod Drop Accident (CRDA) methodology and calculations support the determination of core coolability and radiological consequences for the postulated CRDA. The impacts of the error were minor and resulted in a total enthalpy [

]. The maximum total enthalpy rise remained below the core coolability limit of 230 cal/g such that the established core coolability for B1C23 remains valid and the representative nature of the demonstration report provided in the LAR is not impacted.

The radiological dose consequences are evaluated based on the number of predicted rod failures which may occur from PCMI failure, fuel melting, or enthalpy greater than the high temperature failure thresholds. There is no increase in fuel rod failures from PCMI or fuel melting as a result of this code correction. The change in the number of rod failures based on the high temperature failure threshold Framatome - Fuel This document is subject to the restrictions set forth on the first or title page

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Restricted Framatome which is based on total enthalpy rise and fuel rod differential pressure was minimal. The predicted

[ ] rod failures were determined to be [ ] of the of allowed rod failures which defines the dose consequences of the accident. The small change in the total enthalpy would [

] of the allowed rod failures. Therefore this code correction has no impact on the radiological consequences for B1C23 postulated CRDA.

The CRDA demonstration report submitted with the LAR is only used for demonstration purposes and is not intended to be a bounding licensing analysis. Given the negligible impact on core coolability and radiological consequences seen for B1C23 and the margin to these criterions in the demonstration report, it is concluded that this error has no impact on the core coolability or radiological consequences of the CRDA demonstration report.

3.7. MASS AND ENERGY RELEASE EVENTS Decay heat and initial stored energy in the fuel are first order phenomena concerning the mass and energy release during an accident or special event (e.g. fire event). Decay heat is not impacted and corrections in the coding for both the steady-state RODEX4 and the S-RELAP5 RODEX4 kernel calculations show an [

] Therefore, there is no adverse impact on the ATRIUM 11 mass and energy release during an accident or special event from the RODEX4 issue.

3.8. AURORA-B OVERPRESSURIZATION The AURORA-B overpressurization calculation supports the vessel overpressure criteria. The limiting case for the B1C23 licensing analysis was evaluated with and without the RODEX4 correction. The comparison showed [ ] established as insignificant per Section 9.3 of the approved AURORA-B AOO topical report (Reference 8). The negligible impacts on B1C23 demonstrate the error can have no significant impact on the transient demonstration report (Reference 1) provided with the BSEP Advanced Framatome Methods LAR. Based on the insignificant impact on the results, the overpressurization criterion is still met and the BSEP Advanced Framatome Methods LAR analyses are not impacted.

Framatome - Fuel This document is subject to the restrictions set forth on the first or title page

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4. CONCLUSIONS As shown in Section 3, the error described in Section 2 of this report has a negligible effect on the BSEP LAR submittal which utilized advanced Framatome methods. Given the negligible impacts seen for B1C23, assurance is provided that the demonstration reports provided in the LAR remain representative.

Although the error described in Section 2 of this report is associated with the coding of various methodologies, the error is not with any methodology itself. Therefore, no methodology topical reports, including any related to the BSEP LAR, are impacted by the error.

5. REFERENCES
1. ANP-3702P Revision 0, Brunswick ATRIUM 11 Transient Demonstration, Framatome Inc.,

August 2018.

2. ANP-3703P Revision 0, BEO-III Analysis Methodology for Brunswick Using RAMONA5-FA, Framatome Inc., August 2018.
3. ANP-3674P Revision 2, Brunswick Units 1 and 2 LOCA Analysis for ATRIUM 11 Fuel, Framatome Inc., May 2019.
4. ANP-3694P Revision 0, ATWS-I Analysis Methodology for Brunswick Using RAMONA5-FA, Framatome Inc., June 2018.
5. ANP-3714P Revision 0, Brunswick ATRIUM 11 Control Rod Drop Accident Analyses with the AURORA-B CRDA Methodology, Framatome Inc., September 2018.
6. ANP-3808P Revision 0, Brunswick Unit 1 Cycle 23 Reload Safety Analysis, Framatome Inc.,

October 2019.

7. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, October 11, 2018, ADAMS Accession Number ML18284A395.
8. ANP-10300P-A Revision 1, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios, Framatome Inc., February 2018.

Framatome - Fuel This document is subject to the restrictions set forth on the first or title page

RA-19-0479 Enclosure 3 Affidavit for FS1-0047694, Brunswick LAR Supplement for RODEX4 Axial PCMI Onset Error (Proprietary), Revision 1

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