BSEP 13-0002, Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact

Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact

ML13031A012
Person / Time
Site:	Brunswick
Issue date:	01/14/2013
From:	Carr D AREVA, AREVA NP
To:	Office of Nuclear Reactor Regulation
References
BSEP 13-0002 12-9197120-000
Download: ML13031A012 (7)

Text

BSEP 13-0002 Enclosure 7 AREVA Report No. 12-9197120-000, Brunswick SAFLIM3D LAR Support - CalculationErrorImpact (Non-ProprietaryVersion)

Controlled Document 20004-019 (11/20/2012)

A AREVA AREVA NP Inc.

TECHNICAL DATA RECORD Document No: 12 - 9197120 - 000 Brunswick SAFLIM3D LAR Support -

Calculation Error Impact (Nonproprietary Version)

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Caontrored Documc iet A

AR EVA 20004-019 (11/20/2012) 12-9197120-000 Brunswick SAFLIM3D LAR Support -

Calculation Error Impact (Nonproprietary Versicon)

Safety Related? [--DYES NO Does this document establish design or technical requirements? i-i YES H NO Does this document contain assumptions requiring verification? [-- YES FJ NO Does this document contain Customer Required Format? [D] YES F; NO Signature Block Pages/Sections Name and PILP, R/LR, Prepared/Reviewed/

Title/Discipline Signature A-CRF, A Date Approved or Comments D. G. Carr, Supervisor D

0) 467 P It AL-Thermal-Hydraulics Richland D. R. Tinkler, Engineer ,7U -t R Thermal-Hydraulics Richland / *L/L A

D. W . Pruitt, Manager A h A LL' Thermal-Hydraulics Richland C/V36)9 -LL-A. B. Meginnis, Manager A Product Licensing / jfj ___ __---__

Note: P/LP designates Preparer (P), Lead Preparer (LP)

R/LR designates Reviewer (R), Lead Reviewer (LR)

A-CRF designates Project Manager Approver of Customer Required Format (A-CRF)

A designates Approver/RTM - Verification of Reviewer Independence Record of Revision Revision PageslSections/ Brief DescriptionTI No. Paragraphs Changed Change Authorization 000 All Initial issue of document Page 2

Controlled Document 12-9197120-000 Brunswick SAFLIM3D LAR Support -

Calculation Error Impact (Nonproprietary Version)

Introduction Two errors were recently discovered in the analyses provided in support of the Reference 1 Brunswick SAFLIM3D license amendment request (LAR). The errors are associated with inputs used in the calculation process and do not impact the Reference 2 SAFLIM3D methodology. The purpose of this report is to discuss the impact of the errors on the results previously reported. In all cases the previously reported two-loop operation (TLO) and single-loop operation (SLO) SLMCPR values remain valid; however, there are small impacts to some of the supporting results.

Description of Errors In the SAFLIM3D analysis process, [

] at the core power and flow conditions of interest. The errors and the affected analyses are described below:

1. An error in the [

] This error occurred in the SAFLIM3D analyses for Brunswick Unit 1 Cycle 19 (References 3-10), Brunswick Unit 2 Cycle 20 (References 11-14), and Brunswick Unit 2 Cycle 21 (References 15-18).

2. The second error was the use of an incorrect version of [

] This error affected only the Brunswick Unit 2 Cycle 21 analysis results.

Impact on Results The limiting and near limiting analyses (i.e. cases with the highest number of rods expected to experience boiling transition) that support the results presented in References 3-18 were re-analyzed with the corrected inputs. In each case, the same safety limit MCPR was supported. There were small changes in the percentage of rods expected to experience boiling transitions and the contribution of the total predicted rods in boiling transition by nuclear fuel type. In general the changes in the TLO results were less than the changes in the SLO results due in part to [

] Since the thermal hydraulic input error was the only impact on the BRK1-19 and BRK2-20 results and both errors affected the BRK2-21 analysis, the impacts are reported separately.

