ML070230540
| ML070230540 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/16/2007 |
| From: | Westinghouse |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NF-BEX-06-281, Rev 0 | |
| Download: ML070230540 (40) | |
Text
Westinghouse Non-Proprietary Class 3 NF-BEX-06-281 Rev. 0 NP-Attachment Quad Cities Unit 1 Cycle 20 SLMCPR Westinghouse Electric Company Nuclear Fuel 4350 Northern Pike Monroeville, PA 15146
© 2006 Westinghouse Electric Company LLC, All Rights Reserved Page 1 of40
1.0 Introduction This document contains a description of the Safety Limit Minimum Critical Power Ratio (SLMCPR) evaluation for Quad Cities Nuclear Power Station Unit 1 (QCNPS1) Cycle 20, as well as identification of the Critical Power Ratio (CPR) correlation for Global Nuclear Fuel (GNF) GE14 fuel and the "conservative Adder" required by SER restriction 7 of Reference 3.
Dual (DLO) and single (SLO) recirculation loop SLMCPRs of 1.10 and 1.11, respectively, were established for the GEl4 fuel by GNF for Quad Cities Unit 1 (QCNPS1) Cycle 19, and application of the approved methodology in Reference 3 would apply these values to the GE14 fuel in Cycle 20. DLO and SLO recirculation loop SLMCPRs of 1.11 and 1.13, respectively, have been calculated for the Westinghouse SVEA-96 Optima2 assemblies in QCNPS 1 Cycle
- 20. As discussed below, Exelon has elected to apply the higher SLMCPR values of 1.11 and 1.13 established for the Westinghouse fuel to all the assemblies in the core including the GEl 4 Legacy fuel assemblies. As discussed in Reference 13, this conservative approach was also applied for Dresden Nuclear Power Station Unit 3 (DNPS3) Cycle 20.
The GNF NRC-approved methodology (References 1 and 2) was used previously to determine the appropriate SLMCPR values for the currently operating QCNPS1 Cycle 19, which contains all GNF GE14 fuel assemblies.
For QCNPS1 Cycle 20, Exelon Generation Company, LLC (EGC) will load Westinghouse SVEA-96 Optima2 fuel. Therefore, the Westinghouse NRC-approved methodology described in Reference 3 and further clarified in the response to request for additional information (RAI)
D13 of Reference 4, was used to determine the SLMCPRs for Cycle 20. Further clarification of the Westinghouse SLMCPR methodology was also provided to the NRC in support of the transition to SVEA-96 Optima2 fuel in the Quad Cities and Dresden Units as follows:
The response to NRC Request 19 in Reference 9 which supported the Licensing Amendment Request for transition to SVEA-96 Optima2 fuel in the Dresden and Quad Cities plants provided in Reference 8, The technical information supporting the QCNPS2 Technical Specification SLMCPR changes transmitted by Reference 10 as supplemented by the clarifying information in Reference 11.
The same SLMCPR methodology described in these references was followed to establish appropriate GEl4 and SVEA-96 Optima2 SLMCPRs for QCNPS1 Cycle 20. Unlike the GNF methodology, [
NF-BEX-06-281 Rev. 0 NP-Attachment Page 2 of 40
I a,c The EGC proposed license amendment to use the Westinghouse methodology for core reload evaluations at the Dresden and Quad Cities units was submitted to the NRC in Reference 8.
This submittal was approved by the NRC and supported QCNPS2 Cycle 19 and DNPS3 Cycle 20, which contained reload cores of SVEA-96 Optima2 fuel. It also supports QCNPS 1 Cycle 20 with a reload core containing SVEA-96 Optima2 fuel.
Condition 7 in the NRC safety evaluation for Reference 3 requires that a conservative factor applied to the GE14 operating limit minimum critical power ratio (OLMCPR) be identified in licensee applications. The value of this factor for QCNPS 1 Cycle 20 is [XXXX]a,c which was also used for the QCNPS2 Cycle 19 and DNPS3 Cycle 20 licensing analyses.
