ML072480572

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Gnf S-0000-0068-2643, Gnf Additional Information Regarding the Requested Changes to the Technical Specification Slmcpr. Hope Creek (KT1) Cycle 15
ML072480572
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/15/2007
From:
Global Nuclear Fuel - Americas
To:
Office of Nuclear Reactor Regulation
References
LCR H05-01, Rev 1, LR-N07-0215 GNF S-0000-0068-2643
Download: ML072480572 (22)
v • d • e


Text

ATTACHMENT 3 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354 Extended Power Uprate GNF Hope Creek C15 SLMCPR - Non-Proprietary Letter

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment 6/15/2007 GNF S-0000-0068-2643 GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek (KT1) Cycle 15 Hope Creek (KT1) Cycle 15 Page 1 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment Proprietary Information Notice This document is the GNF non-proprietary version of the GNF proprietary report. From the GNF proprietary version, the information denoted as GNF proprietary (enclosed in double brackets) was deleted to generate this version.

Proprietary Information Notice Page 2 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment Table of Contents 1.0 M ETH O D O LO G Y .......................................................................................................................................... 4 2.0 D ISC U SSIO N ................................................................................................................................................... 4 2.1. M AJOR CONTRIBUTORS TO SLM CPR CHANGE .......................................................................................... 4 2.2. DEVIATIONS IN N RC-APPROVED U NCERTAINTIES ..................................................................................... 5 2.2.1. R-Factor................................................................................................................................................. 5 2.2.2. Core Flow Rate and Random Effective TIP Reading....................................................................... 5 2.2.3. Reactor PressureM easurement .................................................................................................... 6 2.3. DEPARTURE FROM NRC-A PPROVED M ETHODOLOGY. ............................................................................... 6 2.4. FUEL A XIAL POWER SHAPE PENALTY ................................................................................................... 7 2.5. M ETHODOLOGY RESTRICTIONS ...................................................................................................................... 8 2.6. M IN IM UM CORE FLOW CONDITION ................................................................................................................ 8 2.7. LIM ITING CONTROL ROD PATTERNS ............................................................................................................... 8 2.8. CORE M ONITORING SYSTEM .......................................................................................................................... 8 2.9. POWER/FLOW M AP ......................................................................................................................................... 8 2.10. CORE LOADING D IAGRAM .......................................................................................................................... 8 2.1 1. FIGURE REFERENCES .................................................................................................................................. 8 2.12. A DDITIONAL SLM CPR LICENSING CONDITIONS ................................................................................... 9 2.13. SUM MARY .................................................................................................................................................. 9 3.0 REFER EN C ES .............................................................................................................................................. 10 List of Figures FIGURE 1. CURRENT CYCLE CORE LOADIN G D IAGRAM .............................................................................................. 11 FIGURE 2. PREVIOUS CYCLE CORE LOADING D IAGRAM ......................................................................................... 12 FIGURE 3. FIGURE 4.1 FROM NED C-32601 -P-A ......................................................................................................... 13 FIGURE 4. FIGURE 111.5-1 FROM N EDC-32601P-A ...................................................................... 13 FIGURE 5. FIGURE 111.5-2 FROM N EDC-32601P-A ................................................................................................. 13 List of Tables TABLE 1. D ESCRIPOPTION OF CORE ................................................................................................................................. 14 TABLE 2. SLM CPR CALCULATION M ETHODOLOGIES ............................................................................................. 15 TABLE 3. MONTE CARLO CALCULATED SLMCPR vs. ESTIMATE .......................................................................... 16 TABLE 4. NON-POWER D ISTR IBUTION U NCERTAINTIES ......................................................................................... 17 TABLE 5. POWER D ISTRIB UTION U NCERTAINTIES ....................................................................................................... 19 TABLE 6. CRITICAL POW ER U NCERTAINTIES ............................................................................................................... 21 Table of Contents Page 3 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment 1.0 Methodology GNF performed the Hope Creek Cycle 15 Safety Limit Minimum Critical Power Ratio (SLMCPR) calculation in accordance to NEDE-24011-P-A "General Electric Standard Application for Reactor Fuel" (Revision 15) using the following 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 GEl 1, GEl2 and GE13 Fuel" (Revision 1, July 1999).
  • NEDO-10958-A "General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application" (January 1977).

Table 2 identifies the actual methodologies used for the previous and current cycle 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. The "Previous Cycle" is Cycle 14, and the "Current Cycle" is Cycle 15.

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 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 impact 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 Methodology Page 4 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment estimated impacts on the TLO SLMCPR due to methodology deviations, penalities, and/or uncertainties deviations from approved values. Based on the MIPRIP correlation and any impacts 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 (( f31)) and the inherent variation in the Monte Carlo results (( 13 W], the change in the Hope Creek Cycle 15 calculated Monte Carlo TLO SLMCPR using rated core power and rated core flow conditions is consistent with the corresponding estimated TLO SLMCPR value.

