ML15120A290

License Amendment Request - Safety Limit Minimum Critical Power Ratio Change

ML15120A290
Person / Time
Site:	Peach Bottom
Issue date:	04/30/2015
From:	Jim Barstow Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15120A288	List: ML15120A290
References
Download: ML15120A290 (47)

Text

O O O) 1 h

wlo

SLs 2.0

2.0 SAFETY

LIMITS (SLs)

2.1 SLs

2.1.1 Reactor

Core SLs

2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

THERMAL POWER shall be 25% RTP.

2.1.1.2 With the reactor steam dome pressure 785 psig and core flow 10% rated core flow:

MCPR shall be 1.09 for two recirculation loop operation or 1.12 for single recirculation loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor

Coolant System Pressure SL

Reactor steam dome pressure shall be 1325 psig.

2.2 SL Violations

With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.1 Restore

compliance with all SLs; and

2.2.2 Insert

all insertable control rods.

(continued)

PBAPS UNIT 3 2.0-1 Amendment No. 284

SLs 2.0

2.0 SAFETY

LIMITS (SLs)

2.1 SLs

2.1.1 Reactor

Core SLs

2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

THERMAL POWER shall be 25% RTP.

2.1.1.2 With the reactor steam dome pressure 785 psig and core flow 10% rated core flow:

MCPR shall be 1.15 for two recirculation loop operation or 1.15 for single recirculation loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor

Coolant System Pressure SL

Reactor steam dome pressure shall be 1325 psig.

2.2 SL Violations

With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.1 Restore

compliance with all SLs; and

2.2.2 Insert

all insertable control rods.

(continued)

PBAPS UNIT 3 2.0-1 Amendment No.

284

Non-Proprietary Information - Class I (Public) Peach Bottom Unit 3 Cycle 21 Page 1 of 27 002N5030 R1-NP Revision 0 Copyright 2015 Global Nuclear Fuel - Americas, LLC All Rights Reserved

Non-Proprietary Information - Class I (Public) Proprietary Information Notice Page 2 of 27 This is a non-proprietary version of the document 002N5030 R1-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 [[ ]].

The design, engineering, and other information contained in this document is furnished for the purpose of providing information regarding the requested changes to the Technical Specification SLMCPR for Exelon Peach Bottom Unit 3. The only undertakings of GNF-A with respect to information in this document are contained in contracts between GNF-A and Exelon, and nothing contained in this document shall be construed as changing th at contract. The use of this information by anyone other than Exelon, or for a ny purposes other than t hose for which it is intended is not authorized; a nd 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.

Non-Proprietary Information - Class I (Public) Table of Contents Page 3 of 27 M AJOR CONTRIBUTORS TO SLMCPR CHANGE .............................................................................................. 4DEVIATIONS IN NRC-A PPROVED UNCERTAINTIES ......................................................................................... 52.2.1.R-Factor ......................................................................................................................

........................... 52.2.2.Core Flow Rate and Random Effective TIP Reading ............................................................................. 62.2.3.LPRM Update Interval and Calculated Bundle Power .......................................................................... 6DEPARTURE FROM NRC-APPROVED METHODOLOGY .................................................................................... 7F UEL AXIAL P OWER SHAPE PENALTY ............................................................................................................ 7METHODOLOGY RESTRICTIONS ...................................................................................................................... 8MINIMUM CORE FLOW CONDITION ................................................................................................................ 8LIMITING CONTROL R OD PATTERNS .............................................................................................................. 9C ORE MONITORING SYSTEM .......................................................................................................................... 9P OWER/FLOW M AP ..............................................................................................................................

........... 9C ORE LOADING DIAGRAM .......................................................................................................................... 9F IGURE REFERENCES ..............................................................................................................................

.... 9ADDITIONAL SLMCPR LICENSING CONDITIONS ........................................................................................ 910 CFR 21 EVALUATION ............................................................................................................................ 9

SUMMARY

..............................................................................................................................

.................. 10F IGURE 1. CURRENT CYCLE C ORE LOADING D IAGRAM ............................................................................................... 12F IGURE 2. PREVIOUS CYCLE C ORE LOADING DIAGRAM .............................................................................................. 13F IGURE 3. FIGURE 4.1 FROM NEDC-32601P-A ........................................................................................................... 14F IGURE 4. FIGURE III.5-1 FROM NEDC-32601P-A ...................................................................................................... 15F IGURE 5. RELATIONSHIP BETWEEN MIP AND CPR MARGIN ...................................................................................... 16 T ABLE 1. DESCRIPTION OF C ORE ..............................................................................................................................

