ML14223A794
| ML14223A794 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/31/2014 |
| From: | Global Nuclear Fuel, Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14223A790 | List: |
| References | |
| VSP-SNC-HV1-14-068 GNF-001N6296-R1-NP | |
| Download: ML14223A794 (26) | |
Text
Edwin I. Hatch Nuclear Plant - Units 2 License Amendment Request Concerning Safety Limit Minimum Critical Power Ratio Non-Proprietary GNF Report GNF-001N6296-R1-NP
ENCLOSURE2 VSP-SNC-HV1-14-068 GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Hatch 2 Cycle 24 Non-Proprietary Information - Class I (Public)
INFORMATION NOTICE This is a non-proprietary version of VSP-SNC-HV1-14-068 Enclosure 1, which has the proprietary information removed.
Portions of the document that have been removed are indicated by white space inside an open and closed bracket as shown here ((
I].
Non-Proprietary Information-Class I (Public)
July 2014 GNF-00IN6296-R I-NP PLM Specification 001N6296 RI GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hatch 2 Cycle 24 Copvrighi 2014 Global Nuclear Fuel - Americas. LLC
.4// Rights Reserved Hatch 2 Cycle 24 Page I of 24
Non-Proprietary Information-Class I (Public)
Information Notice This is a non-proprietary version of the document GNF-001N6296-RI-P, which has the proprietary information removed.
Portions of the document that have been removed are indicated by an open and closed bracket as shown here ((
Important Notice Regarding Contents of this Report Please Read Carefully The design, engineering, and other information contained in this document is furnished for the purpose of providing information regarding the requested changes to the Technical Specification SLMCPR for Southern Nuclear Operating Company Hatch 2. The only undertakings of GNF-A with respect to information in this document are contained in contracts between GNF-A and Southern Nuclear Operating Company, and nothing contained in this document shall be construed as changing that contract. The use of this information by anyone other than Southern Nuclear Operating Company, or for any purposes other than those for which it is intended is not authorized; and with respect to any unauthorized use, GNF-A makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.
Page 2 of 24
Non-Proprietary Information-Class I (Public)
Table of Contents 1.0 M ethodology........................................................................................................................
4 2.0 D iscussion.............................................................................................................................
4 2.1.
M ajor Contributors to SLM CPR Change.....................................................................
4 2.2.
Deviations in N RC-A pproved Uncertainties.................................................................
5 2.2.1.
R-Factor......................................................................................................................
5 2.2.2.
Core Flow Rate and Random Effective TIP Reading.............................................
6 2.3.
Departure from N RC-A pproved M ethodology............................................................
6 2.4.
Fuel Axial Power Shape Penalty..................................................................................
7 2.5.
M ethodology Restrictions.............................................................................................
8 2.6.
M inim um Core Flow Condition....................................................................................
8 2.7.
Lim iting Control Rod Patterns......................................................................................
9 2.8.
Core M onitoring System...............................................................................................
9 2.9.
Pow er/Flow M ap.......................................................................................................
9 2.10.
Core Loading D iagram................................................................................................
9 2.11.
Figure References...................................................................................................
9 2.12.
Additional SLM CPR Licensing Conditions...............................................................
9
- 2. 13.
10CFR Part 21 Evaluation.........................................................................................
9 2.14.
Sum m ary........................................................................................................................
9 3.0 References..........................................................................................................................
10 List of Figures Figure 1. Current Cycle Core Loading D iagram.........................................................................
I 1 Figure 2. Previous Cycle Core Loading D iagram.....................................................................
12 Figure 3. Figure 4.1 from N EDC-32601P-A............................................................................
13 Figure 4. Figure 111.5-1 firom N EDC-32601P-A.......................................................................
14 Figure 5. Relationship Between M IP and CPR M argin..........................................................
15 List of Tables Table 1. Description of Core....................................................................................................
16 Table 2. SLM CPR Calculation M ethodologies.......................................................................
17 Table 3. M onte Carlo Calculated SLM CPR vs. Estim ate.........................................................
18 Table 4. N on-Power D istribution Uncertainties.....................................................................
20 Table 5. Power D istribution Uncertainties...............................................................................
22 Table 6. Critical Power Uncertainties......................................................................................
24 Table of Contents Page 3 of 24
Non-Proprietary Information-Class I (Public) 1.0 Methodology Global Nuclear Fuel (GNF) performs Safety Limit Minimumn Critical Power Ratio (SLMCPR) calculations in accordance with NEDE-2401 I-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 GEl I, GE12 and GE13 Fuel,"
Revision 1, July 1999.
