ML11306A064

Gnf S-0000-0136-7814 R0-NP, Rev. 0, Gnf Additional Information Regarding Requested Changes to the Technical Specification SLMCPR, Grand Gulf Cycle 19, Extended Power Uprate.

ML11306A064
Person / Time
Site:	Grand Gulf
Issue date:	08/31/2011
From:	Global Nuclear Fuel
To:	Office of Nuclear Reactor Regulation
References
GNRO-2011/00064, eDRF Section 0000-0136-7814 R 2 GNF S-0000-0136-7814 R0-NP, Rev. 0
Download: ML11306A064 (27)

Text

Attachment 4 GNRO-2011/00064 GNF-A Analysis Summary (Non-Proprietary)

This is a non-proprietary version of Attachment 1 from which the proprietary information has been removed. The proprietary portions that have been removed are indicated by double square brackets as shown here: (( I].

Global Nuclear Fuel Global Nuclear Fuel A Joint Venture of GEToshiba, & Hitachi GNF S-0000-0136-7814 RO-NP Revision 0 eDRF Section 0000-0136-7814 R2 August 2011 Non-ProprietaryInformation- Class I (Public)

GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Grand Gulf Cycle 19 Extended Power Uprate Copyright 2011 GlobalNuclear Fuel - Americas, LLC All Rights Reserved

GNF S-0000-0136-7814 RO-NP Non-Proprietary Information - Class I (Public)

Information Notice This is a non-proprietary version of the document GNF S-0000-0136-7814 RO-P, Revision 0, 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 (( 1].

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 Entergy in proceedings before the U.S. 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 that 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.

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GNF S-0000-0136-7814 RO-NP Non-Proprietary Information - Class I (Public)

Table of Contents 1.0 M ETH ODO LO GY .......................................................................................................................................... 1 2.0 DISCUSSIO N ................................................................................................................................................... 1 2.1. M AJOR CONTRIBUTORS TO SLM CPR CHANGE .............................................................................................. 2 2.2. D EVIATIONS INNRC-APPROVED UNCERTAINTIES ..................................................................................... 2 2 .2 .1. R -F acto r ................................................................................................................................................. 2 2.2.2. Core Flow Rate andRandom Effective TIP Reading....................................................................... 3 2.3. D EPARTURE FROM NRC-APPROVED M ETHODOLOGY ................................................................................ 4 2.4. FUEL AXIAL POWER SHAPE PENALTY ..................................................................................................... 4 2.5. M ETHODOLOGY RESTRICTIONS ...................................................................................................................... 5 2.6. M INIMUM CORE FLOW CONDITION ................................................................................................................ 5 2.7. LIMITING CONTROL ROD PATTERNS ...................................................................................................... 6 2.8. CORE MONITORING SYSTEM .......................................................................................................................... 6 2.9. POWER/FLOW M AP ......................................................................................................................................... 6 2.10. CORE LOADING DIAGRAM .......................................................................................................................... 6 2.11. FIGURE RE FERENCES .................................................................................................................................. 6 2.12. ADDITIONAL SLM CPR LICENSING CONDITIONS .................................................................................... 6 2.13. GNF2 SPACER BENT FLOW W ING EFFECT ............................................................................................. 7 2 .14 . S UM M AR Y .................................................................................................................................................. 7

3.0 REFERENCES

................................................................................................................................................ 8 List of Figures FIGURE 1. CURRENT CYCLE CORE LOADING D IAGRAM ............................................................................................ 10 FIGURE 2. PREVIOUS CYCLE CORE LOADING DIAGRAM .............................................................................................. 11 FIGURE 3. FIGURE 4.1 FROM NEDC-32601P-A .......................................................................... ......... 12 FIGURE 4. FIGURE 111.5-1 FROM N EDC-32601P-A ............................................................................................. 13 FIGURE 5. RELATIONSHIP BETW EEN MIP AND CPR M ARGIN .................................................................................. 14 List of Tables TABLE 1. D ESCRIPTION OF CORE ................................................................................................................................. 15 TABLE 2. SLM CPR CALCULATION M ETHODOLOGIES ................................................................................................. 16 TABLE 3. M ONTE CARLO CALCULATED SLM CPR vs. ESTIMATE .......................................................................... 17 TABLE 4. N ON-POWER D ISTRIBUTION UNCERTAINTIES ............................................................................................ 19 TABLE 5. POW ER DISTRIBUTION UNCERTAINTIES ....................................................................................................... 21 TABLE 6. CRITICAL POW ER UNCERTAINTIES ............................................................................................................... 23 Table of Contents iii