... 17T ABLE 2. SLMCPR CALCULATION METHODOLOGIES ................................................................................................. 18T ABLE 3. MONTE CARLO CALCULATED SLMCPR VS. ESTIMATE ............................................................................... 19T ABLE 4. N ON-P OWER DISTRIBUTION UNCERTAINTIES ............................................................................................... 21T ABLE 5. POWER DISTRIBUTION UNCERTAINTIES ....................................................................................................... 24T ABLE 6. C RITICAL POWER UNCERTAINTIES ............................................................................................................... 27 Non-Proprietary Information - Class I (Public) Methodology Page 4 of 27 Global Nuclear Fuel (GNF) performs Safety Limit Minimum Critical Power Ratio (SLMCPR) calculations in accordance with NEDE-24011-P-A "General Electric Standard Application for Reactor Fuel" (Revision 20) using the following Nuclear Regulatory Commission (NRC)-

approved methodologies and uncertainties: NEDC-32601P-A "Methodology and Uncertainties for Safety Limit MCPR Evaluations,"

August 1999. NEDC-32694P-A "Power Distribution Uncertainties for Safety Limit MCPR Evaluations," August 1999. NEDC-32505P-A "R-Factor Calculation Method for GE11, GE12 and GE13 Fuel,"

Revision 1, July 1999.

The latter reference is applicable to GNF's current fuel offeri ngs of GE14 and GNF2. Both are 10x10 lattice designs with two water rods, as for GE12. Table 2 identifies the methodologies used for the Peach Bottom Unit 3 Cycle 20 and the Cycle 21 SLMCPR calculations. 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.

The calculated Monte Carlo SLMCPR values for the prior cycle and the current cycle are presented in Table 3. 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 calcu lated SLMCPR. MCPR Importance Parameter (MIP) measures the core bundle-by-bundle MC PR distribution and R-Factor Importance Parameter (RIP) measur es the bundle pin-by-pin power/R-Factor distribution. The effect of the fuel loading pattern on the calculated TLO SLMCPR has been correlated to the parameter MIPRIP, which combines the MIP and RIP values.

Another factor besides core MCPR distribution or bundle R-factor distribution that significantly affects the SLMCPR is the expansion of the analysis domain that comes with the initial application of Maximum Extended Load Line Limit Analysis Plus (MELLLA+). The rated power/minimum core flow point is analyzed at a lower core flow (than without MELLLA+)

Non-Proprietary Information - Class I (Public) Discussion Page 5 of 27 using increased uncertainties (see Section 2.2.2) that tend to incr ease the SLMCPR. Also, a new point at off-rated power/off-rated flow is analyzed using the increased uncertainties. It is expected that in most cases this off-rated power/off-rated flow point will set the overall limit. Table 3 presents the MIP and RIP parameters for the previous cycle and the current cycle along with the TLO SLMCPR estimates using MIPRIP correlations. The MIPRIP prediction is correlated to Monte Carlo results for rated power/rated flow. Predictions for the MELLLA+ domains (at rated power/minimum core flow and off-rated power/off-rated core flow) must be adjusted by an amount estimated to account for the effect of the larger (SLO) uncertainties. 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 SLMCPR.

Given the bias and uncertainty in the MIPRIP correlation [[

]] and the inherent variation in the Monte Carlo results [[

]], the change in the Peach Bottom Unit 3 Cycle 21 calculated Monte Carlo TLO SLMCPR 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. Tables 4 and 5 provide a list of NRC-approved uncer tainties along with values actually used. A discussion of deviations from these NRC-approved values follows, all of which are conservative relative to NRC-approved values. Also, the estimated effect on the SLMCPR is provided in Table 3 for each deviation. 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 corro sion-induced channel bow, which is not accounted for in the channel bow uncertainty component of the a pproved R-Factor uncertainty. The step " RPEAK" in Figure 4.1 from NEDC-32601P-A, which has b een provided for convenience in Figure 3, is affected by this deviation. Reference 4 technically justifies that a GEXL R-Factor uncertainty of

[[ ]] accounts for a channel bow uncertainty of up to [[

]]. Peach Bottom Unit 3 has experienced control blade shadow corrosion-induced channel bow to the extent that an increase in th e NRC-approved R-Fact or uncertainty [[ ]] is deemed prudent to address its effect. Accounting for the control blade shadow co rrosion-induced Non-Proprietary Information - Class I (Public) Discussion Page 6 of 27 channel bow, the Peach Bottom Unit 3 Cycle 21 analysis shows an expected channel bow uncertainty of [[ ]], 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 Peach Bottom Unit 3 Cycle 21. In Reference 5, GNF committed to the expansion of the state points used in the determination of the SLMCPR. Consistent with the Reference 5 commitments, GNF performs analyses at the rated core power and minimum licensed core flow poi nt in addition to analyses at the rated core power and rated core flow point. The approved SLMCPR methodology is ap plied at each state point that is analyzed. For the TLO calculations performed in the MELLLA+ domain at rated power/minimum core flow and off-rated power/off-rated 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 using the SLO uncerta inty values of 6.0% and 2.85% for the core flow rate and random effective TIP reading respectively. The steps " CORE FLOW" and

