GO2-14-139, Attachment 6 - GNF-001N8896-R3-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Columbia Cycle 23

Attachment 6 - GNF-001N8896-R3-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Columbia Cycle 23

ML14336A007
Person / Time
Site:	Columbia
Issue date:	10/31/2014
From:	Global Nuclear Fuel - Americas
To:	Office of Nuclear Reactor Regulation
References
GO2-14-139 GNF-001N8896-R3-NP
Download: ML14336A007 (26)

Text

LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION CHANGE TO SAFETY LIMIT MINIMUM CRITICAL POWER RATIO Attachment 5 GNF-001 N8896-R3-NP GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Columbia Cycle 23 Non-Proprietary version

GNFM Global Nuclear Fuel Global Nuclear Fuel A Joint Venture of GE.1Toshibao

& Hitachi GNF-001N8896-R3-NP PLM Report Specification: 001N8896 R3 October 2014 Non-ProprietaryInformation - Class I (Public)

GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Columbia Cycle 23 Copyright2014 GlobalNuclear Fuels-Americas, LLC All Rights Reserved

GNF-OO1N8869-R3-NP Non-Proprietary Information - Class I (Public)

Information Notice This is a non-proprietary version of the document GNF-001N8869-R3-P, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( )).

Important Notice Regarding Contents of this Report Please Read Carefully The design, engineering, and other information contained in this document is furnished for the purpose of supporting Energy Northwest in proceedings before the United States (US) Nuclear Regulatory Commission. The only undertakings of GNF-A with respect to information in this document are contained in contracts between GNF-A and its customers, and nothing contained in this document shall be construed as changing those contracts. The use of this information by anyone for any purposes other than those for which it is intended is not authorized; and with respect to any unauthorized use, GNF-A makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.

ii

GNF-OO1N8869-R3-NP Non-Proprietary Information - Class I (Public)

Table of Contents 1.0 M ETH ODOLO GY .......................................................................................................................................... 1 2.0 DISCUSSION ................................................................................................................................................... 1 2.1. MAJOR CONTRIBUTORS TO SLM CPR CHANGE ......................................................................................... 1 2.2. DEVIATIONS IN NRC-APPROVED UNCERTAINTIES ..................................................................................... 2 2.2.1. R-Factor ................................................................................................................................................ 2 2.2.2. Core Flow Rate and Random Effective TIP Reading....................................................................... 3 2.3. DEPARTURE FROM NRC-APPROVED METHODOLOGY ................................................................................ 3 2.4. FUEL AXIAL POWER SHAPE PENALTY ............................................................................................................ 4 2.5. METHODOLOGY RESTRICTIONS ...................................................................................................................... 4 2.6. MINIMUM CORE FLOW CONDITION ........................................................................................................ 5 2.7. LIMITING CONTROL ROD PATTERNS ...................................................................................................... 6 2.8. CORE M ONITORING SYSTEM .......................................................................................................................... 6 2.9. POWER/FLOW MAP ......................................................................................................................................... 6 2.10. CORE LOADING DIAGRAM .......................................................................................................................... 6 2.11. FIGURE REFERENCES .................................................................................................................................. 6 2.12. ADDITIONAL SLM CPR LICENSING CONDITIONS .................................................................................... 6 2.13. 10 CFR PART 21 EVALUATION ................................................................................................................... 6 2 .14 . S UMMARY .................................................................................................................................................. 6

3.0 REFERENCES

................................................................................................................................................ 7 List of Figures FIGURE 1. CURRENT CYCLE CORE LOADING DIAGRAM ................................................................................................. 9 FIGURE 2. PREVIOUS CYCLE CORE LOADING DIAGRAM ................................... ............... 10 FIGURE 3. FIGURE 4.1 FROM NEDC-32601P-A ....................................................................................................... 11 FIGURE 4. FIGURE 111.5-1 FROM NEDC-3260 IP-A ................................................................................................ 12 FIGURE 5. RELATIONSHIP BETW EEN M IP AND CPR MARGIN .................................................................................. 13 List of Tables TABLE 1. DESCRIPTION OF CORE ................................................................................................................................. 14 TABLE 2. SLM CPR CALCULATION M ETHODOLOGIES ............................................................................................. 15 TABLE 3. M ONTE CARLO CALCULATED SLM CPR vs. ESTIMATE .......................................................................... 16 TABLE 4. NON-POWER DISTRIBUTION UNCERTAINTIES ............................................................................................... 18 TABLE 5. POW ER DISTRIBUTION UNCERTAINTIES .................................................................................................. 20 TABLE 6. CRITICAL POW ER UNCERTAINTIES ............................................................................................................... 22 Table of Contents iii

