BSEP 14-0007, 1707-01-F03, Rev. 3, Operability Assessment (CR2013-8241)

1707-01-F03, Rev. 3, Operability Assessment (CR#2013-8241)

ML14036A101
Person / Time
Site:	Brunswick
Issue date:	09/08/2011
From:	AREVA, AREVA NP
To:	Office of Nuclear Reactor Regulation
References
BSEP 14-0007, CR 2013-8241 1707-01-F03, Rev. 3
Download: ML14036A101 (11)

Text

BSEP 14-0007 Enclosure 3 Non-Proprietary Version of Operability Assessment (CR #2013-8241)

1707-01-F03 (Rev. 003, 09/08/2011)

A OPERABILITY ASSESSMENT (CR #2013-8241)

AREVA Issue

Description:

CR2011-2274 identifies an issue with the approved ACE correlation for the ATRIUM M T

1OXM* fuel design with regard to the calculation of K-factor within the ACE correlation. [

This issue was discussed with the USNRC during the review of a licensing amendment request to add the ATRIUM 1OXM version of the ACE correlation to the list of approved COLR references in the Brunswick Technical Specifications. As part of the approval of this licensing amendment (Reference 1), the USNRC imposed a license condition that requires follow-on operability assessments. The specifics of this license condition were modified in the Reference 2 acceptance of the SAFLIM3D methodology to the list of approved COLR references in the Brunswick Technical Specifications. The revised license condition is:

Safety Limit Minimum CriticalPower Ratio (SLMCPR), setpoint, and core operatinglimit values determined using the ANP-10298PA, ACE/ATRIUM 10XM CriticalPower Correlation(i.e., TS 5.6.5.b.21), shall be evaluated to verify the values determined using the NRC-approved method remain applicableand the core operatinglimits include margin sufficient to bound the effects of the K-factor calculationissue describedin AREVA Operability Assessment CR 2011-2274, Revision 1. SLMCPR shall be evaluated with methods described in AREVA Document ANP-3086(P), Revision 0, "Brunswick Unit 1 and Unit 2 SLMCPR OperabilityAssessment Critical Power Correlationfor ATRIUM IOXM Fuel - Improved K-factor Model. " Setpoint and core operating limit values shall be evaluated with methods described in AREVA OperabilityAssessment CR 2011-2274, Revision 1. The results of the evaluation shall be documented and submitted to the NRC, for review, at least 60 days priorto startup of each operating cycle.

This is the operability assessment for Brunswick Unit 1 Cycle 20 and as such addresses impacts on information provided in Reference 3.

References:

1. Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendments regardingAddition of Analytical Methodology Topical Report to Technical Specification 5.6.5 (TAC Nos. ME3856 and ME3857), Accession No. ML111010234, April 8, 2011.

2. Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendments RegardingAddition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 and Revision to Minimum CriticalPowerRatio Safety Limit (TAC Nos. ME8135 and ME8136), March 1, 2013. (NRC Ascension Number ML13037A551)

3. ANP-3263(P) Revision 0, Brunswick Unit I Cycle 20 Reload Safety Analysis, AREVA NP, December 2013.

4. ANP-3086(P) Revision 0, Brunswick Unit I and Unit 2 SLMCPR OperabilityAssessment CriticalPower Correlationfor-A TRIUM IOXM Fuel - Improved K-factor Model, AREVA NP, February 2012.

Affected Projects Customer, Reload or Customer Reactor (if applicable)

Project Identifier BRK1-20 Duke - Progress Energy Carolinas Brunswick Unit 1 ATRIUM is a trademark of AREVA NP.

Ref: 1707-01 Page 1 of 10 AREVA NP Inc.

1707-01-F03 (Rev. 003, 09/08/2011)

Assessment:

The USNRC approved ACE correlation was used in Cycle 20 core design and licensing analyses. It will also be used in the POWERPLEX-Ill core monitoring system to ensure Technical Specifications compliance of the fuel operating limits during operation. This assessment addresses the licensing and subsequent monitoring of the Cycle 20 core in regard to the potential impacts of the ACE correlation issue described above.