2.0 GE14 SLMCPR for QCNPS1 Cycle 20 Consistent with the Westinghouse methodology described in Reference 3, the treatment of the SLMCPR in mixed cores containing non-Westinghouse fuel [
a,c The Cycle 19 SLMCPR was determined by GNF based on plant- and cycle-specific analyses using GNF's NRC-approved methodology and uncertainties (References 1 and 2) as supplemented with QCNPSl-specific uncertainties. The GNF evaluation used the GEXL14 correlation for GEl4 fuel. The GNF evaluation confirmed that the DLO and SLO SLMCPRs of 1.10 and 1.11, respectively, in Reference 5 bounded the calculated Cycle 19 results and, therefore, continued to be appropriate for Cycle 19. [
a,c A comparison between the QCNPS I Cycle 19 and 20 cores is shown in Table 1.
3.0 SVEA-96 Optima2 SLMCPR for Cycle 20 In establishing the SLMCPR for Westinghouse SVEA-96 Optima2 fuel assemblies, it is assumed that [
a,c NF-BEX-06-281 Rev. 0 NP-Attachment Page 3 of 40
The SVEA-96 Optima2 SLMCPR for QCNPS1 Cycle 20 is based on a Reference Core design (SVEA-96 Optima2 bundle designs, core loading pattern and state point depletion strategy) that represents realistic current plans for the Cycle 20 loading and operation. The Reference Core loading pattern for Cycle 20 is shown in Figure 1. The Reference Core design was generated via collaboration between EGC and Westinghouse based on EGC's cycle assumptions and design goals. The Reference Core was designed to meet the cycle energy requirements, to satisfy all licensing requirements, to provide adequate thermal margins and operational flexibility, and to meet other design and manufacturing criteria established by EGC and Westinghouse.
In general, the calculated SLMCPR is dominated by the flatness of the assembly CPR distribution across the core and the flatness of the relative pin CPR distribution based on the pin-by-pin power/R-factor distribution in each bundle. Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher SLMCPR.
The calculation of the SLMCPR as a function of cycle exposure captures the interplay between the relative fuel assembly CPR and bundle relative pin-by-pin CPR distributions established from the power/R-factor distributions and allows a determination of the maximum (limiting)
SLMCPR for the entire cycle. This limiting SLMCPR is applied throughout the entire cycle.
The SVEA-96 Optima2 SLMCPR for QCNPS 1 Cycle 20 was determined as a function of cycle exposure based on radial assembly power distributions at least as flat as the cycle exposure-dependent radial power distributions from [
a,c Accordingly, the SVEA-96 Optima2 SLMCPR for DLO operation was calculated at 100%
power and 100% core flow at [
Ia,c In order to confirm that the limiting SLMCPR had been established, additional DLO SLMCPRs were calculated at the cycle exposure at which the maximum 100% core flow DLO SLMCPR occurred. These calculations were performed at 100% power at the minimum allowed core flow (95.3% flow) at rated power and at the maximum licensed core flow (108%) at rated power, as shown in the QCNPS 1 power-to-flow map (Figure 3).
SLO SVEA-96 Optima2 SLMCPR calculations were also performed. These SLMCPR calculations were performed at arc NF-BEX-06-281 Rev. 0 NP-Attachment Page 4 of 40
The SLO calculations used the same procedure as the DLO cases, except that the SLO cases applied a larger uncertainty for the core flow.
The SLMCPR results for Cycle 20 are plotted in Figure 4. As shown in Figure 4, the DLO SLMCPR [
Ia,c the interplay between the assembly relative CPRs and the relative fuel rod CPRs.
In general, as the fraction of assembly or fuel rod CPRs in the vicinity of the minimum assembly or fuel rod CPR increases, the number of rods with a potential for experiencing dryout increases. Therefore, a larger SLMCPR is required to assure that less than 0.1% of the rods are in dryout.
While control rod patterns at individual state points required to maintain margins to thermal limits may perturb the trend, experience has shown that the assembly CPR distributions tend to become [
a,c Therefore, the peak SLMCPR tends to occur when the assembly CPR and rod CPR distributions combine to place the maximum number of fuel rod CPRs close to the minimum CPR.