GNF-001N8869-R3-NP Non-Proprietary Information - Class I (Public) 1.0 Methodology Global Nuclear Fuel (GNF) performs Safety Limit Minimum Critical Power Ratio (SLMCPR) calculations in accordance to NEDE-24011-P-A "General Electric Standard Application for Reactor Fuel," Revision 20 (Reference 1) using the following Nuclear Regulatory Commission (NRC) -approved methodologies and uncertainties:

• NEDC-32601P-A, "Methodology and Uncertainties for Safety Limit MCPR Evaluations," August 1999. (Reference 2)

• NEDC-32694P-A, "Power Distribution Uncertainties for Safety Limit MCPR Evaluations," August 1999. (Reference 3)

• NEDC-32505P-A, "R-Factor Calculation Method for GEl1, GE12 and GE13 Fuel,"

Revision 1, July 1999. (Reference 4)

Table 2 identifies the actual methodologies used for the Columbia Cycle 22 and Cycle 23 SLMCPR calculations.

2.0 Discussion In this discussion, the Two Loop Operation (TLO) nomenclature is used for two recirculation loops in operation, and the Single Loop Operation (SLO) nomenclature is used for one recirculation loop in operation.

2.1. Major Contributors to SLMCPR Change In general, the calculated safety limit is dominated by two key parameters: (1) flatness of the core bundle-by-bundle Minimum Critical Power Ratio (MCPR) distribution; and (2) flatness of the bundle pin-by-pin power/R-Factor distribution. Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher calculated SLMCPR. MCPR Importance Parameter (MIP) measures the core bundle-by-bundle MCPR distribution and R-Factor Importance Parameter (RIP) measures the bundle pin-by-pin power/R-Factor distribution. The effect of the fuel loading pattern on the calculated TLO SLMCPR using rated core power and rated core flow conditions has been correlated to the parameter MIPRIP, which combines the MIP and RIP values.

Table 3 presents the MIP and RIP parameters for the previous cycle and the current cycle along with the TLO SLMCPR estimate using the MIPRIP correlation. If the minimum core flow case is applicable, the TLO SLMCPR estimate is also provided for that case although the MIPRIP correlation is only applicable to the rated core flow case. This is done only to provide some reasonable assessment basis of the minimum core flow case trend. In addition, Table 3 presents estimated effects on the TLO SLMCPR due to methodology deviations, penalties, and/or uncertainty deviations from approved values. Based on the MIPRIP correlation and any effects Methodology I

GNF-OO1N8869-R3-NP Non-Proprietary Information - Class I (Public) due to deviations from approved values, a final estimated TLO SLMCPR is determined. Table 3 also provides the actual calculated Monte Carlo SLMCPRs. Given the bias and uncertainty in the MIPRIP correlation (( 1] and the inherent variation in the Monte Carlo results (( )), the change in the Columbia Cycle 23 calculated Monte Carlo TLO SLMCPR using rated core power and rated core flow conditions is consistent with the corresponding estimated TLO SLMCPR value.

The intent of the final estimated TLO SLMCPR is to provide an estimate to check the reasonableness of the Monte Carlo result. It is not used for any other purpose. The methodology and final SLMCPR is based on the rigorous Monte Carlo analysis.

The items in Table 3 that result in the increase of the estimated SLMCPR are discussed in Section 2.2.

Cycle 23 will be the first full reload of GNF2 for Columbia. The critical power uncertainty for GNF2 is defined in Table 6. As seen in Table 6, the critical power uncertainty for GNF2 is higher than the previous cycle's fuel type (GE14). As such, the GEXL uncertainty of the new fuel type tends to make the final SLMCPR higher.