I These are the same methods previously utilized in the Operability Assessment CR2011-2274 Revision 1 and their use is therefore consistent with the license condition imposed by Reference 1 and the license condition in Reference 2.

The evaluation for the SLMCPR calculation was performed using methods as described in document ANP-3086(P) Revision 0 (Reference 4), as required by the Reference 2 licensing condition.

Methods Used for Operability Evaluation In the licensed methodology, a K-factor is determined by [

]

For the setpoint and core operating limit evaluation a version of the ACE correlation was constructed in which the K-factor [

]

For the SLMCPR evaluation, [ ] as described in ANP-3086(P) Revision 0 was utilized.

Ref: 1707-01 Page 2 of 10 AREVA NP Inc.

1707-01-F03 (Rev. 003, 09/08/2011)

Justification of the Evaluation Tool I

Justification for the critical power correlation used in the SLMCPR evaluation is provided in Reference 4.

Monitorina During Cycle 20 Operation The Brunswick Unit 1 Cycle 20 core is composed of the following fuel types:

Fuel Design No. Bundles CPR Correlation Fresh ATRIUM 10XM 222 ACE (10XM)

Once-Burnt ATRIUM 1OXM 234 ACE (10XM)

Twice-Burnt ATRIUM-10 104 SPCB As noted earlier, the concern identified in the condition report affects the K-factor calculation within the ACE correlation. This only affects the ATRIUM 1OXM fuel in the Cycle 20 core since the co-resident ATRIUM-10 fuel utilizes a different CPR correlation.

Once Cycle 20 begins operation, compliance to the operating limits will be performed using the POWERPLEXO-III core monitoring system which contains the approved version of the ACE correlation.

The nominal design step-through depletion was recalculated with the modified version [

] of the ACE correlation in order to evaluate potential non-conservatisms in monitoring during Cycle 20 operation.

Ref: 1707-01 Page 3 of 10 AREVA NP Inc.

1707-01-F03 (Rev. 003, 09/08/2011)

I Figure 1 Impact on Core Limiting MFLCPR during Cycle 20 Figure 1 shows that there is no significant non-conservative impact to the limiting CPR margin throughout most of the cycle. [

]

Figure 2 Change in ATRIUM 10XM CPR at Rated Conditions It is also useful to quantify the impact of the modified correlation on the calculated CPR for the ATRIUM 10XM fuel design (on an absolute AMCPR basis). For the same rated power cases, the maximum change in the calculated CPR was determined to be [ ]

Ref: 1707-01 Page 4 of 10 AREVA NP Inc.

1707-01-F03 (Rev. 003, 09/08/2011)

This evaluation was then expanded to look at a number of off-rated cases to determine ifthe rated power AMCPR results are representative for operation at reduced power conditions. The off-rated cases were performed for a subset of the cycle exposure points presented in Figure 2. The results of this evaluation are summarized in Figure 3.

The primary results of this off-rated evaluation include:

Figure 3 Change in ATRIUM 1OXM CPR at Rated and Off-Rated Conditions The off-rated evaluation described above was performed for power levels at and above [

I Ref: 1707-01 Page 5 of 10 AREVA NP Inc.

1707-01-F03 (Rev. 003. 09/08/2011')

lmpact on the Safety Limit MCPR (SLMCPR)

An evaluation of the impact on the SLMCPR was performed consistent with the Reference 2 licensing condition. The critical power correlation described in Reference 4 was used in the assessment. The results using the Reference 4 critical power correlation support a 0.01 lower SLMCPR for both TLO and SLO than the calculations with the ACE correlation described in ANP-10298PA. Overall, the results from Reference 3 and the operability assessment support the TLO SLMCPR of 1.08 and SLO SLMCPR of 1.11 presented in the Brunswick Unit 1 Cycle 20 reload report.

