ML14064A322
| ML14064A322 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/31/2014 |
| From: | Global Nuclear Fuel - Americas |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 00N0123-SRLR, Rev 2 | |
| Download: ML14064A322 (70) | |
Text
ATTACHMENT (1)
SUPPLEMENTAL RELOAD LICENSING REPORT FOR NINE MILE POINT 2 (NMP2), RELOAD 14 CYCLE. 15, EXTENDED POWER UPRATE (EPU)/ MAXIMUM EXTENDED LOAD LINE LIMIT PLUS (MELLLA+)
(00ON0123-SRLR)
Nine Mile Point Nuclear Station, LLC February 25, 2014
GNF Global Nuclear Fuel A Joint Venture of GE, Toshiba, & Hitachi 00NO123-SRLR Revision 2 Class I January 2014 Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2)
Reload 14 Cycle 15 Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Plus (MELLLA+)
Copyright2014 Global Nuclear Fuel-Americas,LLC All Rights Reserved
NINE MILE POINT 2 00ON0 i 23-SRLR Reload 14 Revision 2 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for use by Nine Mile Point Nuclear Station, LLC ("Recipient") in support of the operating license for NINE MILE POINT 2 (the "Nuclear Plant"). The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at the time this report was prepared.
The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use of the Information for any purpose other than that for which it was intended under the Fuel Contract, is not authorized by GNF-A. In the event of any such unauthorized use, GNF-A neither (a) makes any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness of the Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind which may result from such use of such information.
The content of this SRLR will only serve the Licensing of NMP2 C 15 EPU/MELLLA+.
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NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by GNF-A/GEH Nuclear Analysis personnel. The Supplemental Reload Licensing Report was prepared by M. Thomas. This document has been verified by R. McCord.
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NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Table of Contents I. Plant Unique Items 5
- 2. Reload Fuel Bundles 5
- 3. Reference Core Loading Pattern 6
- 4. Calculated Core Effective Multiplication and Control System Worth 6
- 5. Standby Liquid Control System Shutdown Capability 6
- 6. Reload Unique Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 7
- 7. Selected Margin Improvement Options 8
- 8. Operating Flexibility Options 9
- 9. Core-wide AOO Analysis Results' 10
- 12. Overpressurization Analysis Summary 16
- 13. Fuel Loading Error Results 17
- 14. Control Rod Drop Analysis Results 17
- 15. Stability Analysis Results 17
- 16. Loss-of-Coolant Accident Results 22 Appendix A Analysis Conditions 47 Appendix B Thermal-Mechanical Compliance 48 Appendix C Decrease in Core Coolant Temperature Event 49 Appendix D Off-Rated Limits 50 Appendix E Expanded Operating Domain Analyses 57 Appendix F TRACG04 AOO Supplementary Information 59 Appendix G Interim Methods LTR (NEDC-33173P-A Revision 4) Supplementary Information 60 Appendix H MELLLA+ LTR (NEDC-33006P-A Revision 3) Supplementary Information 63 Appendix I List of Acronyms 66 Page 4
NINE MILE POINT 2 000N0123-SRLR Reload 14 Revision 2 The basis for this report is General Electric StandardApplication for Reactor Fuel, NEDE-2401 I-P-A-19, May 2012; and the U.S. Supplement, NEDE-2401 1-P-A-19-US, May 2012.
A proprietary Fuel Bundle Information Report (FBIR) supplements this licensing report. The FBIR specifies the thermal-mechanical linear heat generation rate limits and also provides a description of the fuel bundles to be loaded. The document number for this report is 000N0123-FBIR.
