ML12076A086

Areva Document No. 51-9177316-000, Brunswick Unit 2 Cycle 20 SLMCPR Analysis with SAFLIM3D Methodology - Operability Assessment, Enclosure 17 to BSEP 12-0031

ML12076A086
Person / Time
Site:	Brunswick
Issue date:	02/17/2012
From:	AREVA, AREVA NP
To:	Office of Nuclear Reactor Regulation
References
BSEP 12-0031 51-9177316-000
Download: ML12076A086 (17)

Text

BSEP 12-003 1 7 AREVA Document No. 51-9177316-000, "Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)"

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A AREVA 20004-018 (10/18/2010)

AREVA NP Inc.

ENGINEERING INFORMATION RECORD Document No:

51 9177316 -

000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

Page 1 of 12

G o r tr c(

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Documnt A

AREVA 20004-018 (10/18/2010) 51-9177316-000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

Safety Related?

H YES F] NO Does this document contain assumptions requiring verification?

IYES M NO Does this document contain Customer Required Format?

Fl]

YES M NO Signature Block PILP, R/LR, Pages/Sections Name and A/A-CRF, PreparedlReviewed/

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

P Thermal-Hydraulics Richland b_

(

D.R. Tinkler, Engineer R

T h e rm a l-H y d ra u lic s R ic h la n d D.W. Pruitt, Manager A/A-CRI.///

Thermal-Hydraulics Richland 2

A. B. Meginnis, Manager

.A

/

Product Licensing z_12 0// 2,.

Note:

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

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

A/A-CRF designates Approver (A), Approver of Customer Requested Format (A-CRF)

A/A-CRI designates Approver (A), Approver - Confirming Reviewer Independence (A-CRI)

Record of Revision Revision PageslSections/

Brief Description I No.

Paragraphs Changed Change Authorization 000 All Initial issue of document Page 2

Uor'onVollec Doc.imevl~rRf 20004-018 (10/18/2010) 51-9177316-000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

Contents 1.0 P u rp o s e......................................................................................................................................

4 2.0 M e th o d o lo g y..............................................................................................................................

4 3.0 A n a ly s is......................................................................................................................................

5 4.0 D is c u s s io n o f R e s u lts.................................................................................................................

6 5.0 R e fe re n c e s.................................................................................................................................

6 Tables 1

Fuel-and Plant-Related Uncertainties for BRK2-20 SLMCPR Analyses.................................

8 2

BRK-2-20 Results Summary for SLMCPR Analysis (Operability Assessment CPR Correlation for ATRIUM 1OXM)..................................................................

9 3

Contribution of Total Predicted Rods in BT by Nuclear Fuel Type........................................... 9 4

BRK2-20 Results Summary for SLMCPR Analysis (Reference 4 ACE/ATRIUM 20XM CPR Correlation)....................................................................................

9 Figures 1

Brunswick Unit 2 Cycle 20 Core Loading Map......................................................................

10 2

Brunswick Unit 2 Power/Flow Map With Nominal Feedwater T em perature B S P R eg ions..................................................................................................

.. 11 3

Radial Power Distribution for Brunswick Unit 2 Cycle 20 SLMCPR

[

] With Operability Assessment CPR Correlation............................

12 Page 3

.~flO~e& DocL.wr~nt 51-9177316-000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version) 1.0 Purpose Reference 1 presents an AREVA methodology for determining the safety limit minimum critical power ratio (SLMCPR) that was recently approved by the NRC. The methodology is an update or extension of the previously approved methodology presented in Reference 2. The SLMCPR methodology was updated to incorporate full implementation of the ACE critical power correlation (References 3 and 4), a realistic fuel channel bow model (Reference 5), and expanded coupling with the MICROBURN-B2 core simulator (Reference 6). More detailed descriptions of these improvements are discussed in Reference 1.

Reference 7 presents results of the Brunswick Unit 2 Cycle 20 (BRK2-20) SLMCPR analysis using the currently approved Reference 4 ACE/ATRIUM TM 1OXM* critical power correlation. As discussed in Reference 8, a concern was identified in the calculation of the K-factor within the approved ACE/ATRIUM 1OXM correlation. The K-factor methodology was modified in response to the deficiencies found in the axial averaging process. An updated correlation for use in the Brunswick SLMCPR operability assessment calculations with ATRIUM 1OXM fuel is described in Reference 8.

The purpose of this report is to present results of an operability assessment for the BRK2-20 SLMCPR calculations presented in Reference 7 using the updated critical power correlation described in Reference 8 for the ATRIUM 1OXM fuel. The results of this analyses support a change in the list of approved methodologies in the Technical Specifications and also a change in the Technical Specification SLMCPR values for two-loop operation (TLO) and single-loop operation (SLO).

2.0 Methodology The analysis presented in this document used the methodology presented in Reference 1 and the operability assessment critical power correlation presented in Reference 8 for the ATRIUM 1OXM fuel.