Table 2 identifies the actual methodologies used for the Hatch 2 Cycle 23 and the Cycle 24 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.
2.1.
Major Contributors to SLMCPR Change In general, the calculated safety limit is dominated by two key parameters: (I) flatness of the core bundle-by-bundle Minimum Critical Power Ratio (MCPR) distribution; and (2) flatness of the bundle pin-by-pin power/R-Factor distribution. Greater flatness in either parameter yields more rods susceptible to boiling transition and thus a higher calculated SLMCPR.
MCPR Importance Parameter (MIP) measures the core bundle-by-bundle MCPR distribution and R-Factor Importance Parameter (RIP) measures the bundle pin-by-pin power/R-Factor distribution. The effect of the fuel loading pattern on the calculated TLO SLMCPR using rated core power and rated core flow conditions has been correlated to the parameter MIPRIP, which combines the MIP and RIP values.
Table 3 presents the MIP and RIP parameters for the previous cycle and the current cycle along with the TLO SLMCPR estimate using the MIPRIP correlation. If the minimumn 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 impacts due to deviations firom approved values, a final estimated TLO SLMCPR is determined. Table 3 Methodology Page 4 of 24
Non-Proprietary Information - Class I (Public) 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 Hatch 2 Cycle 24 calculated Monte Carlo TLO SLMCPR using rated core power and rated core flow conditions is consistent with the corresponding estimated TLO SLMCPR value.
The intent of the final estimated TLO SLMCPR is to provide an estimate to check the reasonableness of the Monte Carlo result. It is not used for any other purpose. The methodology and final SLMCPR is based on the rigorous Monte Carlo analysis.
The items in Table 3 that result in the increase of the estimated SLMCPR are discussed in Section 2.2.
Cycle 24 will be the first full reload of GNF2 for Hatch 2. The critical power uncertainty for GNF2 is defined in Table 6. As seen in Table 6, the critical power uncertainty for GNF2 is higher than the previous cycle's fuel type (GE14). As such, the GEXL uncertainty of the new fuel type tends to make the final SLMCPR higher.
2.2.
Deviations in NRC-Approved Uncertainties Tables 4 and 5 provide a list of NRC-approved uncertainties along with 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 ((
)) 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 "aY RPEAK" 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 ((
)) accounts for a channel bow uncertainty of uIp to Hatch 2 has experienced control blade shadow corrosion-induced channel bow to the extent that an increase in the NRC-approved R-Factor uncertainty ((
)) is deemed prudent to address its impact. Accounting for the control blade shadow corrosion-induced channel bow, the Hatch 2 Cycle 24 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 Hatch 2 Cycle 24.
Discussion Page 5 of 24
Non-Proprietary Information-Class I (Public) 2.2.2.
Core Flow Rate and Random Effective TIP Reading 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 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 92.9 % core flow, the approved uncertainty values for the core flow rate (2.5%) and the random effective Traversing Incore Probe (TIP) reading (1.2%) are conservatively adjusted by dividing them by 92.9/100.
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.
2.3.
Departure from NRC-Approved Methodology No departures from NRC-approved methodologies were used in the Hatch 2 Cycle 24 SLMCPR calculations.
Discussion Page 6 of 24
Non-Proprietary Information-Class I (Public) 2.4.
Fuel Axial Power Shape Penalty At this time, GNF has determined that higher uncertainties and non-conservative biases in the GEXL correlations for the various types of axial power shapes (i.e., inlet, cosine, outlet, and double hump) could potentially exist relative to the NRC-approved methodology values (References 3, 6, 7, and 8).
The following table identifies, by marking with an "X", this potential for each GNF product line currently being offered:
))
Axial bundle power shapes corresponding to the limiting SLMCPR control blade patterns are determined using the PANACEA 3D core simulator. These axial power shapes are classified in accordance to the following table:
If the limiting bundles in the SLMCPR calculation exhibit an axial power shape identified by this table, GNF penalizes the GEXL critical power uncertainties to conservatively account for the 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-2401 I-P-A along with values actually used.
Discussion Page 7 of 24
Non-Proprietary Information-Class I (Public)
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 Hatch 2 Cycle 24 SLMCPR values.
2.5.