- 1. Plant Unique Items Appendix A: Analysis Conditions Appendix B: Thermal-Mechanical Compliance Appendix C: Decrease in Core Coolant Temperature Event Appendix D: Off-Rated Limits Appendix E: Expanded Operating Domain Analyses Appendix F: TRACG04 AOO Supplementary Information Appendix G: Interim Methods LTR (NEDC-33173P -A Revision 4) Supplementary Information Appendix H: MELLLA+ LTR (NEDC-33006P - A Revision 3) Supplementary Information Appendix I: List of Acronyms
- 2. Reload Fuel Bundles FuelType Cycle Number Loaded Irradiated:
GE14-PIOCNAB434-8G7.0/7G6.0-120T-150-T6-3233 (GE14C) 13 80 GEI4-PIOCNAB416-17GZ-120T- 150-T6-3235 (GE14C) 13 12 GE 14-P 1OCNAB417-17GZ- 120T- 150-T6-3236 (GE 14C) 13 4 GE 14-PIOCNAB434-15GZ-120T- 150-T6-4039 (GEI4C) 14 120 GE 14-P 1OCNAB422-17GZ- 120T- 150-T6-4041 (GE 14C) 14 60 GE 14-P IOCNAB412-15GZ- 120T- I50-T6-4040 (GE 14C) 14 104 GE 14-P i OCNAB422-17GZ- 120T- 150-T6-4042 (GE 14C) 14 32 GE I4-P I OCNAB412-14GZ- 120T- 150-T6-4043 (GE 14C) 14 16 New:
GE 14-P IOCNAB422-16GZ- 120T- 150-T6-4244 (GE 14C) 15 64 GEI4-P1OCNAB418-16GZ-120T-150-T6-4243 (GE14C) 15 56 GE 14-P IOCNAB419-17GZ- 120T- 150-T6-4242 (GE 14C) 15 96 GE14-PIOCNAB418-15GZ-120T- 150-T6-4241 (GE14C) 15 56 GE 14-P 1OCNAB430-14GZ- 120T- 150-T6-4240 (GE 14C) 15 40 GE 14-P 1OCNAB430-15GZ- 120T- 150-T6-4239 (GE 14C) 15 24 Total: 764 Page 5
NINE MILE POINT 2 00ON01I23-SRLR P1I l,*0 l 1A
- 3. Reference Core Loading Pattern Core Average Cycle Exposure Exposure 34134 MWd/MT 18164 MWd/MT Nominal previous end-of-cycle exposure: (30966 MWd!ST) (16478 MWd/ST)
Minimum previous end-of-cycle exposure (for cold 33583 MWd/MT 17613 MWd/MT shutdown considerations): (30466 MWd/ST) (15978 MWd/ST) 14094 MWd/MT 0 MWd/MT Assumed reload beginning-of-cycle exposure: (12786 MWd/ST) (0 MWdIST)
Assumed reload end-of-cycle exposure (rated 33032 MWd/MT 18938 MWd/MT conditions): (29966 MWd/ST) (17180 MWd/ST)
Reference core loading pattern: Figure 1
- 4. Calculated Core Effective Multiplication and Control System Worth Beginning of Cycle, keffective Uncontrolled (20'C) 1.132 Fully controlled (20'C) 0.959 Strongest control rod out (most reactive condition, 20'C) 0.989 R, Maximum increase in strongest rod out reactivity during the cycle (Ak) 0.000 0 MWd/MT (0 MWd!ST)
Cycle exposure at which R occurs
- 5. Standby Liquid Control System Shutdown Capability Boron (ppm) Shutdown Margin (Ak)
(at 20(C) (at 160 0C, Xenon Free)
Analytical Requirement Achieved 780 >0.0 10 0.019 Page 6
NINE MILE POINT 2 00ON0123-SRLR t?.1nA Id
- 6. Reload Unique Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 1 Operating domain: ICF (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 3)
Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow
__esign__ _(MWt) (1000 lb/hr) MCPR GEI4C 1.0 1.36 1.27 0.98 7.071 126.5 1.59 Operating domain: ICF (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 3)
Exposure range_: BOC to EOC ( Application Condition: 2 )
Peaking Factors Fuel Bundle Bundle Initial Local Radial Axial R-Factor Power Flow Design (MWt) (1000 lb/hr) MCPR GE14C 1.0 1.37 1.42 0.97 7.147 128.1 1.51 Operating domain: LCF (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 3)
Peaking Factors Fuel Bundle Bundle Initial Design Design__ Local Radial Axial R-Factor
__(MWt)
Power Flow (1000 lb/hr) MCPR GE14C 1.0 1.36 1.29 0.97 7.065 100.8 1.48 Operating domain: LCF (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 3)
Exposure range_: BOC to EOC (Application Condition: 2 )
Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR 13 0.8 72(MWt) (1000 .b/hr)
GE14C 1.0 1.38 1.34 0.98 7.217 100.8 1.38 Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.