" TIP (INSTRUMENT)" in Figure 4.1 from NE DC-32601P-A, which has been provided for convenience in Figure 3, are affected by this deviation, respectively. The treatment of the core flow and random effe ctive TIP reading uncerta inties is based on the assumption that the signal to noise ratio deteriorates as core flow is reduced. GNF believes this is conservative. To address the Local Power Range Monitor (LPRM) update/calibra tion interval in the Peach Bottom Unit 3 Technical Specifications, GNF has increased the LPRM update uncertainty in the SLMCPR analysis for Peach Bottom Unit 3 Cycle 21. The approved uncertainty values for the contribution to bundle power uncertainty due to LPRM update [[ ]], and the resulting total uncertainty in ca lculated bundle power [[

]] are conservatively increased, as shown in Table 5. The steps " TIP (INSTRUMENT)" and " BUNDLE (MODEL)" in Figure 4.1 from NEDC-32601P-A, which has been provided for convenience in Figure 3, are affected by this difference.

[[

]] The total bundle power Non-Proprietary Information - Class I (Public) Discussion Page 7 of 27 uncertainty is a function of the LPRM updat e uncertainty as detailed in Section 3.3 of NEDC-32694P-A.

No departures from NRC-approved methodologies were used in the Peach Bottom Unit 3 Cycle 21 SLMCPR calculations. At this time, GNF has determined that higher uncertainties and non-conser vative 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 3, 6, 7, and 8). The following table identifies, by marking with an "X", this potential for each GNF product line currently in use:

[[ ]] Axial bundle power shapes corresponding to the limiting SLMCPR control blade patterns are determined using the PANACEA three-dimensional (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 to the NRC-approved methodology contained in NEDE-24011-P-A along with the values actually used.

Non-Proprietary Information - Class I (Public) Discussion Page 8 of 27 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 Peach Bottom Unit 3 Cycle 21 SLMCPR values. The four restrictions identified on Page 3 of NRC's Safety Evaluation (SE) relating to the General Electric (GE) Licensing Topical Re ports (LTRs) NEDC-32601P, NEDC-32694P, and Amendment 25 to NEDE-24011-P-A (March 11, 1999) are addressed in References 1, 2, 3, and

9. The four restrictions for GNF2 were determined acceptable by the NRC review of "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," NEDC-33270P, Revision 0, FLN-2007-011, March 14, 2007. Specifically, in the NRC audit report ML081630579 for the said document, S ection 3.4.1 (page 59) states: "The NRC staff's SE of NE DC-32694P-A (Reference 19 of NEDC-33270P) provides four actions to follow whenever a new fuel design is introduced. Thes e four conditions are listed in Section 3.0 of the SE. The anal ysis 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 previ ously established 10x10 array and two water rod makeup, as stated by the NRC audit re port ML081630579, 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 Peach Bottom Unit 3 Cycle 21; therefore, the NEDC-32505P-A statement "-if new fuel is introduced, GENE must confirm that the revised R-Factor method is still valid based on new test dat a" is not applicable. For Peach Bottom Unit 3 Cycle 21, the most limiting SLMCPR calculation occurred at the 78.8% rated power/55.0% rated flow point. At low core flows, the search spaces for the limiting rod pattern and the 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 78.8% rated power/55.0% rated flow reasonably assures that at least 99.9% of the fuel rods in the core would not be expected to Non-Proprietary Information - Class I (Public) Discussion Page 9 of 27 experience boiling transition during normal operation or anticipated operational occurrences (AOOs) during the operation of Peach Bottom Unit 3 Cycle 21. Consequently, the SLMCPR value calculated from the 78.8% rated power/5 5.0% rated core flow condition limiting MCPR distribution reasonably bounds this mode of operation for Peach Bottom Unit 3 Cycle 21.

The limiting control rod patterns used to calculate the SLMCPR reasonably assure that at least 99.9% of the fuel rods in the core would not be expected to experience boiling transition during normal operation or AOOs during the operation of Peach Bottom Unit 3 Cycle 21. For Peach Bottom Unit 3 Cycle 21, the 3DMONICORE system will be used as the core monitoring system. The utility has provided the current and previous cycle power/flow map in a separate document.

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.