This behavior is shown for the QCNPS 1 Cycle 20 SLMCPR by the relative assembly CPR and relative fuel rod histograms shown in Figures 5 through 15 and 16 through 30, respectively. In Figures 5 through 15, assembly types QA20, QB20, and QC20 refer to the SVEA-96 Optima2 assembly types loaded in Cycle 20. Assembly type I a,c Inspection of the DLO histograms in Figures 5 through 15 and the relative fuel rod CPR histograms in Figures 16 through 30 leads to the following observations, which explain the SLMCPR behavior in Figure 4:
- 1. [
2.
3.
NF-BEX-06-281 Rev. 0 NP-Attachment Page 5 of 40
4.
I a,c Therefore, the DLO SLMCPR results at rated conditions in Figure 4 can be explained in terms of I a,c As noted above, the continued adequacy of a DLO SLMCPR of [
a,c The SLO results calculated at [
I a,c NF-BEX-06-281 Rev. 0 NP-Attachment Page 6 of 40
In addition to the strong dependence on assembly CPR and relative fuel rod CPR distributions, the SLMCPR is strongly dependent on the distribution of assembly and relative fuel pin CPRs about their mean values leading to an overall distribution of fuel rod CPRs relative to their mean values. The wider these distributions, the higher the SLMCPR must be to prevent 0.1%
of the fuel rods from experiencing boiling transition. The distributions of fuel rod CPRs relative to their mean values are determined by the uncertainties relative to the mean CPRs.
Accordingly, the uncertainties used in establishing the SVEA-96 Optima2 SLMCPR for Cycle 20 are shown in Table 2.
4.0 Westinghouse CPR Correlation for GE14 Fuel The Westinghouse CPR correlation for GE14 fuel used in the QCNPS1 reload design and licensing analyses is the same as that used for QCNPS2 Cycle 19 and DNPS3 Cycle 20 and described in the Response to NRC Request 8 in Reference 9. Further clarification of the correlation was provided in the response to NRC Request 2 in Reference 11 as well as in Reference 12.
a,c The determination of this value was also based on EGC's plans to continue to monitor the CPR performance of GEl4 fuel using the GNF GEXL14 correlation within the POWERPLEX-II online core monitoring system rather than the USAG14 correlation. This approach is consistent with Westinghouse's NRC-approved methodology described in Reference 3.
5.0 References
- 1. Letter, Frank Akstulewicz (NRC) to Glen A. Watford (GE), Acceptancefor Referencing ofLicensing Topical Reports NEDC-32601P,Methodology and Uncertaintiesfor Safety Limit MCPR Evaluations; NEDC-32694P,PowerDistribution Uncertaintiesfor Safety Limit MCPR Evaluation; and Amendment 25 to NEDE-2401 1-P-A on Cycle Specific Safety Limit MCPR, (TAC Nos. M97490, M99069, and M97491), March 11, 1999.
- 2. General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation,and Design Application, NEDO-10958-A, January 1977.
- 3. Licensing Topical Report, Reference Safety Reportfor Boiling Water Reactor Reload Fuel, CENPD-300-P-A, July 1996.
- 4. CENPD-389-P-A, 1OxlO SVEA Fuel CriticalPower Experiments and CPR Correlations:SVEA-96+,
August 1999.
- 5. Quad Cities Technical Specifications, Section 2.1.1.2
- 6. WCAP-16081-P-A, lOxlO SVEA Fuel CriticalPower Experiments and CPR Correlation: SVEA-96 Optima2, March 2005.
- 7. Letter, Jason S. Post (GE) to NRC, Part21 60 Day Interim Report Notification.: CriticalPower Determinationfor GEl4 and GE12 Fuel With Zircaloy Spacers, MFN 05-058 Rev 1, June 24, 2005, and GE Energy - Nuclear, 10 CFR Part 21 Communication, 60-Day Interim Report Notification and NF-BEX-06-281 Rev. 0 NP-Attachment Page 7 of 40
Transfer of Information, CriticalPower Determinationfor GEl4 and GEl2 Fuel With Zircaloy Spacers, SC05-04 Rev 1, June 24, 2005.
- 8. Letter, Patrick R. Simpson (Exelon Generation Company, LLC) to NRC, Requestfor License Amendment Regarding Transition to Westinghouse Fuel, dated June 15, 2005.