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NINE MILE POINT 2 00ON0123-SRLR I* .,*-A 1A Operating domain: ICF (UB)
Exposure range : MOC to EOC (Application Condition: 1, 3)
Exposure range : BOC to EOC (Application Condition: 2 )
Peaking Factors Fuel Bundle Bundle Initial Local Radial Axial R-Factor Power Flow Design (MWt) (1000 lb/hr) MCPR GEI4C 1.0 1.28 1.26 0.97 6.674 129.4 1.73 Operating domain: LCF (UB)
Exposure range : MOC to EOC ( Application Condition: 1, 3)
Exposure range : BOC to EOC (Application Condition: 2 )
Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Design__ __(MWt) (1000 lb/hr) MCPR GEI4C 1.0 1.31 1.22 0.97 6.833 101.6 1.57
- 7. Selected Margin Improvement Options 2 Recirculation pump trip: Yes Rod withdrawal limiter: No Thermal power monitor: Yes Improved scram time: Yes (Option B)
Measured scram time: No Exposure dependent limits: Yes Exposure points analyzed: 2 2 Refer to the GESTAR basis document identified at the beginning of this report for the margin improvement options currently supported therein.
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NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Table 7-1 Cycle Exposure Range Designation Name Exposure Range 3 BOC to MOC BOC 15 to EORI5-2816 MWd/ST MOC to EOC EORI 5-2816 MWd/ST to EOC 15 BOC to EOC BOC15 to EOCI5
- 8. Operating Flexibility Options 4 The following information presents the operational domains and flexibility options which are supported by the reload licensing analysis.
Extended Operating Domain (EOD): Yes EOD type: Maximum Extended Load Line Limit Plus (MELLLA+)
Minimum core flow at rated power: 85.0 %
Increased Core Flow: Yes Flow point analyzed throughout cycle: 105.0%
Feedwater Temperature Reduction: No ARTS Program: Yes Single Loop Operation: Yes Equipment Out of Service:
Safety/relief valves Out of Service: Yes (credit taken for 16 valves)
ADS Out of Service: Yes Turbine Bypass Valve Out of Service Yes End Of Cycle Recirculation Pump Trip Out of Service Yes Main Steam Isolation Valve Out of Service Yes Pressure Regulator Out of Service Yes 3 End of Rated (EOR) is defined as the cycle exposure corresponding to all rods out, 100% power/100% flow, and normal feedwater temperature. For plants without mid-cycle OLMCPR points, EOR is not applicable.
4 Refer to the GESTAR basis document identified at the beginning of this report for the operating flexibility options currently supported therein.
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NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 56
Exposure range : BOC to MOC (Application Condition: 1, 3)
Uncorrected ACPRIICPR Event Flux STP
(% rated) (% rated) GEI4C Fig.
Load Rejection w/o Bypass 545.9 110.0 0.2088 2 FW Controller Failure 517.1 112.4 0.2001 3 Operating domain: ICF (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 3)
Exposure range : BOC to EOC (Application Condition: 2 )
Uncorrected ACPRIICPR Event Flux STP
(% rated) (% rated) GEI4C Fig.
Turbine Trip w/o Bypass 614.5 110.8 0.2139 4 FW Controller Failure 569.0 113.4 0.2108 5 Operating domain: LCF (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 3 )
Uncorrected ACPRIICPR Event Flux STP Event_____________(% rated) (% rated) GEI4C Fig.
Load Rejection w/o Bypass 436.7 108.4 0.2026 6 FW Controller Failure 367.9 110.3 0.1890 7 5 The 6 Exposure Heat range Q/A Flux, designation is output
(% rated) definedisinnot Table 7-1. Application available condition from TRACG04, number so the is defined Simulated in Section Thermal 11.
Power (STP) (%
rated) is shown.
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NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Operating domain: LCF (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 3)
Exposure range : BOC to EOC (Application Condition: 2 )
Uncorrected ACPR/ICPR Event Flux STP
(% rated) (% rated) GEI4C Fig.