2.2. Deviations in NRC-Approved Uncertainties Tables 4 and 5 provide a list of NRC-approved uncertainties along with the values actually used.

A discussion of deviations from these NRC-approved values follows, all of which are conservative relative to the NRC-approved values. Also, the estimated effect on the SLMCPR is provided in Table 3 for each deviation.

2.2.1. R-Factor At this time, GNF has generically increased the GEXL R-Factor uncertainty from ((

1] to account for an increase in channel bow due to the emerging unforeseen phenomena called control blade shadow corrosion-induced channel bow, which is not accounted for in the channel bow uncertainty component of the approved R-Factor uncertainty. The step "a RPEAK" in Figure 4.1 from NEDC-32601P-A (Reference 2), which has been provided for convenience in Figure 3 of this document, is affected by this deviation. Reference 5 technically justifies that a GEXL R-Factor uncertainty of (( )) accounts for a channel bow uncertainty of up to

(( 1].

GNF calculations predict control blade shadow corrosion-induced channel bow to the extent that an increase in the NRC-approved R-Factor uncertainty (( )) is deemed prudent to address its effect. Accounting for the control blade shadow corrosion-induced channel bow, the Columbia Cycle 23 analysis shows an expected channel bow uncertainty of (( 1], which is bounded by a GEXL R-Factor uncertainty of (( 1]. Thus the use of a GEXL R-Factor uncertainty of (( 11 adequately accounts for the expected control blade shadow corrosion-induced channel bow for Columbia Cycle 23.

Discussion 2

GNF-001N8869-R3-NP Non-Proprietary Information - Class I (Public) 2.2.2. Core Flow Rate and Random Effective TIP Reading In Reference 6, GNF committed to the expansion of the state points used in the determination of the SLMCPR. Consistent with the Reference 6 commitments, GNF performs analyses at the rated core power and minimum licensed core flow point in addition to analyses at the rated core power and rated core flow point. The approved SLMCPR methodology is applied at each state point that is analyzed.

For the TLO calculations performed at 80.7% core flow, the approved uncertainty values for the core flow rate (2.5%) and the random effective Traversing In-Core Probe (TIP) reading (1.2%)

are conservatively adjusted by dividing them by 80.7/100. The steps "a CORE FLOW" and 1a TIP (INSTRUMENT)" in Figure 4.1 from NEDC-32601P-A (Reference 2), which has been provided for convenience in Figure 3 of this document, are affected by this deviation.

Historically, these values have been construed to be somewhat dependent on the core flow conditions as demonstrated by the fact that higher values have always been used when performing SLO calculations. It is for this reason that GNF determined that it is appropriate to consider an increase in these two uncertainties when the core flow is reduced. The amount of increase is determined in a conservative way. For both parameters it is assumed that the absolute uncertainty remains the same as the flow is decreased so that the percentage uncertainty increases inversely proportional to the change in core flow. This is conservative relative to the core flow uncertainty because the variability in the absolute flow is expected to decrease somewhat as the flow decreases. For the random effective TIP uncertainty, there is no reason to believe that the percentage uncertainty should increase as the core flow decreases for TLO.

Nevertheless, this uncertainty is also increased as is done in the more extreme case for SLO primarily to preserve the historical precedent established by the SLO evaluation. Note that the TLO condition is different than the SLO condition because for TLO there is no expected tilting of the core radial power shape.

The treatment of the core flow and random effective TIP reading uncertainties is based on the assumption that the signal to noise ratio deteriorates as core flow is reduced. GNF believes this is conservative and may in the future provide justification that the original uncertainties (non-flow dependent) are adequately bounding.

The core flow and random TIP reading uncertainties used in the SLO minimum core flow SLMCPR analysis remain the same as in the rated core flow SLO SLMCPR analysis because these uncertainties (which are substantially larger than used in the TLO analysis) already account for the effects of operating at reduced core flow.

2.3. Departure from NRC-Approved Methodology No departures from NRC-approved methodologies were used in the Columbia Cycle 23 SLMCPR calculations.