- 9. RS-06-009, Additional Information SupportingRequest for License Amendment Regarding Transition to Westinghouse Fuel, January 26, 2006.
- 10. Letter from Patrick R. Simpson, Exelon Nuclear, to U.S. NRC, Requestfor Technical Specifications Changefor Minimum CriticalPower Ratio Safety Limit, QCNPS Unit 2, Decemberl 5, 2005.
- 11. RS-06-024, AdditionalInformation SupportingRequest for Technical Specifications Changefor Minimum CriticalPower Ratio Safety Limit, QCNPS, Unit 2, February 13, 2006.
- 12. RS-06-038, AdditionalInformation SupportingRequest for Licensing Amendment Request Regarding Transition to Westinghouse Fuel and Request for Technical Specifications Changefor Minimum CriticalPower Ratio Safety Limit, March 3, 2006.
13 Letter from NRC (John Honcharik) to EXELON GENERATION COMPANY, LLC, dated November 7, 2006, Dresden Nuclear Power Station, Unit 3- Issuance ofAmendment RE: Minimum CriticalPower Ration Safety Limit (TAC No. MD2706)
NF-BEX-06-281 Rev. 0 NP-Attachment Page 8 of 40
Table 1 Comparison of Cycle 19 and 20 Cores Description Quad Cities Unit 1 Quad Cities Unit 1 Cycle 19 Cycle 20 Number of Bundles in Core 724 724 Limiting Cycle Exposure Point N/A (GNF proprietary) Near EOC Cycle Exposure at Limiting DLO Point, EFPH N/A (GNF proprietary) 14282 EFPH Reload Fuel Type GE14 SVEA-96 Optima2 Reload Batch Average Weight % Enrichment 4.09 w/o 4.01 w/o Reload Batch Fraction (%) 27.1% 35.9%
Batch Fraction of SVEA-96 Optima2 Fuel 00.0% 35.9%
Batch Fraction of GNF GE14 Fuel 100% 64.1%
Core Average Weight % Enrichment 3.40 w/o 3.96 w/o Calculated Safety Limit MCPR (DLO) 1.10 for all fuel types a,c Calculated Safety Limit MCPR (SLO) 1.11 for all fuel types ] a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 9 of 40
Table 2 - Uncertainties used in Quad Cities 1 Cycle 20 SVEA-96 Optima2 SLMCPR Determination a.c t -I- +
i + i 4 +
i + i i + +
4 + +
NF-BEX-06-281 Rev. 0-NP-Attachment Page 10 of 40
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I I I I I I I I I I i I i i i i iI I!
Assembly Number of Serial Number Cycle Type # Assembly Name Assemblies Range First Loaded 16 GE14-P1ODNAB411-14GZ-10OT-145-T6-2564 128 JLE001-JLE152 18 17 GE14-P1ODNAB409-15GZ-100T-145-T6-2565 104 JLE153-JLE296 18 1 GE 14-P1ODNAB194-4G7.0-10OT-145-T6-2647 36 JLH731-JLH963 18A 2 GE14-P1ODNAB409-17GZ-100T-145-T6-2825 128 JLT101-JLT228 19 3 GE14-P1ODNAB408-15GZ-10OT-145-T6-2826 68 JLT229-JLT296 19 31 Opt2-3.99-15GZ8.00-3G6.00 56 QAA001-QAA056 20 32 Opt2-4.00-13GZ8.00-3G6.00 136 QAA057-QAA192 20 33 Opt2-4.05-12GZ7.00-2G6.00 68 QAA193-QAA260 20 Figure 1 Quad Cities Unit 1 Cycle 20 Reference Loading Pattern NF-BEX-06-281 Rev. 0-NP-Attachment Page I11of 40
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.l 1 2 17 .216 6 2 17 2 - 3 7 2 11733321711711' 1 17 1 32 3 17 1 16 116 _-