Methodology Restrictions The four restrictions identified on page 3 of NRC's Safety Evaluation (SE) relating to the General Electric (GE) Licensing Topical Reports (LTRs) NEDC-32601 P, NEDC-32694P, and Amendment 25 to NEDE-2401 I-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 11), NEDC-33270P, Revision 0, FLN-2007-011, March 14, 2007.
Specifically, in the NRC audit report ML081630579 for the said document, Section 3.4.1 (page 59) states:
"The NRC staff-s SE of NEDC-32694P-A (Reference 19 of NEDC-33270P) provides four actions to follow whenever a new fuel design is introduced.
These four conditions are listed in Section 3.0 of 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 IOxIO array and two water rod makeup, as stated by the NRC audit report 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 Hatch 2 Cycle 24; 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 data" is not applicable.
2.6.
Minimum Core Flow Condition For Hatch 2 Cycle 24, the minimum core flow SLMCPR calculation performed at 92.9% core flow at rated core power conditions was not limiting as compared to the rated core flow at rated core power conditions.
Discussion Page 8 of 24
Non-Proprietary Information - Class I (Public) 2.7.
Limiting Control Rod Patterns The limiting control rod patterns used to calculate the SLMCPR reasonably assures that at least 99.9% of the fuel rods in the core would not be expected to experience boiling transition during normal operation or anticipated operational occurrences during the operation of Hatch 2 Cycle 24.
2.8.
Core Monitoring System For Hatch 2 Cycle 24, 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 document.
2.10. Core Loading Diagram Figures I 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 I-P-A. Table I provides a description of the core.
2.11.
Figure References Figure 3 is Figure 4.1 friom NEDC-32601P-A. Figure 4 is Figure 111.5-I from NEDC-32601P-A.
Figure 5 is based on Figure 111.5-2 fi'om NEDC-32601 P-A, and has been updated with GEl4 and GNF2 data.
2.12.
Additional SLMCPR Licensing Conditions For Hatch 2 Cycle 24, no additional SLMCPR licensing conditions are included in the analysis.
2.13.
10 CFR 21 Evaluation There are no known 10 CFR 21 factors that affect the Hatch 2 Cycle 24 SLMCPR calculations.
2.14.
Summary The requested changes to the Technical Specification SLMCPR values are 1.09 for TLO and
- 1. 12 for SLO for Hatch 2 Cycle 24.
Discussion Page 9 of 24
Non-Proprietary Information-Class I (Public) 3.0 References
- 1. Letter, Glen A. Watford (GNF-A) to NRC Documnent Control Desk with attention to R.
Pulsifer (NRC), "'Confirmation of l0xl0 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 Applicability of the GEXLI4 Correlation and Associated R-Factor Methodology for Calculating SLMCPR Values in Cores Containing GEI4 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. (NRC), "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 IOXIO Fuel," FLN-2003-005.,
May 31, 2003.
- 8.
Letter, Andrew A. Lingenfelter (GNF-A) to NRC Document Control Desk with cc to MC Honcharik (NRC), "Removal of Penalty Being Applied to GE14 Critical Power Correlation for Outlet Peaked Axial Power Shapes.," FLN-2007-03 1, 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 I1) and GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), NEDC-33270P, Revision 3,
March 2010," MFN 10-045, March 5, 2010.