Load Rejection w/o Bypass 481.1 109.3 0.2053 8 FW Controller Failure 1 413.9 111.4 0.1924 9 Operating domain: ICF with TBVOOS (HBB)
Exposure range : BOC to EOC (Application Condition: 2)
Uncorrected ACPR/ICPR Event Flux STP G
(% rated) (% rated) GEl4C Fig.
FW Controller Failure 675.9 114.9 0.2294 10 Operating domain: LCF with TBVOOS (HBB)
Exposure range : BOC to EOC (Application Condition: 2)
Uncorrected ACPR/ICPR Event Flux STP G1CFg Event (%rtd Prtd)j GE14C Fig.
(% rated) (% rated FW Controller Failure 495.3 112.9 0.2171 11 Operating domain: ICF with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 3)
Uncorrected ACPRIICPR Event Flux STP Event_____________(% rated) (% rated) GE14C Fig.
Turbine Trip w/o Bypass 655.8 110.8 0.2249 12 FW Controller Failure 582.1 113.4 0.2156 13 Operating domain: [CF with RPTOOS (HBB)
Exposure range : MOC to EOC (Application Condition: 3)
Uncorrected ACPR/ICPR Event Flux STP Event_____________(% rated) (% rated) GEI4C Fig.
Load Rejection w/o Bypass 645.5 111.7 0.2475 14 FW Controller Failure 631.6 114.3 0.2280 15 Page 11
NINE MILE POINT 2 O00N0123-SRLR Reload 14 Revision 2 Operating domain: LCF with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 3)
Uncorrected ACPR/ICPR Event Flux STP Event_____________(% rated) (% rated) GEI4C Fig.
Load Rejection w/o Bypass 484.2 109.1 0.1995 16 FW Controller Failure 404.8 111.1 0.1877 17 Operating domain: LCF with RPTOOS (HBB)
Exposure range : MOC to EOC (Application Condition: 3)
Uncorrected ACPR/ICPR Event Flux STP Event_____________(% rated) (% rated) GEI4C Fig.
Load Rejection w/o Bypass 532.2 110.1 0.1994 18 FW Controller Failure 453.7 112.2 0.1870 19 Page 12
NINE MILE POINT 2 00ON0123-SRLR2 Reload 14 Revisin
- 10. Rod Withdrawal Error AO0 Summary The Rod Withdrawal Error (RWE) is analyzed in NEDC-33286P, Nine Mile Point Nuclear Station Unit 2 APRM/RBM/Technical Specifications / Maximum Extended Load Line Limit Analysis (ARTS/MELLLA),
Revision 0, March 2007.
RWE Results:
RBM Setpoint (%) ACPR 108.0 0.23 111.0 0.25 114.0 0.25 117.0 0.29 Unblocked 0.257 The more limiting of the cycle specific and the generic ACPR values are reported in the table above. The RWE OLMCPR is determined by adding the ACPR for the desired RBM setpoint from the table above to the SLMCPR in Section 11.
The ARTS RWE analysis validated that the following MCPR values provide the required margin for full withdrawal of any control rod during this cycle:
For Power < 90% MCPR > 1.70 For Power > 90% MCPR >_1.40 The RBM operability requirements have been evaluated and shown to be sufficient to ensure that the SLMCPR and cladding 1% plastic strain criteria will not be exceeded in the event of a RWE.
7The cycle specific unblocked response is used to validate the MCPR operating limits for a full withdrawal provided in the paragraph below the table.
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NINE MILE POINT 2 00ON0123-SRLR J? I I- A 1A ýv a v" 8 10
- 11. Cycle SLMCPR and OLMCPR Summary 9 Two Loop Operation (TLO) safety limit: 1.09 Single Loop Operation (SLO) safety limit: 1.09 Stability MCPR Design Basis: See Section 15 EGGS MCPR Design Basis: See Section 16 (Initial MCPR)
Non-pressurization Events:
Exposure range: BOG to EOC All Fuel Types Rod Withdrawal Error (117.0 % RBM Setpoint) 1.38 Loss of Feedwater Heating 1.23 Fuel Loading Error (Mislocated) Not Limiting Fuel Loading Error (Misoriented) 1.28 Rated Equivalent SLO Pump Seizure "1 1.34 Limitinga Pressurization Events OLMCPR Summary Table: 12 Appi.