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86 16 171716 1 17 1 U1, 1 1 161 1 81 1 1 17 16 1117 17 11 17117 1 161717 1 1 1 4 1 16 16 17 17 16116 17 17 16 16 1 2 11 1 1 1 Assembly Number of Serial Number Cycle Typeml Assembly Name Assemblies Range Loaded 16 GE14-P1ODNAB411-14GZ-100T-145-T6-2564 152 JLE001-JLE152 18 17 GE14-P1ODNAB409-15GZ-10OT-145-T6-2565 144 JLE153-JLE296 18 1 GE 14-P1ODNAB194-4G7.0-10OT-145-T6-2647 232 JLH731-JLH963 18A 2 GE14-P1ODNAB409-17GZ-10OT-145-T6-2825 128 JLT101-JLT228 19 3 GE14-P1ODNAB408-15GZ-10OT-145-T6-2826 68 JLT229-JLT296 19 Figure 2 Quad Cities Unit 1 Cycle 19 Reference Loading Pattern NF-BEX-06-281 Rev. 0-NP-Attachment Page 12 of 40
120 110 100 0
TI 0
CL D)
IL 0 20 30 40 50 60 70 80 90 100 110 120 Core Flow (%)
Figure 3 - QCNPS 1 Power Flow Map (Nominal Feedwater Temperature)
NF-BEX-06-281 Rev. 0-NP-Attachment Page 13 of 40
a,c Figure 4 Quad Cities 1, Cycle 20 SLMCPR Results for SVEA-96 Optima2 Fuel NF-BEX-06-281 Rev. 0-NP-Attachment Page 14 of 40
Figure 5 - Assembly Histograms axc NF-BEX-06-281 Rev. 0-NP-Attachment Page 15 of 40
Figure 6 - Assembly Histograms ac NF-BEX-06-281 Rev. 0-NP-Attachment Page 16 of 40
Figure 7 - Assembly Histograms axc NF-BEX-06-281 Rev. 0-NP-Attachment Page 17 of 40
Figure 8 - Assembly Histograms axc NF-BEX-06-281 Rev. 0-NP-Attachment Page 18 of 40
Figure 9 - Assembly Histograms axc NF-BEX-06-281 Rev. O-NP-Attachment Page 19 of 40
Figure 10 - Assembly Histograms ax NF-BEX-06-281 Rev. 0-NP-Attachment Page 20 of 40
Figure 11 - Assembly Histograms axc NF-BEX-06-281 Rev. 0-NP-Attachment Page 21 of 40
SLO Figure 12 - Assembly Histograms alc Page 22 of 40 NF-BEX-06-281 Rev. 0-NP-Attachment
Figure 13 - Assembly Histograms SLO axC NF-BEX-06-281 Rev. 0-NP-Attachment Page 23 of 40
Figure 14 - Assembly Histograms SLO a.c NF-BEX-06-281 Rev. 0-NP-Attachment Page 24 of 40
Figure 15 - Assembly Histograms 100/95.3 and 100/108 ax NF-BEX-06-281 Rev. 0-NP-Attachment Page 25 of 40
Figure 16 - Fuel Rod Histograms a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 26 of 40
Figure 17 - Fuel Rod Histograms - a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 27 of 40
- Figure 18 - Fuel Rod Histograms __ a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 28 of 40
Figure 19 - Fuel Rod Histograms ac NF-BEX-06-281 Rev. 0-NP-Attachment Page 29 of 40
Figure 20 - Fuel Rod Histograms __ a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 30 of 40
Figure 21 - Fuel Rod Histograms a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 31 of 40
Figure 22 - Fuel Rod Histograms NF-BEX-06-281 Rev. 0-NP-Attachment Page 32 of 40
Figure 23 - Fuel Rod Histograms
- a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 33 of 40
Figure 24 - Fuel Rod Histograms __ a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 34 of 40
Figure 25 - Fuel Rod Histograms _
- a~c NF-BEX-06-281 Rev. 0-NP-Attachment Page 35 of 40
Figure 26 - Fuel Rod Histograms __ a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 36 of 40
Figure 27 - Fuel Rod Histograms -1 a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 37 of 40
Figure 28 - Fuel Rod Histograms
- a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 38 of 40
Figure 29 - Fuel Rod Histograms a,c NF-BEX-06-28 1 Rev. 0-NP-Attachment Page 39 of 40
- Figure 30 - Fuel Rod Histograms -a,c NF-BEX-06-281 Rev. 0-NP-Attachment Page 40 of 40