Discussion 3

GNF-001N8869-R3-NP Non-Proprietary Information - Class I (Public) 2.4. Fuel Axial Power Shape Penalty At this time, GNF has determined that higher uncertainties and non-conservative biases in the GEXL correlations for the various types of axial power shapes (i.e., inlet, cosine, outlet, and double hump) could potentially exist relative to the NRC-approved methodology values (References 7, 8, 9, and 10). The following table identifies, by marking with an "X", this potential for each GNF product line currently being offered:

((

Axial bundle power shapes corresponding to the limiting SLMCPR control blade patterns are determined using the PANACEA 3D core simulator. These axial power shapes are classified in accordance to the following table:

If the limiting bundles in the SLMCPR calculation exhibit an axial power shape identified by this table, GNF penalizes the GEXL critical power uncertainties to conservatively account for the effect of the axial power shape. Table 6 provides a list of the GEXL critical power uncertainties determined in accordance with the NRC-approved methodology contained in NEDE-2401 1-P-A (Reference 1) along with values actually used.

For the limiting bundles, the fuel axial power shapes in the SLMCPR analysis were examined to determine the presence of axial power shapes identified in the above table. These power shapes were not found; therefore, no power shape penalties were applied to the calculated Columbia Cycle 23 SLMCPR values.

2.5. Methodology Restrictions The four restrictions identified on page 3 of NRC's Safety Evaluation (SE) relating to the General Electric licensing topical reports NEDC-32601P (Reference 2), NEDC-32694P Discussion 4

GNF-001N8869-R3-NP Non-Proprietary Information - Class I (Public)

(Reference 3), and Amendment 25 to NEDE-24011-P-A (Reference 1) are addressed in References 11, 12, 7, and 13.

The four restrictions for GNF2 were determined to be acceptable by the NRC review of "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-33270P, March 2007, and GEXL17 Correlation for GNF2 Fuel, NEDC-33292P, March 2007,"

(Reference 14). Specifically, in the NRC audit report (Reference 15) for the said document, Section 3.4.1 page 59 states:

"The NRC staff's SE of NEDC-32694P-A (Reference 19 of NEDC-33270P) provides four actions to follow whenever a new fuel design is introduced. These four conditions are listed in Section 3.0 of tie SE. The analysis and evaluation of the GNF2 fuel design was evaluated in accordance with the limitations and conditions stated in the NRC staff's SE, and is acceptable."

GNF's position is that GNF2 is an evolutionary fuel product based on GE14. It is not considered a new fuel design as it maintains the previously established 10xlO array and two water rod makeup, as stated by the NRC audit report (Reference 15), Section 3.4.2.2.1 page 59:

"The NRC staff finds that the calculational methods, evaluations and applicability of the OLMCPR and SLMCPR are in accordance with existing NRC-approved methods and thus valid for use with GNF2 fuel."

As such, no new GNF fuel designs are being introduced in Columbia Cycle 23; therefore, the NEDC-32505P-A (Reference 4) statement "...if new fuel is introduced, GENE must confirm that the revised R-Factor method is still valid based on new test data" is not applicable.

2.6. Minimum Core Flow Condition For Columbia Cycle 23, the minimum core flow SLMCPR calculation performed at 80.7% core flow and rated core power condition was limiting as compared to the rated core flow and rated core power condition. At low core flows, the limiting rod pattern and the nominal rod pattern are essentially the same. Additionally, the condition that MIP ((

1] establishes a reasonably bounding limiting rod pattern. Hence, the rod pattern used to calculate the SLMCPR at 100% rated power/80.7% rated flow reasonably assures that at least 99.9% of the fuel rods in the core would not be expected to experience boiling transition during normal operation or anticipated operational occurrences (AOOs) during the operation of Columbia Cycle 23. Consequently, the SLMCPR value calculated from the 80.7% core flow and rated core power condition limiting MCPR distribution reasonably bounds this mode of operation for Columbia Cycle 23.

Discussion 5

GNF-0O1N8869-R3-NP Non-Proprietary Information - Class I (Public) 2.7. Limiting Control Rod Patterns The limiting control rod patterns used to calculate the SLMCPR reasonably assures that at least 99.9% of the fuel rods in the core would not be expected to experience boiling transition during normal operation or AQOs during the operation of Columbia Cycle 23.