Cond. Exposure Range Option A Option B GE14C GEI4C I Equipment in Service BOC to MOC 1.65 1.41 MOC to EOC 1.66 1.42 2 TBV OOS BOC to EOC 1.65 1.44 3 RPT OOS BOC to MOC 1.75 1.42 MOC to EOC 1.81 1.48 8 Exposure range designation is defined in Table 7-1.
9 For SLO, the MCPR operating limit is equal to the two loop value.
10The safety limit values presented include a 0.02 adder in accordance with extended operating domain licensing commitments.
" The cycle-independent OLMCPR for the recirculation pump seizure event for GEI4C is 1.47 based on the cycle-specific SLO SLMCPR. When adjusted for the off-rated power/flow conditions of SLO, this limit corresponds to a rated OLMCPR of 1.34. This limit does not require an adjustment for the SLO SLMCPR.
12 Each application condition (Appl. Cond.) covers the entire range of licensed flow and feedwater temperature unless specified otherwise. The OLMCPR values presented apply to rated power operation based on the two loop operation safety limit MCPR.
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NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revisinn 2 Pressurization Events: 13 Operating domain: ICF (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 3 )
Option A Option B GE14C GE14C Load Rejection w/o Bypass 1.63 1.39 Operating domain: ICF (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 3)
Exposure range : BOC to EOC (Application Condition: 2 )
Option A Option B GE14C GE14C Turbine Trip w/o Bypass 1.64 1.40 Operating domain: LCF (HBB)
Exposure range : BOC to MOC (Application Condition: 1, 3)
Option A Option B GE14C GE14C Load Rejection w/o Bypass 1.65 1.41 Operating domain: LCF (HBB)
Exposure range : MOC to EOC (Application Condition: 1, 3)
Exposure range : BOC to EOC (Application Condition: 2 )
Option A Option B GE14C GE14C Load Rejection w/o Bypass 1.66 1.42 Operating domain: ICF with TBVOOS (HBB)
Exposure range : BOC to EOC (Application Condition: 2)
Option A Option B GE14C GE14C FW Controller Failure 1.65 1.44 3 Application condition numbers shown for each of the following pressurization events represent the application conditions for which this event contributed in the determination of the limiting OLMCPR value.
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NINE MILE POINT 2 00ON01I23-SRLR DIA,-,A I -
1A Operating domain: LCF with TBVOOS (HBB)
Exposure range : BOC to EOC (Application Condition: 2)
Option A Option B GE14C GE14C FW Controller Failure 1.65 1.44 Operating domain: ICF with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 3)
Option A Option B GE14C GE14C Turbine Trip w/o Bypass 1.75 1.42 Operating domain: ICF with RPTOOS (HBB)
Exposure range : MOC to EOC (Application Condition: 3 )
Option A Option B GE14C GE14C Load Rejection w/o Bypass 1.81 1.48 Operating domain: LCF with RPTOOS (HBB)
Exposure range : BOC to MOC (Application Condition: 3)
Option A Option B GE14C GE14C Load Rejection w/o Bypass 1.74 1.41 Operating domain: LCF with RPTOOS (HBB)
Exposure range : MOC to EOC (Application Condition: 3)
Option A Option B GE14C GE14C Load Rejection w/o Bypass 1.73 1.40
- 12. Overpressurization Analysis Summary 14 Pdome (psig) Pv (psig) Plant
Response
MSIV Closure (Flux Scram) - ICF (HBB) 1277.9 1313.4 Figure 20 MSIV Closure (Flux Scram) - LCF (HBB) 1277.9 1307.0 Figure 21 14Overpressure calculated at an initial dome pressure of 1020 psig.