It should be noted MCPR is monitored relative to the OLMCPR and not directly to the SLMCPR. Therefore, there is no need in this SLMCPR evaluation to [

I Impact on CPR Operating Limits (OLMCPR)

The licensing analyses result in OLMCPRs that are a combination of power-dependent (MCPRp) and flow-dependent (MCPRf) limits. These are calculated from a series of quasi-steady-state and transient pressurization analyses. The quasi-steady-state events that have the potential to contribute to the MCPRp limits are the Control Rod Withdrawal Error (CRWE) and the Loss of Feedwater Heating (LFWH).

The MCPRf limits are based on the quasi-steady-state flow run-up analysis. [

The Cycle 20 flow run-up results were reviewed to determine the margin to the MCPRf limits presented in Reference 3. This review confirmed that for MCPRf limits above 1.35 (the lowest rated power MCPR limit),

the margin to the limit is more than adequate to compensate for the K-factor [ ] in setting the MCPRf limits and the steady-state CPR monitoring concern.

The MCPRp limits are a combination of the results from the pressurization analyses, CRWE, and potentially LFWH.

PressurizationTransient Impacts. This K-factor issue [

] the later cycle pressurization transient analysis results are only minimally affected by this K-factor issue. This was verified with analyses using the modified version of the ACE Ref: 1707-01 Page 6 of 10 AREVA NP Inc.

1707-01-F03 (Rev. 003, 09/08/2011) correlation.

Pressurization transient analyses are also performed [

The results of the analyses at all power levels show that in all cases (including the equipment out of service scenarios) the change in ACPR was such that there remains sufficient margin to the MCPRp limits. The margin is also large enough to account for the MCPR monitoring concern discussed above.

CRWE Impacts. CRWE analyses have been performed using both the as-approved version of the ACE correlation [ ] The CRWE results reported in Table 5.10 of Reference 3 are the most limiting from both sets of calculations.

The CRWE event is limiting for some conditions and sets the MCPRp limit for nominal scram speed with equipment in-service. For this reason, [

]

The RBM operability requirements specified in Table 5.11 of Reference 3 [

] are valid for both the as-approved and modified version of the ACE correlation.

LFWH Impacts. The LFWH event is non-limiting with significant margin to the Cycle 20 MCPRp limits.

This was confirmed for Cycle 20 with the performance of cycle-specific calculations using the modified ACE correlation. This calculation verified that the generic LFWH methodology continues to bound the cycle specific results including the impact of the ACE K-factor [ ] . Adequate margin exists at all power levels to offset the potential monitoring impact of the K-factor [ ].

Summary of MCPR impacts: The Reference 3 MCPRf and MCPRp limits have sufficient margin to account for the K-factor [ ] on the Cycle 20 quasi-steady-state and pressurization transient analysis results. This evaluation confirms [ ] for the use of the as-approved ACE correlation in the POWERPLEX-III core monitoring system.

Impact on Instrumentation Setpoints The licensing analyses for Cycle 20 support CPR-based instrumentation setpoints for both the Rod Block Monitor (RBM) and for the Oscillation Power Range Monitor (OPRM).

The RBM setpoints are based upon the CRWE event which in turn has been analyzed based on the analytical high power trip setpoints listed in Table 5.10 of Reference 3. Since it was confirmed that the MCPR, limits continue to bound the CRWE ACPR results, the use of the Table 5.10 setpoints continues to be supported for Cycle 20 operation.

The OPRM setpoints are based upon a combination of the cycle-specific DIVOM (Delta over Initial CPR Versus Oscillation Magnitude), the plant-specific HCOM (Hot Channel Oscillation Magnitude), and cycle-specific 2PT (2 recirculation pump trip) results. The cycle-specific DIVOM and 2PT results are the two components of this calculation that are potentially impacted by a CPR correlation error. Two sets of operating limits are reported for each OPRM setpoint, OLMCPR(SS) and OLMCPR(2PT). The DIVOM can impact both OLMCPRs and the 2PT results can only impact the OLMCPR(2PT) results.

DIVOM Impacts: The discussion in the DIVOM approved topical report (BAW-10255PA Revision 2) indicates that the DIVOM analysis is [

3Therefore, there is no DIVOM impact on the OLMCPR(SS) and OLMCPR(2PT) results.