2.8. Core Monitoring System For Columbia Cycle 23, the 3DMONICORE system will be used as the core monitoring system.

2.9. Power/Flow Map The utility has provided the current and previous cycle power/flow map in a separate document.

2.10. Core Loading Diagram Figures 1 and 2 provide the core-loading diagram for the current and previous cycle respectively, which are the reference loading pattern as defined by NEDE-24011-P-A (Reference 1). Table 1 provides a description of the core.

2.11. Figure References Figure 3 is Figure 4.1 from NEDC-32601P-A (Reference 2). Figure 4 is Figure 111.5-1 from NEDC-32601P-A (Reference 2). Figure 5 is based on Figure 111.5-2 from NEDC-32601P-A (Reference 2), and has been updated with GE14 and GNF2 data.

2.12. Additional SLMCPR Licensing Conditions For Columbia Cycle 23, no additional SLMCPR licensing conditions are included in the analysis.

2.13. 10 CFR Part 21 Evaluation There are no known 10 Code of Federal Regulations (CFR) Part 21 factors that affect the Columbia Cycle 23 SLMCPR calculations.

2.14. Summary The requested changes to the Technical Specification SLMCPR values are 1.10 for TLO and 1.13 for SLO for Columbia Cycle 23.

Discussion 6

GNF-001N8869-R3-NP Non-Proprietary Information - Class I (Public) 3.0 References

1. Global Nuclear Fuel, "General Electric Standard Application for Reactor Fuel,"

NEDE-24011-P-A, Revision 20, December 2013.

2. GE Nuclear Energy, "Methodology and Uncertainties for Safety Limit MCPR Evaluations," NEDC-32601P-A, August 1999.

3. GE Nuclear Energy, "Power Distribution Uncertainties for Safety Limit MCPR Evaluations," NEDC-32694P-A, August 1999.

4. GE Nuclear Energy, "R-Factor Calculation Method for GEl 1, GE12 and GE13 Fuel,"

NEDC-32505P-A, Revision 1, July 1999.

5. Letter, John F. Schardt (GNF-A) to US NRC Document Control Desk with attention to Mel B. Fields (NRC), "Shadow Corrosion Effects on SLMCPR Channel Bow Uncertainty," FLN-2004-030, November 10, 2004.

6. Letter, Jason S. Post (GENE) to US NRC Document Control Desk with attention to Chief, Information Management Branch, et al. (NRC), "Part 21 Final Report: Non-Conservative SLMCPR," MFN 04-108, September 29, 2004.

7. Letter, Glen A. Watford (GNF-A) to US NRC Document Control Desk with attention to Joseph E. Donoghue (NRC), "Final Presentation Material for GEXL Presentation -

February 11, 2002," FLN-2002-004, February 12, 2002.

8. Letter, Glen A. Watford (GNF-A) to US NRC Document Control Desk with attention to Alan Wang (NRC), "NRC Technology Update - Proprietary Slides - July 31 -

August 1, 2002," FLN-2002-015, October 31, 2002.

9. Letter, Jens G. Munthe Andersen (GNF-A) to US NRC Document Control Desk with attention to Alan Wang (NRC), "GEXL Correlation for 1OX10 Fuel," FLN-2003-005, May 31, 2003.

10. Letter, Andrew A. Lingenfelter (GNF-A) to US NRC Document Control Desk with cc to MC Honcharik (NRC), "Removal of Penalty Being Applied to GE14 Critical Power Correlation for Outlet Peaked Axial Power Shapes," FLN-2007-031, September 18, 2007.

11. Letter, Glen A. Watford (GNF-A) to US NRC Document Control Desk with attention to R. Pulsifer (NRC), "Confirmation of 10xlO0 Fuel Design Applicability to Improved SLMCPR, Power Distribution and R-Factor Methodologies," FLN-2001-016, September 24, 2001.