References Page 10 of 24
Non-Proprietary Information - Class I (Public) 12 11 12 11 11 11 11 12 11 1
12 11 12 11 11 11 11 12 11 12 13 3
1 j 11 j 13 51 23 4
23 Fuel Type 13 11 1
3 4
1 1
4 3
1 U1 13 11 13 11 11 4
23 23 4
3 3
4 23 23 4
11 11 13 11 5
12 12 1
23 23 23 23 23 23 23 23 23 23 23 23 1
2 13 5
1222 1
2 23 D
2 3
22 24 4
1 16 13 131211 J 2312113 21 22 4
21 21 4
22 21 3
21 23 411 4
12 13 13 12 1
4 24 4
22 4
20 4
22 2
2 22 4
20 4
22 4
24 4
U112 13 11 23 23 21 22 4
22 2
22 1
22 22 1
22 21 22 22 21 23 23 11 12 11 4
23 22 3
4 22 1
22 1
20 2
2 20 1
22 1
22 4
3 22 23 4
11 12 11 1
23 1 2 2
2 22 1
20 2
20 20 2
20 1
22 2
20 21 1
23 23 1
11 10 3
23 23 2
22 4
22 1
20 4
22 2
2 22 4
20 1
22 4
22 2
23 23 3
12 14 4
4 23 23 4
22 1
20 2
22 2
21 21 2
22 2
20 1
22 4
23 23 4
4 14 11 11 2
22 2
20 2
21 2
2 21 2
20 2
22 2
21 2
23 3
1 11 51 1
3 23 2
21 2
22 2
20 2
21 2
2 21 2
20 2
22 2
21 2
23 3
1 11 04 4
4 23 23 4
22 1
20 2
22 2
21 21 2
22 2
20 1
22 4
23 23 4
4 14 02 3
23 23 2
22 4
22 1
20 4
22 2
2 22 4
20 1
22 4
22 2
23 23 3
12 1
0 23 22 1
20 2
20 20 2
20 1
22 2
20 21 1
23 23 1
11 02 11 4
23 22 3
4 22:
1 22 1
20 2
2 20 1
22 1
22 4
3 22 23 4
11 12 52 50 48 46 44 42 40 38 36 34 32 30 28 26 24 22 20 18 16 14 12 10 08 06 04 02 13 1 23 23 21 22 4
22 2
22 1
22 22 1
22 2
22 4
22 21 23 23 11 12 1
4 24 4
22 4
20 4
22 2
2 22 4
20 4
22 4
24 11 12 3
21 22 4
21 21 4
22 21 3
21 23 4
1 2
13 13 14 2211 2231 2 2
1 22 24 [
1 j6 13 11 13]
15 13 12U 23 23 23 23 23 23 23 23 23 23 23 23 1
12 13 5
23 23 23 23 23 23 23 23 1
4-4-4 I -
1-i-I -
+ -
+ -
+ -
P -
I -
I -
I-I--I I-
+ -
23 23 23 23 11 11 13 1 ýI 11 4 23 23 4
3 3
4 23 23 4
11 11 13 11 1
11 3
4 1
I 4
3 1
ý1 13 12 11 12 11 11 11 11 12 11 12 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 Bundle Name GE14-P10NNAB393-14GZ-100T-150-T6-4182 GE14-P 10DNAB406-18GZ-10OT-150-T6-4183 GE14-PIODNAB418-16GZ-10oT-150-T6-4184 GE14-PIODNAB423-15GZ-looT-150-T6-4185 GE14-PIODNAB398-4G7.O/llG6.0/1G2.0-1OOT-150-T6-2620 GE14-P lODNAB419-16GZ-100T-150-T6-3392 GE14-P 1ODNAB395-14GZ-10oT-150-T6-3391 GE14-P 10DNAB402-15GZ-looT-150-T6-3389 GE14-P10DNAB423-15GZ-10oT-150-T6-2876 GNF2-P10DG2B401-14GZ-100T2-150-T6-3394 GE14-P 10DNAB423-15GZ-100T-150-T6-2876 GN F2-P10DG2B398-15GZ-100T2-150-T6-4314 GN F2-P10DG2B402-14GZ-10OT2-150-T6-4315 GN F2-P10DG2B40O-13GZ-10OT2-150-T6-4316 GN F2-P10DG2B411-14GZ-100T2-150-T6-4317 GN F2-P10DG2B411-14GZ-10OT2-150-T6-4317 Fuel Type 1
2 3
4 5
11 12 13 14 16 19 20 21 22 23 Cycle Loaded 23 23 23 23 24 Thrice burned bundles reinserted for Cycle 24 22 22 22 22 22 23 24 24 24 24 24 24 Figure 1. Current Cycle Core Loading Diagram Figure 1. Current Cycle Core Loading DiagramP Pace I11 of 24
Non-Proprietary Information-Class I (Public) 9 7
j 7 j 7
7 j
7 j
7 j
7 j
7 j
9 FuelType 9
9 12 7
11 113 13 11 7
12 9
9 7I 7 7 7
11 4
12 3
4 4
3 12 4
11 9
7 7
7 9
7 11 7
14 4
4 4
3 13 13 3
4 4
4 14 7
1 7
9 77I164iI1 43413 21112121112+/-T13[~1 4+/-344~1679~
7 11 7
1 1
31 13 4
11 4
14 11 7
9 7
4 4
11 2
1 13 12 2
13 13 2
12 13 1
2 11 4
4 7
7 9
8 11 3
13 2
11 1 13 2
12 1
1 12 2
13 1
1 1 ý 9
9 7
11 4
4 11 1
1 11 1
12 1
13 13 1
12 1
11 1
1 11 4
4 11 7
9 7
19 4
4 13 2
13 13 1
17 1
12 1
1 12 1
17 1
13 13 2
13 4
4 12 7
8 7
12 4
2 11 12 2
12 1
17 1
17 17 1