The SLMCPR is defined as the minimum value of the critical power ratio which ensures that at least 99.9% of the fuel rods in the core are expected to avoid boiling transition during normal operation or an anticipated operational occurrence (AOO). The SLMCPR is determined using a statistical analysis that employs a Monte Carlo process that perturbs key input parameters used in the calculation of MCPR.

The set of uncertainties used in the statistical analysis include both fuel-related and plant-related uncertainties.

The SLMCPR analysis is performed with a power distribution that conservatively represents expected reactor operating states that could both exist at the operating limit MCPR (OLMCPR) and produce a MCPR equal to the SLMCPR during an AOO. [

ATRIUM is a trademark of AREVA NP.

Page 4

51-9177316-000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

In the AREVA methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis. Reference 1 discusses the application of a realistic channel bow model.

3.0 Analysis The core loading and cycle depletion from the BRK2-20 fuel cycle design report (Reference 9) was used as the basis of the SLMCPR analysis. Figure 1 presents the core loading including the assembly type, the cycle the fuel was originally loaded, and the number of assemblies. The BRK2-20 core is made up of ATRIUM 1OXM, ATRIUM-10, and GE14 fuel. Analyses were performed [

] for the Brunswick power/flow map for MELLLA operation as shown in Figure 2. The BSP regions shown in the power/flow map are based on the methods discussed in Reference 10. The radial power distribution [

] is presented in Figure 3.

The operability assessment critical power correlation is used for the ATRIUM 1OXM fuel while the SPCB critical power correlation (Reference 11) is used for the ATRIUM-10 and GE14 fuel. The application of the SPCB critical power correlation to GE14 fuel follows the indirect process described in Reference 12.

The fuel-and plant-related uncertainties used in the BRK2-20 SLMCPR analysis are presented in Table 1. The radial and nodal power uncertainties used in the analysis include the effects of up to 40%

of the TIP channels out-of-service, up to 50% of the LPRMs out-of-service, and a 2500 effective full power hour (EFPH) LPRM calibration interval.

The BRK2-20 SLMCPR analysis supports a TLO SLMCPR of 1.06 and an SLO SLMCPR of 1.08.

Table 2 presents a summary of the analysis results including the SLMCPR and the percentage of rods expected to experience boiling transition. The percentages of the total number of fuel rods predicted to experience boiling transition in the overall Monte Carlo statistical evaluation associated with each nuclear fuel type are presented in Table 3. The results are for the [

I Page 5

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0 f-,r Iem 51-9177316-000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version) 4.0 Discussion of Results Results from Reference 7 based on the currently approved ACE/ATRIUM 1OXM critical power correlation (Reference 4) are presented in Table 4. They are based on the same BRK2-20 design step-through and most of the same fuel-and plant-related uncertainties. The one exception is a slightly higher additive constant uncertainty associated with the currently approved correlation for the ATRIUM 1OXM fuel- [

]. A comparison of results shows a decrease in the number of rods expected to experience boiling transition in both TLO and SLO with the use of the operability assessment correlation. The same SLMCPR limits are supported with both the currently approved ACE correlation (Reference 4) and the operability assessment correlation.

5.0 References

1.

ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.

2.

ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.

3.

ANP-10249PA Revision 1, ACE/ATRIUM-1O Critical Power Correlation, AREVA NP, September 2009.

4.

ANP-10298PA Revision 0, ACE/ATRIUM IOXM Critical Power Correlation, AREVA NP, March 2010.

5.

BAW-1 0247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.

6.

EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4 / MICROBURN-B2, Siemens Power Corporation, October 1999.

7.

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

8.

ANP-3086(P), Brunswick Unit 1 and Unit 2 SLMCPR Operability Assessment Critical Power Correlation for ATRIUM IOXM Fuel - Improved K-factor Model, AREVA NP, February 2012.

9.

ANP-2920(P) Revision 0, Brunswick Unit 2 Cycle 20 Fuel Cycle Design, AREVA NP, May 2010.

10.

0G02-0119-260, Backup Stability Protection (BSP) for Inoperable Option Ill Solution, GE Nuclear Energy, July 17, 2002.

11.

EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.

12.

EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations for Co-Resident Fuel, Siemens Power Corporation, August 2000.

13.

EMF-2493(P), MICROBURN-B2 Based Impact of Failed/Bypassed LPRMs and TIPs, Extended LPRM Calibration Interval, and Single Loop Operation on Measured Radial Bundle Power Uncertainty, AREVA NP, December 2000.

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on'O", "ed Documen 51-9177316-000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

14.

NEDO-20340, Process Computer Performance Evaluation Accuracy, General Electric, June 1974.

15.

NEDO-1 0958-A, General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application, General Electric, January 1977.

16.

NEDO-24344, Brunswick Steam Electric Plant Units 1 and 2 Single-Loop Operation, General Electric, September 1981.

17.