References 7

GNF-001N8869-R3-NP Non-Proprietary Information - Class I (Public)

12. Letter, Glen A. Watford (GNF-A) to US NRC Document Control Desk with attention to Joseph E. Donoghue (NRC), "Confirmation of the Applicability of the GEXL14 Correlation and Associated R-Factor Methodology for Calculating SLMCPR Values in Cores Containing GE14 Fuel," FLN-2001-017, October 1, 2001.

13. Letter, Andrew A. Lingenfelter (GNF-A) to US NRC Document Control Desk with cc to SS Philpott (NRC), "Amendment 33 to NEDE-24011-P, General Electric Standard Application for Reactor Fuel (GESTAR II) and GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-33270P, Revision 3, March 2010,"

MFN 10-045, March 5, 2010.

14. Letter, Andrew A. Lingenfelter (GNF) to US NRC Document Control Desk with cc to MC Honcharik (NRC), "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-33270P, March 2007, and GEXL17 Correlation for GNF2 Fuel, NEDC-33292P, March 2007," FLN-2007-011, March 14, 2007.

15. Memorandum, Michelle C. Honcharik (NRC) to Stacey L. Rosenberg (NRC), "Audit Report for Global Nuclear Fuels GNF2 Advanced Fuel Assembly Design GESTAR II Compliance Audit," September 25, 2008. (ADAMS Accession Number ML081630579)

References 8

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Figure 1. Current Cycle Core Loading Diagram Figure 1. Current Cycle Core Loading Diagram 9

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5 7 8 10 7 7 8 10 8 7 5 58 5 88 12 19 7 3 17 3 7 19 12 8 8 5 56 6 12 13 8 14 3 13 3 18 3 14 8 13 12 6 54 10 7 7 18 8 3 2 14 3 13 3 8 18 7 7 10 52 5 6 7 7 8 18 3 13 13 2 18 2 13 3 18 8 7 7 6 5 50 8 12 7 8 7 3 13 2 2 18 2 19 2 13 3 7 8 7 12 8 48 5 8 13 18 18 3 12 3 13 18 2 19 3 13 3 12 3 18 18 13 8 5 46 5 7 12 8 8 3 13 3 13 2 2 17 2 17 2 13 3 13 3 8 8 12 7 5 44 10 8 19 14 3 13 2 13 2 19 10 2 13 2 19 2 13 2 13 3 14 19 8 10 42 8 10 7 3 13 2 19 3 17 2 2 13 2 13 2 17 3 19 2 13 3 7 10 8 40 7 8 3 18 3 18 2 19 2 13 17 2 17 2 13 2 19 2 18 3 18 3 8 7 38 8 7 17 3 14 2 18 2 17 2 2 19 213 2 17 2 18 2 14 3 17 7 8 36 8 7 3 13 2 13 2 18 2 10 8 2 17 2 10 2 18 2 13 2 13 3 7 8 34 7 8 17 3 10 3 8 13 8 19 2 19 2 7 19 8 13 8 3 10 3 17 8 7 32 7 8 17 3 10 3 8 13 8 19 2 19 2 7 19 8 13 8 3 10 3 17 8 7 30 8 7 3 13 2 13 2 18 2 10 8 2 17 2 10 2 18 2 13 2 13 3 7 8 28 8 7 17 3 14 2 18 2 17 2 2 19 2 13 2 17 2 18 2 14 3 17 7 8 26 7 8 3 18 3 18 2 19 2 13 17 2 17 2 13 2 19 2 18 3 18 3 8 7 24 8 10 7 3 13 2 19 3 17 2 2 13 2 13 2 17 3 19 2 13 3 7 10 8 22 10 8 19 14 3 13 2 13 2 19 10 2 13 2 19 2 13 2 13 3 14 19 8 10 20 5 7 12 8 8 3 13 3 13 2 2 17 2 17 2 13 3 13 3 8 8 12 7 5 18 5 8 13 18 18 3 12 3 13 18 2 19 3 13 3 12 3 18 18 13 8 5 16 8 12 7 8 7 3 13 2 2 18 2 19 2 13 3 7 8 7 12 8 14 5 6 7 7 8 18 3 13 13 2 18 2 13 3 18 8 7 7 6 5 12 10 7 7 18 8 3 2 14 3 13 3 8 18 7 7 10 10 6 12 13 8 14 13 3 18 3 14 8 13 12 6 8 5 8 8 12 19 3 17 3 7 19 12 8 8 5 6 578 7 7 8 10 8 7 5 4 10 10 7 8 8 7 7 8 8 7 81010 2 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 Fuel Type 2 GE14-P 10CNAB407-18GZ-120T- 150-T6-4209 (Cycle 22) 12 GE14-PIOCNAB408-18GZ-120T-150-T6-3174 (Cycle 20) 3 GE14-P IOCNAB407-10G7.0/4G6.0-120T-150-T6-4208 (Cycle 22) 13 GEI4-P1OCNAB408-16GZ-120T-150-T6-3395 (Cycle 21) 5 ATRMI0-P1OCAZB414-15GZ-IOOU-9WR-149-T6-3136 (Cycle 19) 14 GE14-P10CNAB408-1GGZ-120T-150-T6-3974 (Cycle 21) 6 ATRM1O-PIOCAZB414-14GZ-100U-9WR-149-T6-3137 (Cycle 19) 17 GE14-PIOCNAB408-16GZ-12OT-150-T6-3976 (Cycle 21) 7 GEI4-PIOCNAB407-15GZ-12OT-150-T6-3173 (Cycle 20) 18 GE14-P1OCNAB408-16GZ-120T-150-T6-3398 (Cycle 21) 8 GE14-P10CNAB408-18GZ-120T-150-T6-3171 (Cycle 20) 19 GE14-PIOCNAB408-17GZ-120T-150-T6-3975 (Cycle 21) 10 GE14-P1OCNAB407-13GZ-120T-150-T6-3172 (Cycle 20)