Table 1 provides a description of the core. Figure 3 is Figure 4.1 from NEDC-32601P-A. Figure 4 is Figure III.5-1 from NEDC-32601P-A. Figure 5 is based on Figure III.5-2 from NEDC -32601P-A, and has been updated with GE14 and GNF2 data.

For Peach Bottom Unit 3 Cycle 21, the additional SLMCPR licensing condition that the SLMCPR shall be established by adding 0.02 (Reference 10) to the cycle-specific SLMCPR value calculated using the NRC-approved methodologies documented in NEDE-24011-P-A has been applied (see Table 3).

There are no known 10 CFR 21 factors that affect the Peach Bottom Un it 3 Cycle 21 SLMCPR calculations.

Non-Proprietary Information - Class I (Public) Discussion Page 10 of 27 The requested changes to the Technical Spec ification SLMCPR valu es are 1.15 for TLO and 1.15 for SLO for Peach Bottom Unit 3 Cycle 21. These values bound the calculated results for Peach Bottom Unit 3 Cycle 21.

Non-Proprietary Information - Class I (Public) References Page 11 of 27 1.Letter, Glen A. Watford (GNF-A) to NRC Document Control Desk with attention to R. Pulsifer (NRC), "Confirmation of 10x10 Fuel Design Applicability to Improved

SLMCPR, Power Distribution and R-Factor Methodologies," FLN-2001-016, September 24, 2001.

2.Letter, Glen A. Watford (GNF-A) to NRC Document Control Desk with attention to Joseph E. Donoghue (NRC), "Confirmation of the App licability of the GEXL14 Correlation and Associated R-Factor Methodol ogy for Calculating SLMCPR Va lues in Cores Containing GE14 Fuel," FLN-2001-017, October 1, 2001.

3.Letter, Glen A. Watford (GNF-A) to 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.

4.Letter, John F. Schardt (GNF-A) to 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.

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

6.Letter, Glen A. Watford (GNF-A) to 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.

7.Letter, Jens G. Munthe Andersen (GNF-A) to NRC Document Control Desk with attention to Alan Wang (NRC), "GEXL Correlation for 10X10 Fuel," FLN-2003-005, May 31, 2003.

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

9.Letter, Andrew A. Lingenfelter (GNF-A) to NRC Document Control Desk with cc to Stephen S. 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.

10.GE Hitachi Nuclear Energy, "Applicability of GE Met hods to Expanded Operating Domains," NEDC-33173P-A, Revision 4, November 2012.

Non-Proprietary Information - Class I (Public) Figure 1. Current Cycle Core Loading Diagram Page 12 of 27 60 16 22 22 22 23 23 11 23 23 16 16 16 22 16 58 21 24 11 26 29 29 3 24 23 3 29 29 26 23 24 21

56 22 22 11 22 36 25 36 25 36 26 26 36 25 36 25 36 22 23 22 22

54 22 23 3 36 32 32 35 32 35 33 33 35 32 35 32 32 36 3 22 22

52 16 23 26 32 33 34 25 31 25 31 4 4 31 25 31 25 34 33 32 26 11 22

50 22 16 22 25 32 32 34 28 35 29 31 29 31 31 29 31 29 35 28 34 32 32 25 23 16 22

48 22 23 26 32 3 34 3 35 34 34 3 31 26 26 31 3 34 34 35 3 34 3 32 26 23 22

46 21 16 3 32 32 34 3 35 3 34 4 35 25 38 38 25 35 4 34 3 35 3 34 32 32 3 22 21

44 22 24 22 36 33 34 3 35 29 39 29 35 34 34 3 3 34 34 35 29 39 29 35 3 34 33 36 22 23 16

42 23 23 36 32 34 28 35 3 39 26 35 4 39 26 31 31 26 39 4 35 26 39 3 35 28 34 32 36 23 22

40 16 29 25 32 25 35 34 34 29 35 25 38 30 31 25 25 31 30 38 25 35 29 34 34 35 25 32 25 26 22

38 16 29 36 35 31 29 34 4 35 4 38 25 35 27 37 37 27 35 25 38 4 35 4 34 29 31 35 36 29 22

36 23 26 25 32 25 31 3 35 34 39 30 35 29 37 3 3 37 29 35 30 39 34 35 3 31 25 32 25 29 16

34 22 3 36 35 31 29 31 25 34 26 31 27 37 26 35 35 26 37 27 31 26 34 25 31 29 31 35 36 3 24

32 16 24 26 33 4 31 26 38 3 31 25 37 3 35 25 25 35 3 37 25 31 3 38 26 31 4 33 26 24 24

30 23 24 26 33 4 31 26 38 3 31 25 37 3 35 25 25 35 3 37 25 31 3 38 26 31 4 33 26 23 23