GNF S-0000-0136-7814 RO-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 with NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel," Revision 18 (Reference 1), using the following 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 GEl 1, GEl2 and GEl3 Fuel,"

Revision 1, July 1999. (Reference 4)

NEDC-32505P-A is the generic R-Factor methodology report that describes the changed methodology that was adopted after part length rods were introduced. The NRC staff's Safety Evaluation (SE) for NEDC-32505P-A has a requirement that the applicability of the R-Factor methodology is confirmed when a new fuel type is introduced. The confirmation for GE14 is contained in "GEXL14 Correlation for GE14 Fuel, NEDC-32851P Revision 2, and GEXL1O Correlation for GE12 Fuel with Inconel Spacer, NEDC-32464P Revision 2," FLN-2001-018, September 25, 2001 (Reference 5) and in Reference 6. The confirmation for GNF2 is contained in "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 (Reference 7).

Table 2 identifies the actual methodologies used for the Grand Gulf Cycle 18 and the Cycle 19 SLMCPR calculations.

2.0 Discussion In this discussion, the TLO nomenclature is used for two recirculation loops in operation, and the SLO nomenclature is used for one recirculation loop in operation.

This information regarding requested changes to the Technical Specification SLMCPR is based on and is for the Grand Gulf Extended Power Uprate (EPU) license condition of 4,408 MWt in Cycle 19. The EPU condition represents a 13% increase in power relative to the 3,898 MWt licensed power of Cycle 18.

Also addressed is the application of the limitations from the SE for the Interim Methods Licensing Topical Report (IMLTR) (Reference 8) related to EPUs. Specifically, the following limitation is being addressed:

• For EPU operation, a 0.02 value shall be added to the cycle-specific SLMCPR value.

This adder is applicable to SLO, which is derived from the dual loop SLMCPR value.

Methodology 1

GNF S-0000-0136-7814 RO-NP Non-Proprietary Information - Class I (Public) 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. MIP (MCPR Importance Parameter) measures the core bundle-by-bundle MCPR distribution and RIP (R-Factor Importance Parameter) 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 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 (( )) and the inherent variation in the Monte Carlo results (( )), the change in the Grand Gulf Cycle 19 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.

2.2. Deviations in NRC-Approved Uncertainties Tables 4 and 5 provide a list of Nuclear Regulatory Commission (NRC)-approved uncertainties along with 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 ((

)) 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 Discussion 2

GNF S-0000-0136-7814 R0-NP Non-Proprietary Information - Class I (Public) 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 attachment, is affected by this deviation. Reference 9 technically justifies that a GEXL R-Factor uncertainty of (( )) accounts for a channel bow uncertainty of up to Grand Gulf has experienced control blade shadow corrosion-induced channel bow to the extent that an increase in the NRC-approved R-Factor uncertainty of (( )) is deemed prudent to address its effect. Accounting for the control blade shadow corrosion-induced channel bow, the Grand Gulf Cycle 19 analysis shows an expected channel bow uncertainty of (( 11, which is bounded by a GEXL R-Factor uncertainty of (( )). Thus the use of a GEXL R-Factor uncertainty of (( )) adequately accounts for the expected control blade shadow corrosion-induced channel bow for Grand Gulf Cycle 19.

2.2.2. Core Flow Rate and Random Effective TIP Reading In Reference 10 GNF committed to the expansion of the state points used in the determination of the SLMCPR. Consistent with the Reference 10 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 92.8% 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 92.8/100. The steps "a5 CORE FLOW" and "a TIP (INSTRUMENT)" in Figure 4.1 from NEDC-32601P-A (Reference 2), which has been provided for convenience in Figure 3 of this attachment, 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.