2.2. Deviations in NRC-Approved Uncertainties Tables 4 and 5 provide a list of 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 NRC-approved values. Also, estimated impact 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 (( (3))) 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 "aYRPEAK" in Figure 4.1 from NEDC-32601P-A, which has been provided for convenience in Figure 3 of this attachment, is affected by this deviation. Reference 4 technically justifies that a GEXL R-Factor uncertainty of (( 131)) accounts for a channel bow uncertainty of up to (( (3))).

The Hope Creek Cycle 15 analysis has addressed the potential for shadow corrosion-induced channel bow by increasing the NRC-approved R-Factor uncertainty from (( 13))) to (( f3()).

Accounting for control blade shadow corrosion-induced channel bow, the Hope Creek Cycle 15 analysis shows an expected channel bow uncertainty of (( 131)), which is bounded by a GEXL R-Factor uncertainty of (( 131)). Thus the use of a GEXL R-Factor uncertainty of (( 13))) adequately accounts for control blade shadow corrosion-induced channel bow for Hope Creek Cycle 15 and subsequent cycles that exhibit channel bow uncertainty of ((I13 ))).

2.2.2. Core Flow Rate and Random Effective TIP Reading At this time, GNF has not been able to show that the NRC-approved process to calculate the SLMCPR only at the rated core power and rated core flow condition is adequately bounding relative to the SLMCPR calculated at rated core power and minimum core flow, see Reference 5.

The minimum core flow condition can be more limiting due to the control rod pattern used.

GNF has modified the NRC-approved process for determining the SLMCPR to include 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. GNF believes this modification is conservative and may in the future provide justification that the original NRC-approved process is adequately bounding.

Discussion Page 5 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment For the TLO calculations performed at 94.8% core flow, the approved uncertainty values for the core flow rate (2.5%) and the random effective TIP reading (1.2%) are conservatively adjusted by dividing them by 94.8/100. The steps "a CORE FLOW" and "a TIP (INSTRUMENT)" in Figure 4.1 from NEDC-32601P-A, which has been provided for convenience in Figure 3 of this attachment) are affected by this deviation, respectively.

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 since 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.

2.2.3. Reactor Pressure Measurement The input for reactor pressure measurement uncertainty was changed from ((131)) to ((I31))]. Hope Creek supplied this conservative value to be used in the GNF SLMCPR analysis.

2.3. Departure from NRC-Approved Methodology No departures from NRC-approved methodologies were used in the Hope Creek Cycle 15 SLMCPR calculations.

NRC-approved methodologies or methodologies that produce a conservative result (less margin to acceptance limits) were used in the Hope Creek Cycle 15 SLMCPR calculations.

Discussion Page 6 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment 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, see References 3, 6, and 7. The following table identifies, by marking with an "X", this potential for each GNF product line currently being offered:

((

I t I -i ]

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:

((

13111 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 impact 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 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 Hope Creek Cycle 15 SLMCPR values.

Discussion Page 7 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment 2.5. Methodology Restrictions The four restrictions identified on Page 3 of NRC's Safety Evaluation relating to the General Electric Licensing Topical Reports NEDC-32601P, NEDC-32694P, and Amendment 25 to NEDE-240 11-P-A (March 11, 1999) are addressed in References 1, 2, and 3.

No new GNF fuel designs are being introduced in Hope Creek Cycle 15; therefore, the NEDC-32505-P-A statement "...if new fuel is introducted, 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 Hope Creek Cycle 15 the minimum core flow SLMCPR calculation performed at 94.8% core flow at rated core power condition was not limiting as compared to the rated core flow at rated core power condition.

.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 Hope Creek Cycle 15.

2.8. Core Monitoring System For Hope Creek Cycle 15, 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 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. Table I provides a description of the core.

2.11. Figure References Figure 3 is Figure 4.1 from NEDC-32601-P-A. Figure 4 is Figure 111.5-1 from NEDC-32601P-A. Figure 5 is Figure 111.5-2 from NEDC-32601P-A.

Discussion Page 8 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment 2.12. Additional SLMCPR Licensing Conditions Hope Creek has submitted a licensing amendment to increase rated power from 3339 MWt to 3840 MWt, which is reflected in the attached power/flow map. This uprate licensing amendment is currently being reviewed by the NRC with anticipation of approval before Hope Creek Cycle 15 starts up. Recent NRC communications for such uprates have suggested that an 0.02 adder to the SLMCPR will be a licensing condition. In anticipation that this licensing condition will be imposed on the Hope Creek uprate amendment, the SLMCPR has been established by adding 0.02 to the cycle-specific SLMCPR value calculated using the NRC-approved methodologies documented in NEDE-2401 1-P-A (see Table 3).

2.13. Summary The requested changes to the Technical Specification SLMCPR values are 1.08 for TLO and 1.10 for SLO for Hope Creek Cycle 15.

Discussion Page 9 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment 3.0 References

1. Letter, Glen A. Watford (GNF-A) to U.S. Nuclear Regulatory Commission Document Control Desk with attention to R. Pulsifer (NRC), "Confirmation of 10xl0 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 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 GE14 Fuel", FLN-2001-017, October 1.2001.
3. 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.
4. 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.
5. 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.
6. 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.

7. 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.