28 23 3 36 35 31 29 31 25 34 26 31 27 37 26 35 35 26 37 27 31 26 34 25 31 29 31 35 36 3 24

26 23 29 25 32 25 31 3 35 34 39 30 35 29 37 3 3 37 29 35 30 39 34 35 3 31 25 32 25 29 16

24 22 29 36 35 31 29 34 4 35 4 38 25 35 27 37 37 27 35 25 38 4 35 4 34 29 31 35 36 29 22

22 16 26 25 32 25 35 34 34 29 35 25 38 30 31 25 25 31 30 38 25 35 29 34 34 35 25 32 25 26 16

20 22 11 36 32 34 28 35 3 39 26 35 4 39 26 31 31 26 39 4 35 26 39 3 35 28 34 32 36 23 22

18 16 24 22 36 33 34 3 35 29 39 29 35 34 34 3 3 34 34 35 29 39 29 35 3 34 33 36 22 24 16

16 21 23 3 32 32 34 3 35 3 34 4 35 25 38 38 25 35 4 34 3 35 3 34 32 32 3 22 21

14 22 16 26 32 3 34 3 35 34 34 3 31 26 26 31 3 34 34 35 3 34 3 32 26 23 22

12 22 16 23 25 32 32 34 28 35 29 31 29 31 31 29 31 29 35 28 34 32 32 25 16 22 22

10 22 11 26 32 33 34 25 31 25 31 4 4 31 25 31 25 34 33 32 26 11 22

8 22 23 3 36 32 32 35 32 35 33 33 35 32 35 32 32 36 3 22 16

6 22 16 22 22 36 25 36 25 36 26 26 36 25 36 25 36 22 23 16 22

4 21 24 23 26 29 29 3 24 23 3 29 29 26 23 24 21

2 16 22 22 22 22 23 16 23 24 11 22 22 23 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 3=GNF2-P10DG2B403-8G7.0/4G6.0-100T2-150-T6-4236 (Cycle 20) 4=GNF2-P10DG2B393-15GZ-100T2-150-T6-4235 (Cycle 20)11=GNF2-P10DG2B395-14GZ-100T2-150-T6-3991 (Cycle 19)16=GNF2-P10DG2B390-4G8.0/8G7.0/2G6.0-100T2-150-T6-3992 (Cycle 19)21=GNF2-P10DG2B399-13GZ-100T2-150-T6-3993 (Cycle 19)22=GNF2-P10DG2B404-13GZ-100T2-150-T6-3994 (Cycle 19)23=GNF2-P10DG2B390-4G8.0/8G7.0/2G6.0-100T2-150-T6-3992 (Cycle 19)24=GNF2-P10DG2B404-13GZ-100T2-150-T6-3994 (Cycle 19)25=GNF2-P10DG2B400-13GZ-100T2-150-T6-4232 (Cycle 20)26=GNF2-P10DG2B393-4G8.0/8G7.0/2G6.0-100T2-150-T6-4233 (Cycle 20)27=GNF2-P10DG2B400-13GZ-100T2-150-T6-4232 (Cycle 20)28=GNF2-P10DG2B393-4G8.0/8G7.0/2G6.0-100T2-150-T6-4233 (Cycle 20) 29=GNF2-P10DG2B393-15GZ-100T2-150-T6-4235 (Cycle 20) 30=GNF2-P10DG2B403-8G7.0/4G6.0-100T2-150-T6-4236 (Cycle 20) 31=GNF2-P10DG2B409-14GZ-100T2-150-T6-4365 (Cycle 21) 32=GNF2-P10DG2B417-12G7.0-100T2-150-T6-4366 (Cycle 21) 33=GNF2-P10DG2B417-12G7.0-100T2-150-T6-4366 (Cycle 21) 34=GNF2-P10DG2B402-15GZ-100T2-150-T6-4367 (Cycle 21) 35=GNF2-P10DG2B402-15GZ-100T2-150-T6-4367 (Cycle 21) 36=GNF2-P10DG2B424-12G7.0-100T2-150-T6-4368 (Cycle 21) 37=GNF2-P10DG2B408-14GZ-100T2-150-T6-4369 (Cycle 21) 38=GNF2-P10DG2B403-14GZ-100T2-150-T6-4370 (Cycle 21) 39=GNF2-P10DG2B409-14GZ-100T2-150-T6-4365 (Cycle 21)

Non-Proprietary Information - Class I (Public) Figure 2. Previous Cycle Core Loading Diagram Page 13 of 27 60 9 7 1 18 7 10 2 10 2 6 7 1 10 6 58 8 10 10 2 10 6 10 7 7 10 6 10 2 2 10 2 56 1 10 8 8 6 10 10 23 16 11 11 16 23 8 10 6 8 2 2 1