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NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2
- 13. Fuel Loading Error Results Variable water gap misoriented bundle analysis: Yes 15 Misoriented Fuel Bundle ACPR GE 14-P 10CNAB434-15GZ- 120T- I50-T6-4039 (GE 14C) 0.16 GE 14-P 10CNAB422-17GZ- 120T- 150-T6-4041 (GE i 4C) 0.17 GE 14-P I0CNAB412-15GZ- 120T- 150-T6-4040 (GE I4C) 0.17 GE 14-P 1OCNAB422-17GZ- 120T- 150-T6-4042 (GE I4C) 0.17 GE 14-P 1OCNAB412-14GZ- 120T- I50-T6-4043 (GE I 4C) 0.17 GE 14-P 1OCNAB430-15GZ- 120T- 150-T6-4239 (GE I4C) 0.19 GE 14-P 1OCNAB430-14GZ- 120T- I50-T6-4240 (GE I4C) 0.17 GE 14-P 1OCNAB418-15GZ- 120T- 150-T6-4241 (GE 14C) 0.18 GE 14-P IOCNAB419-17GZ- 120T- I50-T6-4242 (GE I4C) 0.19 GE 14-P 1OCNAB418-I 6GZ- 120T- I50-T6-4243 (GE I4C) 0.19 GE 14-P 1OCNAB422-16GZ- 120T- I50-T6-4244 (GE I4C) 0.19
- 14. Control Rod Drop Analysis Results Nine Mile Point Unit 2 is a banked position withdrawal sequence plant, so the control rod drop accident analysis is not required. NRC approval is documented in NEDE-2401 1-P-A-US.
- 15. Stability Analysis Results Nine Mile Point Unit 2 is licensed to operate in the MELLLA+ operating domain. Operation within the MELLLA+ operating domain requires the use of the Detect and Suppress Solution - Confirmation Density (DSS-CD) stability solution. Stability results for operation at EPU with MELLLA+ and DSS-CD are contained in this section.
15.1 Stability DSS-CD Solution Nine Mile Point Unit 2 implements the stability DSS-CD solution using the Oscillation Power Range Monitor (OPRM) as described in Reference I in Section 15.4. Plant-specific analyses for the DSS-CD Solution are provided in Reference 2 in Section 15.4. The Detect and Suppress function of the DSS-CD 15 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.
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NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 solution based on the OPRM system relies on the Confirmation Density Algorithm (CDA), which constitutes the licensing basis. The Backup Stability Protection (BSP) solution may be used by the plant in the event that the OPRM system is declared inoperable.
The CDA, enabled through the OPRM system, and the BSP solution described in Reference 2 in Section 15.4 provide the stability licensing bases for Nine Mile Point Unit 2 Cycle 15. The safety evaluation report for Reference I in Section 15.4 concluded that the DSS-CD solution is acceptable subject to certain limitations and conditions. These limitations and conditions are met for Nine Mile Point Unit 2 Cycle 15.
15.2 Detect and Suppress Evaluation A reload DSS-CD evaluation has been performed in accordance with the licensing methodology described in Reference 1 in Section 15.4 to confirm the Amplitude Discriminator Setpoint (SAD) of the CDA established in Reference 2 in Section 15.4. The Nine Mile Point Unit 2 Cycle 15 DSS-CD evaluation and the results for the DSS-CD Reload Confirmation Applicability Checklist documented in Table 15-1 demonstrate that: 1) the DSS-CD Solution is applicable to Nine Mile Point Unit 2 Cycle 15; and, 2) the SAD= 1 . 10 established in Reference 2 in Section 15.4 is confirmed for operation of Nine Mile Point Unit 2 Cycle 15.
The SAD=I. 1 0 setpoint is applicable to TLO and to SLO. The SAD=1'* 0 setpoint is applicable for a rated feedwater temperature equal to or greater than 420.5°F in the MELLLA+ domain per Reference 2 in Section 15.4.