Discussion 3

GNF S-0000-0136-7814 RO-NP Non-Proprietary Information - Class I (Public)

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 Grand Gulf Cycle 19 SLMCPR calculations.

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 11, 12, 13 and 14). 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:

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11 Discussion 4

GNF S-0000-0136-7814 RO-NP Non-Proprietary Information - Class I (Public)

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 to the NRC-approved methodology contained in NEDE-240 11-P-A (Reference 1) along with the actual values 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 Grand Gulf Cycle 19 SLMCPR values.

2.5. Methodology Restrictions The four restrictions identified on page 3 of NRC's SE relating to the General Electric Licensing Topical Reports NEDC-32601P (Reference 2), NEDC-32694P (Reference 3), and Amendment 25 to NEDE-2401 1-P-A (Reference 15) are addressed in References 6, 11, 16, and 17.

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, Revision 0 (Reference 7). Specifically, in the NRC audit report (Reference 18) for the said document, Section 3.4.1, page 59 states:

"The NRC staffs 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 the 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 lOx 10 array and 2 water rod makeup, as stated by the NRC audit report (Reference 18), 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 Grand Gulf Cycle 19; 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 Grand Gulf Cycle 19, the minimum core flow SLMCPR calculation performed at 92.8% 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 search spaces for the limiting rod pattern and the Discussion 5

GNF S-0000-0136-7814 R0-NP Non-Proprietary Information - Class I (Public) nominal rod pattern are essentially the same. Additionally, the condition that MIP ((

)) establishes a reasonably bounding limiting rod pattern. Hence, the rod pattern used to calculate the SLMCPR at 100% rated power / 92.8% 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 during the operation of Grand Gulf Cycle 19. Consequently, the SLMCPR value calculated from the 92.8%

core flow and rated core power condition limiting MCPR distribution reasonably bounds this mode of operation for Grand Gulf Cycle 19.

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 anticipated operational occurrences during the operation of Grand Gulf Cycle 19.

2.8. Core Monitoring System For Grand Gulf Cycle 19, the 3D Monicore 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 attachment.

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-2401 1-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 GEl4 and GNF2 data.

2.12. Additional SLMCPR Licensing Conditions Grand Gulf's safety analysis report for constant pressure power uprate (PUSAR) (Reference 19) includes Limitation and Condition 9.4 of the IMLTR (Reference 8) to include a 0.02 adder to the calculated cycle-specific SLMCPR value for both the SLO and TLO SLMCPR.

For Grand Gulf Cycle 19, the additional SLMCPR licensing condition that the SLMCPR shall be established by adding 0.02 to the cycle-specific SLMCPR value calculated using the NRC-approved methodologies documented in NEDE-2401 1-P-A (Reference 1) has been applied (see Table 3).

Discussion 6

GNF S-0000-0136-7814 RO-NP Non-Proprietary Information - Class I (Public) 2.13. GNF2 Spacer Bent Flow Wing Effect A manufacturing defect was discovered in the spacer flow wings of the fresh GNF2 fuel loaded in Grand Gulf Cycle 18. The condition is characterized as the spacer flow wing associated with a comer location being bent downward. This condition is described further in Attachment 2 of GNF Enclosure 3 of Reference 20, Attachment 1. The manufacturing process leading to this condition has been corrected such that the Grand Gulf Cycle 19 GNF2 bundles are not affected by this defect. However, as the Cycle 18 GNF2 fuel continues to reside in Cycle 19, the effect of this defect on the SLMCPR has been assessed.

The method used for evaluation of the effect on the defect is the same as that reviewed in an audit by the NRC on August 20, 2010 associated with the FitzPatrick Cycle 20 SLMCPR Technical Specification change submittal. The NRC acknowledged this audit and consideration of the GNF2 bent spacer wing in their FitzPatrick SLMCPR Technical Specification change SE (Reference 21). In approving the FitzPatrick SLMCPR change, the NRC accepted this evaluation method for assessing the effect of the GNF2 bent spacer wing.