Table 1 identifies, by reference and table number, the previously reported BRK1-19 and BRK2-20 results affected by the input error described above. It also presents a bounding change on the results when the error is corrected. It is noted that in four cases, some once burned fuel that previously had no rods in boiling transition, now contributes a small number of rods [ ] In all cases, the previously reported TLO and SLO SLMCPR values continue to be supported. The only differences are the small changes in the number of rods in boiling transition.

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Calculation Error Impact (Nonproprietary Version)

Table 2 identifies, by reference and table number, the previously reported BRK2-21 results affected by both errors described above. It also presents a bounding change on the results when the error is corrected. In all cases, the previously reported TLO and SLO SLMCPR values continue to be supported. The only differences are the small changes in the number of rods in boiling transition.

The information presented in this document has been prepared consistent with the guidance for operability assessments as described in the NRC Inspection Manual Part 9900 Technical Guidance, "Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety," April 16, 2008. The SLMCPR analyses discussed herein do not support any plant operation; therefore, no operating plants are affected by these issues.

References

1. Letter, M.J. Annacone (PGN) to USNRC, "Brunswick Steam Electric Plant, Units Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)" and Revision to Technical Specification 2.1.1.2 Minimum Critical Power Ratio Safety Limit," BSEP 12-0031, March 2012 (NRC Accession Number ML12076A062).

2. ANP-1 0307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.

3. 51-9175814-000, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis; With SAFLIM3D Methodology (Proprietary Version)," AREVA NP, February 2012.

4. 51-9175814-001, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Proprietary Version)," AREVA NP, July 2012.

5. 51-9177317-000, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis; With SAFLIM3D Methodology (Nonproprietary Version)," AREVA NP, February 2012.

6. 51-9177317-001, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)," AREVA NP, July 2012.

7. 51-9176407-000, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis, With SAFLIM3D Methodology

- Operability Assessment (Proprietary Version)," AREVA NP, February 2012.

8. 51-9176407-001, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology

- Operability Assessment (Proprietary Version)," AREVA NP, July 2012.

9. 51-9177315-000, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology

- Operability Assessment (Nonproprietary Version)," AREVA NP, February 2012.

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10. 51-9177315-001, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology

- Operability Assessment (Nonproprietary Version)," AREVA NP, July 2012.

11. 51-9175787-000, "Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology (Proprietary Version)," AREVA NP, February 2012.

12. 51-9177314-000, "Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)," AREVA NP, February 2012.

13. 51-9176342-000, "Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology

- Operability Assessment (Proprietary Version)," AREVA NP, February 2012.

14. 51-9177316-000, "Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology

- Operability Assessment (Nonproprietary Version)," AREVA NP, February 2012.

15. 51-9186363-000, "Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Proprietary Version)," AREVA NP, August 2012.

16. 51-9189033-000, "Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)," AREVA NP, August 2012.

17. 51-9186367-000, "Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology

- Operability Assessment (Proprietary Version)," AREVA NP, August 2012.

18. 51-9189034-000, "Brunswick Unit 2 Cycle 21 SLMCPR Analysis With SAFLIM3D Methodology

- Operability Assessment (Nonproprietary Version)," AREVA NP, August 2012.

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Calculation Error Impact (Nonproprietary Version)

Table I Impact on BRKI-19 and BRK2-20 SAFLIM3D Results Due to Calculation Error Impacted Affected Affected Bounding Changes on Result References Tables Reported Results 3-6,11-12 Table 2 Percentage of Rods in TLO +0.002/-0.005 Boiling Transition 7-10, 13-14 Tables SLO +0.008/-0.017 2 and 4 Contribution of Total Rods 3-4, 7- 8, Table 3 [ ]

Predicted To Be in BT (%) 11, 13 by nuclear fuel type Table 2 Impact on BRK2-21 SAFLIM31D Results Due to Calculation Errors Impacted Affected Affected Bounding Changes on Result References Tables Reported Results 15-16 Table 2 Percentage of Rods in TLO +0.004/-0.002 Boiling Transition 17-18 Tables SLO +0.010/-0.002 2 and 4 Contribution of Total Rods 15, 17 Table 3 [ ]

Predicted To Be in BT (%)

by nuclear fuel type Page 6