54 8 2 10 22 23 23 22 3 3 30 30 3 3 22 23 23 22 10 8 2

52 2 2 2 24 24 3 21 3 3 3 16 16 3 3 3 21 3 24 24 10 8 2

50 1 2 6 8 23 3 3 25 25 4 25 22 26 26 22 25 4 25 25 3 3 23 8 6 2 1

48 2 8 9 23 22 27 21 25 16 25 22 25 16 16 25 22 25 16 25 21 27 22 23 9 8 9

46 8 7 10 24 3 27 23 25 16 26 16 26 23 29 29 23 26 16 26 16 25 23 27 3 24 10 7 8

44 9 6 8 22 24 3 21 25 22 28 22 25 16 29 16 16 29 16 25 22 28 22 25 21 3 24 22 8 6 2

42 7 10 8 23 3 25 25 16 28 16 26 22 29 16 4 4 16 29 22 26 16 28 16 25 25 3 23 2 10 7

40 1 8 8 23 21 25 16 26 22 26 22 29 11 26 16 16 26 11 29 22 26 22 26 16 25 21 23 8 8 1

38 7 8 2 22 3 4 25 16 25 22 29 16 26 23 29 29 23 26 16 29 22 25 16 25 4 3 22 8 8 7

36 2 8 23 3 3 25 22 26 16 29 11 26 22 29 23 23 29 22 26 11 29 16 26 22 25 3 3 23 8 10

34 2 10 16 3 3 22 25 23 29 16 26 23 29 16 4 4 16 29 23 26 16 29 23 25 22 3 3 16 10 7

32 2 6 11 30 16 26 16 29 16 4 16 29 23 4 16 16 4 23 29 16 4 16 29 16 26 16 30 11 6 2

30 2 6 11 30 16 26 16 29 16 4 16 29 23 4 16 16 4 23 29 16 4 16 29 16 26 16 30 11 6 2

28 2 10 16 3 3 22 25 23 29 16 26 23 29 16 4 4 16 29 23 26 16 29 23 25 22 3 3 16 10 2

26 1 8 23 3 3 25 22 26 16 29 11 26 22 29 23 23 29 22 26 11 29 16 26 22 25 3 3 23 8 1

24 18 10 8 22 3 4 25 16 25 22 29 16 26 23 29 29 23 26 16 29 22 25 16 25 4 3 22 8 8 7

22 10 2 10 23 21 25 16 26 22 26 22 29 11 26 16 16 26 11 29 22 26 22 26 16 25 21 23 8 8 10

20 7 8 2 23 3 25 25 16 28 16 26 22 29 16 4 4 16 29 22 26 16 28 16 25 25 3 23 2 10 2

18 9 6 8 22 24 3 21 25 22 28 22 25 16 29 16 16 29 16 25 22 28 22 25 21 3 24 22 8 2 2

16 8 7 10 24 3 27 23 25 16 26 16 26 23 29 29 23 26 16 26 16 25 23 27 3 24 10 7 8

14 2 8 2 23 22 27 21 25 16 25 22 25 16 16 25 22 25 16 25 21 27 22 23 2 8 2

12 1 2 6 8 23 3 3 25 25 4 25 22 26 26 22 25 4 25 25 3 3 23 2 2 6 1

10 10 2 10 24 24 3 21 3 3 3 16 16 3 3 3 21 3 24 24 2 2 2

8 2 2 10 22 23 23 22 3 3 30 30 3 3 22 23 23 22 10 10 2

6 1 2 8 8 6 10 9 23 16 11 11 16 23 10 8 6 8 8 2 1

4 8 10 10 2 10 6 10 7 7 10 6 10 6 2 10 8

2 9 7 1 7 6 2 2 2 10 6 7 1 7 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 1=GE14-P10DNAB416-15GZ-100T-150-T6-2908 (Cycle 18) 2=GE14-P10DNAB408-15GZ-100T-150-T6-3213 (Cycle 18) 3=GNF2-P10DG2B403-8G7.0/4G6.0-100T2-150-T6-4236 (Cycle 20) 4=GNF2-P10DG2B393-15GZ-100T2-150-T6-4235 (Cycle 20) 6=GE14-P10DNAB414-14GZ-100T-150-T6-3200 (Cycle 18) 7=GE14-P10DNAB403-15GZ-100T-150-T6-3003 (Cycle 18) 8=GE14-P10DNAB417-15GZ-100T-150-T6-3199 (Cycle 18) 9=GE14-P10DNAB408-15GZ-100T-150-T6-3213 (Cycle 18)10=GE14-P10DNAB420-13GZ-100T-150-T6-3198 (Cycle 18)11=GNF2-P10DG2B395-14GZ-100T2-150-T6-3991 (Cycle 19)16=GNF2-P10DG2B390-4G8.0/8G7.0/2G6.0-100T2-150-T6-3992 (Cycle 19) 18=GE14-P10DNAB403-15GZ-100T-150-T6-3003 (Cycle