The statistically based MCPR evaluation, including the GNF2 spacer bent flow wings, for Grand Gulf Cycle 19, shows that the effect is less than a (( )) relative to the calculated Monte Carlo SLMCPR that is shown in Table 3. Thus the effect would result in an adjusted Table 3 limiting Cycle 19 TLO SLMCPR of (( )). Similarly, the adjusted Table 3 limiting Cycle 19 SLO SLMCPR would be (( )) for this effect.

2.14. Summary The requested changes to the Technical Specification SLMCPR values are 1.11 for TLO and 1.14 for SLO for Grand Gulf Cycle 19.

Discussion 7

GNF S-0000-0136-7814 RO-NP Non-Proprietary Information - Class I (Public) 3.0 References

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

NEDE-2401 1-P-A, Revision 18, April 2011.

2. GE Nuclear Energy, "Methodology and Uncertainties for Safety Limit MCPR Evaluations," NEDC-32601 P-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, GEl2 and GEl3 Fuel,"

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

5. Letter, Glen A. Watford (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to J. Donoghue (NRC), "GEXL14 Correlation for GE14 Fuel, NEDC-32851P Revision 2, and GEXL10 Correlation for GE12 Fuel with Inconel Spacer, NEDC-32464P Revision 2," FLN-2001-018, September 25, 2001.

6. Letter, Glen A. Watford (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to J. Donoghue (NRC), "Confirmation of the Applicability of the GEXL14 Correlation and Associated R-Factor Methodology for Calculating SLMCPR Values in Cores Containing GEl4 Fuel," FLN-2001-017, October 1, 2001.

7. Letter, Andrew A. Lingenfelter (GNF) to U.S. Nuclear Regulatory Commission Document Control Desk, "GNF2 Advantage Generic Compliance with NEDE-2401 1-P-A (GESTAR II), NEDC-33270P, March 2007, and GEXL 17 Correlation for GNF2 Fuel, NEDC-33292P, March 2007," FLN-2007-01 1, March 14, 2007.

8. GE Hitachi Nuclear Energy, "Applicability of GE Methods to Expanded Operating Domains," NEDC-33173P-A, Revision 1, September 2010.

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

10. Letter, Jason S. Post (GENE) to U.S. Nuclear Regulatory Commission 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.

11. Letter, Glen A. Watford (GNF-A) to U.S. Nuclear Regulatory Commission 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.

12. Letter, Glen A. Watford (GNF-A) to U.S. Nuclear Regulatory Commission 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.

References 8

GNF S-0000-0136-7814 RO-NP Non-Proprietary Information - Class I (Public)

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

14. Letter, Andrew A. Lingenfelter (GNF-A) to U.S. Nuclear Regulatory Commission 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.

15. Letter from Frank Akstulewicz (NRC) to Glen A. Watford (GE), "Acceptance For Referencing of Licensing Topical Reports NEDC-32601P, Methodology And Uncertainties For Safety Limit MCPR Evaluations; NEDC-32694P, Power Distribution Uncertainties For Safety Limit MCPR Evaluation; and Amendment 25 to NEDE-2401 1-P-A On Cycle-Specific Safety Limit MCPR (TAC NOS. M97490, M99069 and M9749 1)," MFN-003-99, March 11, 1999.

16. Letter, Glen A. Watford (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to R. Pulsifer (NRC), "Confirmation of 10xlO Fuel Design Applicability to Improved SLMCPR, Power Distribution and R-Factor Methodologies,"

FLN-2001-016, September 24, 2001.

17. Letter, Andrew A. Lingenfelter (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with cc to SS Philpott (NRC), "Amendment 33 to NEDE-2401 1-P, General Electric Standard Application for Reactor Fuel (GESTAR II) and GNF2 Advantage Generic Compliance with NEDE-2401 1-P-A (GESTAR II),

NEDC-33270P, Revision 3, March 2010," MFN 10-045, March 5, 2010.

18. 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)

19. GE Hitachi Nuclear Energy, "Safety Analysis Report for Grand Gulf Nuclear Station Constant Pressure Power Uprate," NEDC-33477P, Revision 0, August 2010.