Figure 2. Previous Cycle Core Loading Diagram Figure 2. Previous Cycle Core Loading Diagram 10

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[1 1]

Figure 3. Figure 4.1 from NEDC-32601P-A Figure 3. Figure 4.1 from NEDC-32601P-A 11

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[1 1]

Figure 4. Figure 111.5-1 from NEDC-32601P-A Figure 4. Figure 111.5-1 from NEDC-32601P-A 12

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))

Figure 5. Relationship Between MIP and CPR Margin Figure 5. Relationship Between MIP and CPR Margin 13

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Table 1. Description of Core Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case Number of Bundles in the 764 764 Core Limiting Cycle Exposure Point (i.e., Beginning of Cycle (BOC)/Middle of EOC EOC EOC EOC Cycle (MOC)/End of Cycle (EOC))

Cycle Exposure at Limiting Point 13,000 13,000 13,000 13,000 (MWd/STU)

% Rated Core Flow 88 100 80.7 100 Reload Fuel Type GE14 GNF2 Latest Reload Batch 31.41 32.46 Fraction, %

Latest Reload Average Batch Weight % 4.07 3.93 Enrichment Core Fuel Fraction:

ATRIUM1O 0.04 0.00 GE14 0.96 0.68 GNF2 0.00 0.32 Core Average Weight % 4.08 4.03 Enrichment Table 1. Description of Core 14

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Table 2. SLMCPR Calculation Methodologies Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case Non-Power Distribution NEDC-32601P-A NEDC-32601P-A Uncertainty Power Distribution NEDC-32601P-A NEDC-32601P-A Methodology Power Distribution NEDC-32694P-A NEDC-32694P-A Uncertainty Core Monitoring System 3DMONICORE 3DMONICORE R-Factor Calculation NEDC-32505P-A NEDC-32505P-A Methodology Table 2. SLMCPR Calculation Methodologies 15

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Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case

((

Table 3. Monte Carlo Calculated SLMCPR vs. Estimate 16

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Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Flow Core Flow Limiting Minimum Core Flow Core Flow Limiting Limiting Case Case Limiting Case Case

))

Requested Change to the Technical Specification N/A 1.10 (TLO)/ 1.13 (SLO)

SLMCPR I]