2PT Impacts: The recirculation pump trip cases provide a ratio of the CPR before and after the 2PT trip. An increase in this ratio will result in an increase in the required MCPR prior to the pump trip, that is OLMCPR(2PT). This evaluation considers both the impact on the selection of the OPRM setpoint Ref: 1707-01 Page 7 of 10 AREVA NP Inc.

1707-01-F03 (Rev. 003, 09/08/2011) and on whether operation with the selected setpoint retains adequate CPR margin to compensate for monitoring the core with the unmodified ACE correlation.

The OLMCPR(SS) and OLMCPR(2PT) values provided in Table 4.3 of Reference 3 [

]. The use of these setpoints remains supported with the unmodified ACE correlation in the POWERPLEX-Il1 core monitoring system.

Imoact on Fuel Loadina Error (FLE)

The FLE (misorientation and mislocation) is an infrequent event that is analyzed to assure the off-site dose criteria defined in Section 15.4.7 of NUREG-0800 is not exceeded. [

I Impact on Loss-of-Coolant Accident (LOCA)

A MCPR limit is assumed in the LOCA analyses to apply an upper limit on the hot channel power. A MCPR of 1.34 was used in the Brunswick ATRIUM 1OXM LOCA analysis and is based on a conservatively low K-factor which results in a higher hot assembly power. [

]. Therefore, the results of the Brunswick ATRIUM 1OXM LOCA analysis remain applicable for Brunswick Unit 1 Cycle 20.

Ref: 1707-01 Page 8 of 10 AREVA NP Inc.

1707-01-F03 (Rev. 003, 09/08/2011)

Conclusion This evaluation used a combination of calculations and first principal arguments to address the impacts of the ACE correlation concern on planned Brunswick Unit 1 Cycle 20 licensing and operation. The calculations were performed using the modified version of the ACE correlation, [

I.

The fuel in the Cycle 20 core that is impacted by the ACE K-factor [ ] is the fresh and once-burnt ATRIUM 1OXM fuel type. The co-resident twice-burnt ATRIUM-10 fuel design is licensed and will be monitored with the SPCB correlation and is therefore not impacted.

This operability assessment has evaluated the potential impact on all CPR related limits or analyses associated with the limits reported in the Reference 3 Reload Safety Analysis report. This evaluation has determined the SLMCPR and corresponding MCPR operating limits remain applicable to Brunswick Unit 1 Cycle 20 operation. The potential impact on the core monitoring system was conservatively addressed and was also found to be bounded by both the MCPRp and MCPRf values.

The MCPRp limits were set based in part upon the use of the 111% RBM setpoint and this remains supported with the current MCPRp values. The RBM operability limits were also confirmed to be applicable for Cycle 20 operation.

The OPRM setpoints were evaluated using the modified ACE correlation and confirmed to remain applicable for Cycle 20 operation.

The fuel loading error infrequent event was evaluated and itwas confirmed that the required offsite dose criteria continues to be met.

There is no impact on the LOCA analysis.

In conclusion, no changes are required in the operating limits or instrument setpoints supplied in the Reference 3 Reload Safety Analysis report. These limits may be used to support operation and monitoring with the current POWERPLEX-I11 core monitoring system.

Ref: 1707-01 Page 9 of 10 AREVA NP Inc.

-1707-01-F03 (Rev. 003, 09/08/2011)

APPROVALS:

-Y ________________ *1'-'I* *y.-

,a2--/1-20 13 Approved: Date:

I +

Issue Evaluator - E. E. Riley (Neutronic Design and Analysis)

Approved: /jJ. Date: /_ ((1/3 Issue Evaluator - D. R. Tinkler (TIH Applications)

Approved: 7 Y c c Date:

Peer Review - R. E. Fowles (Neutronic Design and Analysis)

Approved: Date:3 Peer Review - D. D. Crockett (T/H Applications)

Approved: . Date:

Peer Review - M. T. Bunker (T/H Codes and Methods)

Approved: Date: /2 - 1-3 Issue Owner - E. E. Riley (Neutronic Design and Analysis)

Ref: 1707-01 Page 10 of 10 AREVA NP Inc.