17 1
12 2
12 11 2
4 12 7
8 7
11 3
3 11 2
2 12 1
12 1
17 2
2 17 1
12 1
12 2
2 11 3
3 11 1
8 12 4
113 2
11 13 1
13 1
17 2
17 17 2
17 1 113 1
13 11 2
13 4
13 7
9 13 4
13 2
11 13 1
13 1
17 2
17 17 2
17 1
13 1
13 11 2
13 4
13 7
8 11 3
3 11 2
2 12 1
12 1
17 2
2 17 1
12 1
12 2
2 11 3
3 11 7
8 7
12 4
2 11 12 2
12 1
17 1
17 17 1
17 1
12 2
12 11 2
4 12 7
7 7
12 4
4 13 2
13 13 1
17 1
12 1
1 12 1
17 1
13 13 2
13 4
4 12 7
9 9
11 4
4 11 1
1 11 1
12 1
3 13 1
12 1
11 1
1 1
4 4_
1 9
8 11 3 13 I 2 11 1
13 2
12 1
1 12 2
13 1
11 2
13 3
11 It 9
7 7
4 4
11 2
j 13 12 2
13 1 132 1
2 12 13 1
2 11 4
4 7
9 7J 11 4]1 H4 13 [11 [2 1112 11{11J 21111 2 111 13 4111 [4 [11[7 7j 716 4
3 [4 1 3:[2 [111212111 2
13 j 4
4 11 9
7 11 7
14 4
4 4
3 13 13 3
4 4
4 14 7
11 8
9 81717 8 11 4
12 3
4 4
3 12 4
11 7
717 9
7 12 7
11 13 13 11 7
12 7
9 7
7 7
7 7
7 7
9 718 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 Bundle Name Fuel Type Cycle Loaded GE14-P10DNAB393-14GZ-100T-150-T6-4182 1
23 GE14-P1ODNAB406-18GZ-100T-150-T6-4183 2
23 GE14-P1ODNAB418-16GZ-10OT-150-T6-4184 3
23 GE14-P ODNAB423-15GZ-100T-150-T6-4185 4
23 GE14-P1ODNAB423-15GZ-100T-150-T6-2876 7
21 GE14-PIODNAB413-14G6.O-100T-150-T6-2949 8
21 GE14-P10DNAB413-15G6.0-100T-150-T6-2875 9
21 GE14-P10DNAB419-16GZ-100T-150-T6-3392 11 22 GE14-P10DNAB395-14GZ-10OT-150-T6-3391 12 22 GE14-P10DNAB402-15GZ-100T-150-T6-3389 13 22 GE14-P1ODNAB423-15GZ-100T-150-T6-2876 14 22 GE14-P10DNAB421-15GZ-100T-150-T6-3016 15 22 GNF2-P1ODG2B401-14GZ-100T2-150-T6-3394 16 22 GE14-P1ODNAB381-14GZ-10OT-150-T6-3390 17 22 GE14-P10DNAB423-15GZ-100T-150-T6-2876 19 23 Figure 2. Previous Cycle Core Loading Diagram Figure 2. Previous Cycle Core Loading Diagram Page 12 of 24
Non-Proprietary Information-Class I (Public)
Figure 3. Figure 4.1 from NEDC-32601P-A Figure 3. Figure 4.1 from NEDC-32601P-A Page 13 of 24
Non-Proprietary Information-Class I (Public)
Figure 4. Figure 111.5-1 from NEDC-32601P-A Figure 4. Figure 111.5-1 from NEDC-32601P-A Page 14 of 24
Non-Proprietary Information-Class I (Public)
Figure 5. Relationship Between MIP and CPR Margin Figure 5. Relationship Between MIP and CPR Margin Page 15 of 24
Non-Proprietary Information - Class I (Public)
Table 1. Description of Core Previous Cycle Previous Cycle Current Cycle Current Cycle Description Minimum Core Flow Rated Core Flow Minimum Core Flow Rated Core Flow Limiting Case Limiting Case Limiting Case Limiting Case Number of Bundles in the 560 560 Core Limiting Cycle Exposure Point (i.e., Beginning of BOC (TLO)
Cycle (BOC)/Middle of EOC BOC (TLO)
EOC EOC Cycle (MOC)/End of EOC (SLO)
Cycle (EOC))
Cycle Exposure at Limiting Point 15,814 0/15,814 13,800 13,800 (MWd/STU)
% Rated Core Flow 92.9 100.0 92.9 100.0 Reload Fuel Type GE14 GNF2 Latest Reload Batch 40.0 40.0 Fraction, %
Latest Reload Average Batch Weight %
4.09 4.04 Enrichment Core Fuel Fraction, %:
GNF2 0.7 40.7 GE14 99.3 59.3 Core Average Weight %
4.09 4.07 Enrichment Table 1. Description of Core Page 16 of 24
Non-Proprietary Information-Class I (Public)