Table 3. Monte Carlo Calculated SLMCPR vs. Estimate 17

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Table 4. Non-Power Distribution Uncertainties Nominal (NRC- Previous Cycle Previous Cycle Current Cycle Current Cycle Approved) Value Minimum Core Rated Core Flow Minimum Core Rated Core Flow a (%)

g Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case GETAB Feedwater Measur Flow 1.76 N/A N/A N/A Measurement N/A Feedwater Temperature 0.76 N/A N/A N/A N/A Measurement Reactor Pressure 0.50 N/A N/A N/A N/A Measurement Core Inlet Temperature 0.20 N/A N/A N/A N/A Measurement Total Core Flow 6.0 SLO/2.50 TLO N/A N/A N/A N/A Measurement Channel Flow Area 3.0 N/A N/A N/A N/A Variation Friction Factor 10.0 N/A N/A N/A N/A Multiplier Channel Friction FactorMutipi 5.0 N/A N/A N/A Factor MultiplierI N/A Table 4. Non-Power Distribution Uncertainties 18

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Table 4. Non-Power Distribution Uncertainties Nominal (NRC- Previous Cycle Previous Cycle Current Cycle Current Cycle Approved) Value Minimum Core Rated Core Flow Minimum Core Rated Core Flow

+/- a (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case NEDC-32601P-A Feedwater FlowR Measurement Feedwater Temperature )) [H] ] [ ]

Measurement Reactor Pressure [R Measurement ((_]_[_]_(( ))_[_]_[_]

Core Inlet Temperature 0.2 0.2 0.2 0.2 0.2 Measurement Total Core Flow 6.0 SLO/2.50 TLO 6.0 SLO/2.84 TLO 6.0 SLO/2.50 TLO 6.0 SLO/3.10 TLO 6.0 SLO/2.50 TLO Measurement Channel Flow Area Variation ((_ )) ((_))_[_))_((_]_((_]

Friction Factor Multiplier )) R Channel Friction FactorMutipi 5.0 5.0 5.0 5.0 5.0 Factor Multiplier Table 4. Non-Power Distribution Uncertainties 19

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Table 5. Power Distribution Uncertainties Nominal (NRC- Previous Cycle Previous Cycle Current Cycle Current Cycle Description Approved) Value Minimum Core Rated Core Flow Minimum Core Rated Core Flow

+/-: c (%) jFlow Limiting Case Limiting Case Flow Limiting Case Limiting Case GETAB/NEDC-32601P-A GEXL R-Factor H )) N/A N/A N/A N/A Random Effective 2.85 SLO/1.2 TLO N/A N/A N/A N/A TIP Reading Systematic Effective 8.6 N/A N/A N/A N/A TIP Reading NEDC-32694P-A, 3DMONICORE GEXL R-Factor [ ] [ ] [

R] ] [

H] [

Random Effective 2.85 SLO/l.20 2.85 SLO/ 1.36 TLO 2.85 SLO/1.20 TLO 2.85 SLO/ 1.49 TLO 2.85 SLO/1.20 TLO TIP Reading TLO TIP Integral] (())[1] [] []

Four Bundle Power Distribution SurroundingTIPP )) [] []

Location Contribution to Bundle Power Uncertainty Due to Local Power Range )) [ ]

Monitor (LPRM)

Update Table 5. Power Distribution Uncertainties 20

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Table 5. Power Distribution Uncertainties Nominal (NRC- Previous Cycle Previous Cycle Current Cycle Current Cycle Description Approved) Value Minimum Core Rated Core Flow Minimum Core Rated Core Flow g (%)

G Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case Contribution to Bundle Power Due to [] (( ]

Failed TIP Contribution to Bundle Power Due to [] [ ] [ ]

Failed LPRM Total Uncertainty in Calculated Bundle Power Uncertainty of TIP Signal Nodal [ ] [ ] R] )) 1]

Uncertainty I Table 5. Power Distribution Uncertainties 21

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Table 6. Critical Power Uncertainties Previous Cycle Current Cycle Current Cycle Previous Cycle Core Rated CoreCase Flow Description a Value Minimum Flow LimitingCore Case Rated Limiting Flow CoreCase Minimum Flow Limiting Case Limiting R]

Table 6. Critical Power Uncertainties 22