20. Letter, Pete Deitrich (JAF) to U.S. Nuclear Regulatory Commission Document Control Desk, "Response to Follow-up Request for Additional Information Re: James A.

FitzPatrick Nuclear Power Plant Proposed Change to the James A. FitzPatrick Nuclear Power Plant's Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio (TAC No. ME3786)," JAFP-10-0122, September 2, 2010.

21. Letter, Bhalchandra K. Vaidya (NRC) to James A. FitzPatrick Nuclear Power Plant, "James A. FitzPatrick Nuclear Power Plant - Issuance of Amendment RE: Changes to the Safety Limit Minimum Critical Power Ratio (TAC NO. ME3786)," September 27, 2010.

References 9

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Figure 1. Current Cycle Core Loading Diagram 64 16 16 62 17 17 16 17 17 4 4 17 16 17 17 15 60 16 17 4 1 1 7 19 19 7 1 1 4 17 16 16 17 17 16 4 7 19 7 7 2 2 7 7 19 7 4 17 17 17 17 17 4 1 7 7 7 19 1 9 19 19 9 1 19 7 7 7 1 4 16 16 17 17 1 18 19 4 9 5 20 9 5 5 9 20 5 9 4 19 18 1 17 17 15 16 1 19 19 4 9 5 20 4 20 6 6 20 4 20 5 9 4. 19 19 1 4 17 17 18 19 1 19 2 20 2 20 2 2 2 2 20 2 20 2 19 1 19 18 1 17 16 17 19 4 19 2 18 2 20 2 6 6 6 6 2 20 2 18 2 19 4 19 7 17 16 15 17 4 4 9 2 18 5 6 2 6 2 3 3 2 6 2 6 5 18 2 9 4 7 4 17 17 17 4 7 9 5 20 2 6 3 6 5 6 6 6 6 5 6 3 6 2 20 5 9 7 7 4 17 17 1 19 5 20 2 20 2 6 5 6 3 3 3 3 6 5 6 2 20 2 20 5 19 19 1 17 17 1 7 20 2 20 2 6 5 6 5 6 8 8 6 5 6 5 6 2 20 2 20 1 7 1 16 17 7 7 9 20 2 6 2 6 3 6 5 3 3 5 6 3 6 2 6 2 20 9 9 7 7 17 16 17 7 7 9 2 20 2 6 5 6 3 8 8 8 8 3 6 5 6 2 20 2 9 1 7 7 17 16 15 4 19 2 5 6 2 6 3 6 3 8 5 2 2 5 8 3 6 3 6 2 6 5 19 2 19 4 16 16 4 19 2 5 6 2 6 3 6 3 8 5 2 2 5 8 3 6 3 6 2 6 5 19 2 19 4 16 16 17 7 7 9 2 20 2 6 5 6 3 8 8 8 8 3 6 5 6 2 20 2 9 1 7 7 17 16 17 7 7 9 20 2 6 2 6 3 6 5 3 3 5 6 3 6 2 6 2 20 9 9 7 7 16 16 1 7 20 2 20 2 6 5 6 5 6 8 8 6 5 6 5 6 2 20 2 20 1 7 1 16 17 1 19 5 20 2 20 2 6 5 6 3 3 3 3 6 5 6 2 20 2 20 5 19 19 1 17 17 4 7 9 5 20 2 6 3 6 5 6 6 6 6 5 6 3 6 2 20 5 9 7 7 4 17 17 17 4 4 9 2 18 5 6 2 6 2 3 3 2 6 2 6 5 18 2 9 4 7 4 15 17 16 17 19 4 19 2 18 2 20 2 6 6 6 6 2 20 2 18 2 19 4 19 7 17 16 17 18 19 1 19 2 20 2 20 2 2 2 2 20 2 20 2 19 1 19 18 1 17 17 1 19 19 4 9 5 20 4 20 6 6 20 4 20 5 9 4 19 19 1 4 17 17 17 1 18 19 4 9 5 20 9 5 5 9 20 5 9 4 19 18 1 17 17 17 17 4 1 7 7 7 19 1 9 19 19 9 1 19 7 7 7 1 4 17 16 16 17 17 17 4 7 19 7 7 2 2 7 7 19 7 4 17 17 17 15 15 15 4 1 1 7 19 19 7 1 1 4 17 16 16 17 17 16 17 4 4 17 17 17 17 16 16 16 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 61 63 Fuel Type l=GNF2-P1 0SG2B42 1-10G8.0-120T2-150-T6-3265 (Cycle 18) 9=GNF2-P1OSG2B416-16GZ-120T2-150-T6-4026 (Cycle 19) 2-GNF2-PIOSG2B401-15GZ-120T2-150-T6-3266 (Cycle 18) 15=GE14-P 1OSNAB396-18GZ-120T- 150-T6-3091 (Cycle 17) 3=GNF2-P 1OSG2B400-19GZ- 120T2-150-T6-3267 (Cycle 18) 16=GE14-P1OSNAB391-18GZ-120T-150-T6-3092 (Cycle 17) 4=GNF2-PI 0SG2B435-14GZ-120T2-150-T6-3269 (Cycle 18) 17=GE14-P 1OSNAB395-18GZ-120T- 150-T6-3093 (Cycle 17) 5=GNF2-PI OSG2B400-19GZ-120T2-150-T6-3270 (Cycle 18) 18=GNF2-PI0SG2B397-14GZ-120T2-150-T6-4027 (Cycle 19) 6-GNF2-P10SG2B387-14GZ-120T2-150-T6-4023 (Cycle 19) 19-GNF2-P1OSG2B409-14GZ- 120T2-150-T6-4028 (Cycle 19) 7=GNF2-P10SG2B424-14GZ-1 20T2-150-T6-4024 (Cycle 19) 20=GNF2-P10SG2B397-15GZ- 120T2-150-T6-4029 (Cycle 19) 8=GNF2-P10SG2B385-14GZ-120T2-150-T6-4025 (Cycle 19)