Table 2. SLMCPR Calculation Methodologies Previous Cycle Previous Cycle Current Cycle Current Cycle Description Minimum Core Flow Rated Core Flow Minimum Core Flow Rated Core Flow Limiting Case Limiting Case Limiting Case Limiting 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 3DMONICORE 3DMONICORE R-Factor Calculation NEDC-32505P-A NEDC-32505P-A Methodology Table 2. SLMCPR Calculation Methodologies Page 17 of 24
- M
Non-Proprietary Information - Class I (Public)
Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Previous Cycle Previous Cycle Current Cycle Current Cycle Description Minimum Core Flow Rated Core Flow Minimum Core Flow Rated Core Flow Limiting Case Limiting Case Limiting Case Limiting Case Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Page 18 of 24
Non-Proprietary Information - Class I (Public)
Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Previous Cycle Previous Cycle Current Cycle Current Cycle Description Minimum Core Flow Rated Core Flow Minimum Core Flow Rated Core Flow Limiting Case Limiting Case Limiting Case Limiting Case Requested Change to the Technical Specification N/A 1.09 (TLO)/ 1.12 (SLO)
((_
______________t_
Table 3. Monte Carlo Calculated SLMCPR vs. Estimate Page 19 of 24
Non-Proprietary Information - Class I (Public)
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
+_ (%)
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 Pressure 0.50 N/A N/A N/A N/A Measurement Core Inlet Temperature 0.20 N/A N/A N/A N/A Measurement Total Core Flow 6.0 SLO/2.5 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 NEDC-32601P-A Feedwater Flow Measurement Table 4. Non-Power Distribution Uncertainties Pacre 20 of 24 L__
Non-Proprietary Information - Class I (Public)
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
+/- ¢ (%)
Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case Feedwater Temperature R[
Er Measurement Reactor Pressure Measurement Core Inlet Temperature 0.2 0.2 0.2 0.2 0.2 Measurement Total Core Flow 6.0 SLO/2.5 TLO 6.0 SLO/2.691 TLO 6.0 SLO/2.5 TLO 6.0 SLO/2.691 TLO 6.0 SLO/2.5 TLO Measurement Channel Flow Area R
Er 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 Paue 21 of 24
Non-Proprietary Information - Class I (Public)
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-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_
NEDC-32694P-A, 3DMONICORE GEXL R-Factor E[
Er
((
))
((
))
E[
))
Random Effective 2.85 SLO/1.2 TLO 2.85 SLO/1.292 TLO 2.85 SLO/1.2 TLO 2.85 SLO/I.292 TLO 2.85 SLO/I.2 TLO TIP Reading TIP Integral
((
Er Er
((
))
((
]
Four Bundle Power Distribution Surrounding TIP
(([
Er
))
Location Contribution to Bundle Power Uncertainty Due to Local Power Range E[
))
Er
))
E
]
((
]
Monitor (LPRM)
Update Table 5. Power Distribution Uncertainties Page 22 of 24
Non-Proprietary Information - Class I (Public)
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 Contribution to Bundle Power Due to
((
))
[]
Failed TIP Contribution to Bundle Power Due to
((
((
))
Failed LPRM Total Uncertainty in Calculated Bundle
((
))
Er Power Uncertainty of TIP Signal Nodal 1]
Er
))
E[
Er Uncertainty Table 5. Power Distribution Uncertainties Page 23 of 24
Non-Proprietary Information - Class I (Public)
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
+/- g (%)
Flow Limiting Case Limiting Case Flow Limiting Case Limiting Case Table 6. Critical Power Uncertainties Page 24 of 24