18) 21=GNF2-P10DG2B399-13GZ-100T2-150-T6-3993 (Cycle 19) 22=GNF2-P10DG2B404-13GZ-100T2-150-T6-3994 (Cycle 19) 23=GNF2-P10DG2B390-4G8.0/8G7.0/2G6.0-100T2-150-T6-3992 (Cycle 19) 24=GNF2-P10DG2B404-13GZ-100T2-150-T6-3994 (Cycle 19) 25=GNF2-P10DG2B400-13GZ-100T2-150-T6-4232 (Cycle 20) 26=GNF2-P10DG2B393-4G8.0/8G7.0/2G6.0-100T2-150-T6-4233 (Cycle 20) 27=GNF2-P10DG2B400-13GZ-100T2-150-T6-4232 (Cycle 20) 28=GNF2-P10DG2B393-4G8.0/8G7.0/2G6.0-100T2-150-T6-4233 Cycle 20) 29=GNF2-P10DG2B393-15GZ-100T2-150-T6-4235 (Cycle 20) 30=GNF2-P10DG2B403-8G7.0/4G6.0-100T2-150-T6-4236 (Cycle 20)

Non-Proprietary Information - Class I (Public) Figure 3. Figure 4.1 from NEDC-32601P-A Page 14 of 27

[[ ]]

Non-Proprietary Information - Class I (Public) Figure 4. Figure III.5-1 from NEDC-32601P-A Page 15 of 27

[[ ]]

Non-Proprietary Information - Class I (Public) Figure 5. Relationship Between MIP and CPR Margin Page 16 of 27

[[ ]]

Non-Proprietary Information - Class I (Public) Table 1. Description of Core Page 17 of 27 Number of Bundles in the Core 764 764 Limiting Point (i.e.,

Beginning of Cycle (BOC)/Middle of Cycle (MOC)/End of

Cycle (EOC)) EOC EOC MOC EOC EOC EOC Cycle Exposure at Limiting Point (MWd/STU) 12,400 12,400 8,100 14,550 14,550 14,550

% Rated Core Power 100.0 100.0 78.8 100.0 100.0 100.0

% Rated Core Flow 82.8 100.0 55.0 83.0 100.0 110.0 Reload Fuel Type GNF2 GNF2 Latest Reload

Batch Fraction, % 35.6 45.0 Latest Reload

Average Batch, Wt% Enrichment 3.97 4.09 Core Fuel, %

GNF2 GE14 70.7 29.3 100.0 --- Core Average Wt% Enrichment 4.01 4.02 Non-Proprietary Information - Class I (Public) Table 2. SLMCPR Calculation Methodologies Page 18 of 27 Non-Power Distribution Uncertainty NEDC-32601P-A NEDC-32601P-A Power Distribution

Methodology NEDC-32601P-A NEDC-32601P-A Power Distribution Uncertainty NEDC-32694P-A NEDC-32694P-A Core Monitoring System 3DMONICORE 3DMONICORE R-Factor Calculation

Methodology NEDC-32505P-A NEDC-32505P-A

Non-Proprietary Information - Class I (Public) Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Page 19 of 27

[[

]]

Non-Proprietary Information - Class I (Public) Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Page 20 of 27

Calculated Monte

Carlo TLO

SLMCPR [[ ]] 1.119 1.093 1.074 1.074

[[ ]] Additional SLMCPR Licensing

Conditions

[[ ]] 0.02 1 0.02 1 0.02 1 0.02 1 Requested Change to the Technical Specification

SLMCPR N/A 1.15 (TLO) / 1.15 (SLO)

[[

]] MELLLA+

Non-Proprietary Information - Class I (Public) Table 4. Non-Power Distribution Uncertainties Page 21 of 27

Feedwater

Flow Measurement 1.76 N/A N/A N/A N/A N/A N/A Feedwater Temperature Measurement 0.76 N/A N/A N/A N/A N/A N/A Reactor Pressure Measurement 0.50 N/A N/A N/A N/A N/A N/A Core Inlet Temperature Measurement 0.20 N/A N/A N/A N/A N/A N/A Total Core