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NINE MILE POINT 2 00ON0 i 23-SRLR Reload 14 Revision 2 Table 15-1 DSS-CD Reload Confirmation Applicability Checklist Parameter DSS-CD Criterion Nine Mile Point Unit Acceptance 2 Cycle 15 Results BWR Product Line BWR/3-6 design BWR/5 Confirmed Fuel Product Line GE14 and earlier GE designs GE14 Confirmed EPUIMELLLA+
Operating Domain <EPU/MELLLA+ including including currently Confirmed (TLO) currently licensed operational licensed operational flexibility features flexibility features EPU/MELLLA Operating Domain c EPU/MELLLA including including currently Confirmed (SLO) currently licensed operational licensed operational flexibility features flexibility features
< 120-F (EPU/MELLLA)
Rated TFw Reduction No TFw Reduction No TFw Reduction Confirmed (MELLLA+ Extension)
Margin for TLO (see Table 2-5 in see Table 2-5 in Reference 2 0.23 Confirmed Reference 2 in Section in Section 15.4 15.4)
Margin for SLO (see Table 2-5 in see Table 2-5 in Reference 2 0.31 Confirmed Reference 2 in Section 15.4 15.4) 15.3 Backup Stability Protection Reference I in Section 15.4 describes two BSP options that are based on selected elements from three distinct constituents: BSP Manual Regions, BSP Boundary, and Automated BSP (ABSP) setpoints.
The Manual BSP region boundaries and the BSP Boundary were calculated for Nine Mile Point 2 Cycle
- 15. The endpoints of the regions are defined in Table 15-2. The Scram Region boundary, the Controlled Entry Region boundary, and the BSP Boundary are shown in Figure 22.
The ABSP APRM Simulated Thermal Power setpoints associated with the ABSP Scram Region are provided for Cycle 15 and are defined in Table 15-3. These ABSP setpoints bound both TLO and SLO.
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NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 The BSP Boundary and the Manual BSP region boundaries for normal feedwater temperature operation are adequate to bound a variation in normal feedwater temperature of-20'F.
Table 15-2 BSP Endpoints for Normal Feedwater Temperature Enpont Endpoint Power
(%) Flow
(%) Definition Scram Region Boundary, HFCL Scram Region B1 39.7 29.5 BonayNC Boundary, NCL Controlled Entry A2 64.5 50.0 Region Boundary, HFCL B2 27.5 28.9 Controlled Entry Region Boundary, NCL BSP Boundary Intercept, HFCL BSP Boundary B3 74.0 55.0 Intercept, MELLLA+
Boundary Minimum Flow Table 15-3 ABSP Setpoints Parameter Symbol Value Slope of ABSP APRM flow-biased trip linear segment.
ABSP APRM flow-biased trip setpoint power intercept.
Constant Power Line for Trip PBSP-TRIP 39.7 %RTP from zero Drive Flow to Flow Breakpoint value.
ABSP APRM flow-biased trip setpoint drive flow intercept. WBSP-TRIP 36.9 %RDF Constant Flow Line for Trip.
Flow Breakpoint value WBSP-BREAK 16.4 %RDF Page 20
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 15.4 References
- 1. GE Hitachi Boiling Water Reactor Detect and Suppress Solution-ConfirmationDensity, Licensing Topical Report, NEDC-33075P-A, Revision 8, November 2013.
- 2. Safety Analysis Reportfor Nine Mile Point Unit 2 Maximum Extended Load Line Limit Analysis Plus, NEDC-33576P, Revision 0, October 2013.
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NINE MILE POINT 2 000N0 I23-SRLR Reload 14 Revision 2
- 16. Loss-of-Coolant Accident Results 16.1 10CFR50.46 Licensing Results The ECCS-LOCA analysis is based on the SAFER/PRIME-LOCA methodology. NRC approval of the PRIME methodology is contained in the Final Safety Evaluation of the PRIME model Licensing Topical Report provided in Section 16.4, Reference 2. The licensing basis results applicable to GE14C fuel type in the new cycle are summarized in the following table.
Table 16.1-1 Licensing Results Core-Wide Licensing Local Me-Wate Fuel Type Basis0 PCT Oxidation Reatio
( F) (OF) (%) Reaction
(%)
GEI4C 1580 < 1.00 < 0.10 The SAFER/PRIME ECCS-LOCA analysis results for GE14C fuel type are documented in Section 16.4, Reference I.
For GE14C, the small break Appendix-K ECCS-LOCA result at EPU power and rated core flow is 1561 °F as documented in Reference 1.
16.2 10CFR50.46 Error Evaluation All ECCS-LOCA errors up to 2011-03 and the SAFER/PRIME methodology are addressed in Section 16.4, Reference 1. Hence, there are no errors applicable to the new cycle for GE14C fuel type. The Licensing Basis PCT remains below the 10 CFR 50.46 limit of 2200 'F.