Figure 1. Current Cycle Core Loading Diagram 10

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Figure 2. Previous Cycle Core Loading Diagram 64 ElF2 E E 62 [GHH [ ((] []EH ]

60 E [EEI1E 58 AD []D[GD ] DE[] GE GE 56 44 ElE KB 2 JE ElJE E E 48 **[1 46 [*))(([*]*[*]*]

40 1*L**GGAJJB *hP 22 *]* [* ((*]*

14 *]*] [* [*]

12 MP PRE 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 61 63 Fuel Type A=GNF2-P I G2B42 1-10G8.0-1 20T2- 50-T6-3265 (Cycle 18) G=ATRM 10-P OSAEB404-1 5GZ-I 4T-9WR- 149-T6-3050 (Cycle 16)

B=GNF2-P I G240 1- 5GZ-1 20T2- 50-T6-3266 I (Cycle 18) H=ATRM1-P0SAEB405-15GZ-114T-9WR-E49-T6-3051 (Cycle 16)

C=GNF2-P 10SG2400-9GZ-120T2-150-T6-3267 N50-T6-309 (Cycle 18) IGEI4-P10SNAB396-S8GZ-1 20T- I (Cycle 17)

D=GNF2-PI0SG2B435-14GZ-1 20T2-150-T6-3269 (Cycle 18) J=GEl4-P 1SNAB391-8GZ-120T-150-T6-3092 (Cycle 17)

E=GNF2-P 10SG2B400-1I9GZ- 120T2- 150-T6-3270 (Cycle 18) K=GE 14-Pl0SNAB395-1 8GZ-1I20T-1I50-T6-3093 (Cycle 17)

F=ATRM 10-P 10 SAEB4O4-1 5GZ-1 14T-9WR- 49-T6-3048 (Cycle M 15)

Figure 2. Previous Cycle Core Loading Diagram I1I

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

((l Figure 3. Figure 4.1 from NEDC-32601P-A 12

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

((E Figure 4. Figure 111.5-1 from NEDC-32601P-A 13

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Figure 5. Relationship Between MIP and CPR Margin Figure 5. Relationship Between MIP and CPR Margin 14