Flow Measurement 2.5 TLO 6.0 SLO N/A N/A N/A N/A N/A N/A Channel Flow

Area Variation 3.0 N/A N/A N/A N/A N/A N/A Friction Factor Multiplier 10.0 N/A N/A N/A N/A N/A N/A Non-Proprietary Information - Class I (Public) Table 4. Non-Power Distribution Uncertainties Page 22 of 27

Channel Friction Factor Multiplier 5.0 N/A N/A N/A N/A N/A N/A Feedwater

Flow Measurement

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Feedwater Temperature Measurement

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Reactor Pressure Measurement

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Core Inlet Temperature Measurement 0.2 0.2 0.2 0.2 0.2 0.2 0.2 Total Core

Flow Measurement 2.5 TLO 6.0 SLO 3.02 TLO 6.0 SLO 2.5 TLO 6.0 SLO 6.0 TLO 6.0 TLO 2.5 TLO 6.0 SLO 2.5 TLO 6.0 SLO Channel Flow

Area Variation

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]]

Non-Proprietary Information - Class I (Public) Table 4. Non-Power Distribution Uncertainties Page 23 of 27

Friction Factor Multiplier

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Channel Friction Factor Multiplier 5.0 5.0 5.0 5.0 5.0 5.0 5.0

Non-Proprietary Information - Class I (Public) Table 5. Power Distribution Un certainties Page 24 of 27

GEXL R-Factor [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Random Effective TIP Reading 1.2 TLO 2.85 SLO N/A N/A N/A N/A N/A N/A Systematic

Effective TIP Reading 8.6 N/A N/A N/A N/A N/A N/A GEXL R-Factor [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Random Effective TIP Reading 1.2 TLO 2.85 SLO 1.45 TLO 2.85 SLO 1.2 TLO 2.85 SLO 2.85 TLO 2.85 TLO 1.2 TLO 2.85 SLO 1.2 TLO 2.85 SLO TIP Integral [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]]

Non-Proprietary Information - Class I (Public) Table 5. Power Distribution Un certainties Page 25 of 27

Four Bundle

Power Distribution

Surrounding

TIP Location

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Contribution

to Bundle

Power Uncertainty Due to LPRM

Update [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Contribution

to Bundle

Power Due to Failed TIP

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Contribution

to Bundle

Power Due to

Failed LPRM

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] Total Uncertainty in

Calculated

Bundle Power

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]]

Non-Proprietary Information - Class I (Public) Table 5. Power Distribution Un certainties Page 26 of 27 Uncertainty of

TIP Signal

Nodal Uncertainty

[[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]] [[ ]]

Non-Proprietary Information - Class I (Public) Table 6. Critical Power Uncertainties Page 27 of 27 GE11 GE14 GNF2 GE11 GE14 GNF2

002N5030 R1-P Affidavit Page 1 of 3 state as follows:

(1) I am Engineering Manager, Reload Design and Analysis, Global Nuclear Fuel - Americas, LLC (GNF-A), and have been delegated the function of reviewing the information described in paragraph (2) whic h is sought to be withheld, a nd have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in GNF-A proprietary report 002N5030 R1-P, GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Peach Bottom Unit 3 Cycle 21 , Revision 0, March 16, 2015. GNF-A proprietary information in 002N5030 R1-P, GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Peach Bottom Unit 3 Cycle 21, Revision 0, March 16, 2015, is identified by a dotted underline placed within doubl e square brackets. [[This sentence is an example.

{3}]] GNF-A proprietary information in figures and some tabl es is identified with double square brackets before and after the object. In each case, the superscript notation

{3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.

(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CF R 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exempti on 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulat ory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group

v. FDA, 704 F2d 1280 (DC Cir. 1983).

(4) Some examples of categories of information which fit into the de finition of proprietary information are:

a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;

b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;

c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;

d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.

002N5030 R1-P Affidavit Page 2 of 3 The information sought to be withheld is cons idered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.

(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information s ought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to preven t its unauthorized disclosure, ar e as set forth in paragraphs (6) and (7) following.

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most lik ely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project ma nager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determinati on of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.

(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology. The development of this methodology, along with the testing, development and approval was achieved at a significant cost to GNF-A.

The development of the fuel design and licensing methodology along with the interpretation and application of the analytical results is derived from an extensive experience database that constitutes a major GNF-A asset.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.

The value of the technology base goes bey ond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value

derived from providing analyses done with NRC-approved methods.

The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A.

002N5030 R1-P Affidavit Page 3 of 3 The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to qua ntify, but it clearly is substantial.

GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitor s without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on this 12th day of March 2015.

Lukas Trosman Engineering Manager, Reload Design and Analysis Global Nuclear Fuel - Americas, LLC

3901 Castle Hayne Road Wilmington, NC 28401 Lukas.Trosman@ge.com