Letter, H.D. Curet (AREVA) to H.J. Richings (NRC), "POWERPLEX Core Monitoring: Failed or Bypassed Instrumentation and Extended Calibration," HDC:96:012, May 6, 1996 (38-9043714-000).

18.

0B21-1305 Revision 1, "Core Monitoring LPRM Uncertainty and Sensitivity Decay," Progress Energy, March 2009 (NRC Accession Number ML092370285).

Page 7

drofled Docur~~ent 51-9177316-000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM31D Methodology - Operability Assessment (Nonproprietary Version)

Table I Fuel-and Plant-Related Uncertainties for BRK2-20 SLMCPR Analyses Parameter Uncertainty Reference Fuel-Related Uncertainties

[

Plant-Related Uncertainties Feedwater flow rate 1.8%§ 15 Feedwater temperature 0.8%1 15 Core pressure 0.8%§- **

14 Total core flow rate TLO 2.5%

15 SLO 6.0%

16 I

I t

[

Values from Reference 13 are a result of the application of the methodology discussed in Reference 17 to the base uncertainties presented in Reference 6. The uncertainties presented support operation with up to 50% of LPRMs out-of-service, up to 40% of the TIP channels out-of-service, and a 2500 EFPH LPRM calibration interval. The bases of these values include a core monitoring LPRM detector uncertainty of 4.3% from Reference 18.

§ References plant uncertainties were conservatively rounded up to the nearest 0.1% before use.

The core pressure uncertainty is taken in Reference 14 to be a more conservative value than accepted in Reference 15; therefore, the more conservative value is used.

Page 8

Coi~i~c~ec~ L.;ocun.ent 51-9177316-000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version)

Table 2 BRK2-20 Results Summary for SLMCPR Analysis (Operability Assessment CPR Correlation for ATRIUM 10XM)

Percentage of Rods SLMCPR in Boiling Transition TLO - 1.06 0.069 SLO - 1.08 0.069 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Contribution of Total Rods Nuclear Predicted To Be Fuel Fuel Burnup in BT (%)

Type Design Status TLO SLO 14 GE14 Twice burned

[

15 GE14 Twice burned 16 GE14 Twice burned 30 ATRIUM-10 Once burned 31 ATRIUM-10 Once burned 32 ATRIUM-10 Once burned 33 ATRIUM 1OXM Fresh 34 ATRIUM 1OXM Fresh Table 4 BRK2-20 Results Summary for SLMCPR Analysis (Reference 4 ACEIATRIUM 1OXM CPR Correlation)

Percentage of Rods SLMCPR in Boiling Transition TLO-1.06 0.090 SLO-1.08 0.088 Page 9

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10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 14 GE14 18 2

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51-9177316-000 Brunswick Unit 2 Cycle 20 SLMCPR Analysis With SAFLIM3D Methodology - Operability Assessment (Nonproprietary Version) 03 0_

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10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Figure 2 Brunswick Unit 2 Power/Flow Map With Nominal Feedwater Temperature BSP Regions Page 11

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0. 631 0.712 0.756 0.781 0.798 0.799 0.782 0.755 0.708 0.627 0.445 0.328 0.400 0.439 0.440 0.438 0.446 0.457 0.435 0.380 0.313 14 15 16 17 18 19 20 21 22 23 24 25 26 Figure 3 Radial Power Distribution for Brunswick Unit 2 Cycle 20 SLMCPR[

]

With Operability Assessment CPR Correlation Page 12

BSEP 12-0031 9 AREVA Affidavit Regarding Withholding AREVA Document ANP-3086(P), Revision 0, "Brunswick Unit I and Unit 2 SLMCPR Operability Assessment Critical Power Correlation for ATRIUM 1 0XM Fuel - Improved K-factor Model" from Public Disclosure

AFFIDAVIT STATE OF WASHINGTON

)

) ss.

COUNTY OF BENTON

)

1.

My name is Alan B. Meginnis. I am Manager, Product Licensing, for AREVA NP Inc. and as such I am authorized to execute this Affidavit.

2.

I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary. I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.

3.

I am familiar with the AREVA NP information contained in the report ANP-3086(P), Revision 0, "Brunswick Unit 1 and Unit 2 Operability Assessment Critical Power Correlation for ATRIUM 1OXM Fuel - Improved K-Factor," dated February 2012 and referred to herein as "Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.

4.

This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.

5.

This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is

requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."

6.

The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary:

(a)

The information reveals details of AREVA NP's research and development plans and programs or their results.

(b)

Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.

(c)

The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.

(d)

The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.

(e)

The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.

The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.

7.

In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8.

AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.

9.

The foregoing statements are true and correct to the best of my knowledge, information, and belief.

SUBSCRIBED before me this c-'O day of

,.eS 2012.

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Susan-K OM w.oy NOTARY PUBLIC, STATE OF WASHING ON MY COMMISSION EXPIRES: 1/14/2016