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Table 1. Description of Core Previous Cycle Previous Cycle Rated Current Cycle Current Cycle Rated Description Minimum Core Core Flow Limiting Minimum Core Flow Core Flow Limiting Flow Limiting Case Case Limiting Case Case Number of Bundles in the 800 800 Core Limiting Cycle Exposure EOC EOC EOC EOC Point (i.e., BOC/MOC/EOC)

Cycle Exposure at Limiting 13840 13840 15700 15700 Point (MWd!STU)

% Rated Core Flow 77.1 100.0 92.8 100.0 Reload Fuel Type GNF2 GNF2 Latest Reload Batch 38.5 45.5 Fraction, %

Latest Reload Average Batch 4.10 4.03 Weight % Enrichment Core Fuel Fraction:

GNF2 0.385 0.840 GE14 0.310 0.160 ATRIUM-10 0.305 0.0 Core Average Weight % 4.03 4.04 Enrichment Table 1. Description of Core 15

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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-32601 -P-A NEDC-32601 -P-A Uncertainty Power Distribution NEDC-32694P-A NEDC-32694P-A Methodology Power Distribution NEDC-32694P-A NEDC-32694P-A Uncertainty Core Monitoring System 3D MONICORE 3D MONICORE R-Factor Calculation NEDC-32505P-A NEDC-32505P-A Methodology Table 2. SLMCPR Calculation Methodologies 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

((

i i +

t t + F Table 3. Monte Carlo Calculated SLMCPR vs. Estimate 17

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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 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 ar (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case GETAB Feedwater Flow 1.76 N/A N/A N/A N/A Measurement Feedwater Temperature 0.76 N/A N/A N/A N/A Measurement Reactor Mea Pressure sure 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 Measurementw6.0 SLO/2.5 TLO N/A N/A N/A Measurement N/A 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 N/A Factor Multiplier Table 4. Non-Power Distribution Uncertainties 19

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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 F'low Limiting Case Limiting Case NEDC-32601P-A Feedwater Flow Measurement Feedwater Temperature (( Er )) Er )) Er )) Er ))

Measurement Reactor Pressure Measurement Core Inlet Temperature 0.2 0.2 0.2 0.2 0.2 Measurement Total Core Flow Measurementw6.0 SLO/2.5 TLO 6.0 SLO/3.24 TLO 6.0 SLO/2.5 TLO 6.0 SLO/2.69 TLO 6.0 SLO/2.5 TLO Measurement Channel Flow Area Variation Friction Factor Multiplier Channel Friction FactorMutipi 5.0 5.0 5.0 5.0 5.0 Factor Multiplier Table 4. Non-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

• (%)

a Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case GETAB/NEDC-32601P-A GEXL R-Factor (( )) 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 I I I NEDC-32694P-A, 3DMONICORE GEXL R-Factor (( )) Er )) Er 1] Er )) Er ))

Random Effective 2.85 SLO/1.2 TLO 2.85 SLO/1.56 TLO 2.85 SLO/1.2 TLO 2.85 SLO/1.29 TLO 2.85 SLO/1.2 TLO TIP Reading TIP Integral (( Er )) Er ][ )) Er Four Bundle Power Distribution Surrounding TIP Location Contribution to Bundle Power Uncertainty Due to LPRM Update Table 5. Power Distribution Uncertainties 21

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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

+/- o (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case Contribution to Bundle Power Due to R[ Er(( ]

Failed TIP Contribution to Bundle Power Due to (( )) Er )) Er )) Er )) Er ))

Failed LPRM Total Uncertainty in Calculated Bundle (( Er Er Er ))

Power Uncertainty of TIP Signal Nodal E[ )) r[ )) Er )) Er )) Er ))

Uncertainty Table 5. Power Distribution Uncertainties 22

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Table 6. Critical Power Uncertainties Nominal Value Previous Cycle Previous Cycle Current Cycle Current Cycle Description Minimum Core Rated Core Flow Minimum Core Rated Core Flow Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case

((

Table 6. Critical Power Uncertainties 23