References Page 10 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment Figure 1. Current Cycle Core Loading Diagram 58f]

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GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment Figure 2. Previous Cycle Core Loading Diagram 60 E_L[D [D]_EA] A] [A] E] []_ [A]_[A [A] [

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Figure 2. Previous Cycle Core Loading Diagram Pacre1-1 12 of 21

GNF NON-PROPRIETARY INFORMATION Class I GNF S-0000-0068-2643 GNF Attachment Figure 3. Figure 4.1 from NEDC-32601-P-A

((131))

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

((131))

Figure 5. Figure 111.5-2 from NEDC-32601P-A

(( 131))

Figure 3. Figure 4.1 from NEDC-32601-P-A Page 13 of 21

GNF Non-Proprietary Information Class I GNF S-0000-0068-2643 GNF Attachment Table 1. Desclription 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 764 764 764 764 Core Limiting Cycle Exposure Point (i.e. BOC BOC EOC EOC BOC/MOC/EOC)

Cycle Exposure at Limiting Point 200 200 11000 11000 (MWd/STU)

% Rated Core Flow 76.6* 100 94.8* 100 Reload Fuel Type GE14 GE14 GEl4 GEl4 Latest Reload Batch 20.4 20.4 29.8 29.8 Fraction, %

Latest Reload Average Batch Weight % 3.93 3.93 4.00 4.00 Enrichment Core Fuel Fraction, %:

GE14 41.9 41.9 71.7 71.7 SVEA96 58.1 58.1 28.3 28.3 Core Average Weight % 3.76 3.76 3.88 3.88 Enrichment

  • Refer to the Power/Flow map for lowest flow at rated power.

Table 1. Description of Core Pacye L_ 14 of 21

GNF Non-Proprietary Information Class I GNF S-0000-0068-2643 GNF Attachment 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 NEDC-32601P-A NEDC-32601P-A Uncertainty Power Distribution NEDC-32694P-A NEDC-32694P-A NEDC-32694P-A NEDC-32694P-A Methodology Power Distribution NEDC-32694P-A NEDC-32694P-A NEDC-32694P-A NEDC-32694P-A Uncertainty Core Monitoring System 3DMONICORE 3DMONICORE 3DMONICORE 3DMONICORE Table 2. SLMCPR Calculation Methodologies Page 15 of 21

GNF Non-Proprietary Information Class I GNF S-0000-0068-2643 GNF Attachment 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

[U 13111 Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Page 16 of 21

GNF Non-Proprietary Information Class i GNF S-0000-0068-2643 GNF Attachment 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 ca (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case GETAB Feedwater Mow 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 6.0 SLO/2.5 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 N/A Factor Multiplier Table 4. Non-Power Distribution Uncertainties Page 17 of 21

GNF Non-Proprietary Information Class I GNF S-0000-0068-2643 GNF Attachment 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

+ g (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case NEDC-32601-P-A I1 I I I I

I I Table 4. Non-Power Distribution Uncertainties Page 18 of 21

GNF Non-Proprietary Information Class I GNF S-0000-0068-2643 GNF Attachment 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

+/- * (%) Flow Limiting Case Limiting Case Flow LiMiting Case Limiting Case GETAB/NEDC-32601-P-A GEXL R-Factor [E {3)] 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-32694-P-A, 3DMONICORE GEXL R-Factor (( 313)) (( E[ "3)))

(((3))) ((

[3))) 131))

Random Effective 2.85 SLO/1.2 TLO 2.85 SLO/1.2 TLO 2.85 SLO/1.2 TLO 2.85 SLO/1.2 TLO 2.85 SLO/I.2 TLO TIP Reading TIP Integral E[ 131] (((3)))

1311] E1 (( {31)) ]3))]

Four Bundle Power Distribution 131]j Surrounding TIP 3] (( (3{)) ] [ 3}][3))

Location Contribution to B undle Pow er "I)) "I)) 131]j "I))

Uncertainty Due to LPRM Update Table 5. Power Distribution Uncertainties Page 19 of 21

GNF Non-Proprietary Information Class I GNF S-0000-0068-2643 GNF Attachment 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 ag (%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case Contribution to Bundle Power Due to (( {3})) (( {3})) (({3})) (({3]3]

Failed TIP Contribution to Bundle Power Due to (( {3})) (( (3))) ((13)1] (({31)) (((3)))

Failed LPRM Total Uncertainty in Calculated Bundle (( 131)) (((3))) ((3T)) ((131)) ((]3)]

Power Uncertainty of TIP 3 3 3 Signal Nodal E[ 13))) E[ {31)) E13 [iE }))

))] ([E)))

Uncertainty Table 5. Power Distribution Uncertainties Page 20 of 21

GNF Non-Proprietary Information Class I GNF S-0000-0068-2643 GNF Attachment Table 6. Critical Power Uncertainties Description TNominal Value Previous Cycle Minimum Core Previous Cycle Rated Core Flow Current Cycle Minimum Core Current Cycle Rated Core Flow

+/- o(%) Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case 131))

Table 6. Critical Power Uncertainties Page 21 of 21

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