16.3 ECCS-LOCA Operating Limits The ECCS-LOCA MAPLHGR operating limits for GE14C fuel bundles in this cycle are shown in the following table.
Page 22
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Table 16.3-1 MAPLHGR Limits Bundle Type(s): GE 14-P 1OCNAB434-8G7.0/7G6.0-120T- 150-T6-3233 (GE 14C)
GEl 4-P1OCNAB416-17GZ-120T-150-T6-3235 (GEI4C)
GE 14-P 1OCNAB417-17GZ- 120T- I50-T6-3236 (GE 14C)
GE 14-P 1OCNAB434-15GZ- 120T- 150-T6-4039 (GE 14C)
GE 14-P 1OCNAB422-17GZ- 120T- 150-T6-4041 (GE 14C)
GE 14-P 10CNAB412-15GZ- 120T- I50-T6-4040 (GE I4C)
GE 14-P 1OCNAB422-17GZ- 120T- 150-T6-4042 (GE I4C)
GE 14-P 1OCNAB412-14GZ- 120T- I50-T6-4043 (GE I4C)
GE 14-P 1OCNAB430- I 5GZ- 120T- I50-T6-4239 (GE I4C)
GE 14-P 1OCNAB430-14GZ- 120T- I50-T6-4240 (GE I4C)
GE 14-P 1OCNAB418-15GZ- 120T- 150-T6-4241 (GE 14C)
GE14-PIOCNAB419-17GZ-120T- 150-T6-4242 (GEl4C)
GE 14-P 1OCNAB418-16GZ- 120T- I50-T6-4243 (GE I4C)
GE 14-P 1OCNAB422-16GZ- 120T- 150-T6-4244 (GE I4C)
Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 16.00 14.51 12.82 21.09 19.13 12.82 63.50 57.61 8.00 70.00 63.50 5.00 The MAPLHGR limits for GE14C fuel, shown in Table 16.3-1, are unaffected by changes to the LHGR curve being implemented in the new cycle.
The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for the off-rated conditions from an ECCS-LOCA analysis perspective. The MAPLHGR multipliers can either be set to unity, or, set equal to the LHGR multipliers, which remain compliant with the basis of the ECCS-LOCA analysis with no loss of ECCS-LOCA margin.
The single loop operation multiplier on LHGR and MAPLHGR and the ECCS- LOCA analytical initial MCPR value applicable to the GE14C fuel type in the new cycle core are provided in the following table.
Page 23
NINE MILE POINT 2 00ON0123-SRLR
]?ýl-A 1A D ; 1 Table 16.3-2 Initial MCPR and Single Loop Operation Multiplier on LHGR and MAPLHGR Single Loop Operation Fuel Type Initial MCPR Multiplier on LHGR and MAPLHGR GE14C 1.25 0.78 The GE14C Single Loop Operation (SLO) multiplier applies to the EPU/MELLLA operating domain only. SLO operation in the MELLLA+ domain is prohibited.
16.4 References The MELLLA+ SAFER/PRIME ECCS-LOCA analysis base reports applicable to the new cycle core are:
References for GE14C
- 1. Supplemental Project Task Report Constellation Energy Nuclear Group Nine Mile Point Nuclear Station Unit 2 MELLLA+ Task T0407: ECCS-LOCA SAFER/PRIME, 0000-0162-4214-RO, Revision 0, August 2013.
- 2. Licensing Topical Report, Global Nuclear Fuel: The PRIME model for Analysis of Fuel Rod Thermal-Mechanical Performance, Technical Bases - NEDC-33256P-A, Rev. 1, Qualification - NEDC-33257P-A, Rev. 1, and Application Methodology - NEDC-33258P-A, Rev. 1, September 2010.
Page 24
NINE MILE POINT 2 00N01 23-SRLR Reload 14 Revision 2 7 7 9 10 10 13 16 15 16 20 14 20 20 18 7 7 7 12 20 10 11 7 7 7 12 20 11 18 15 12 7 8 13 16 13 17 10 20 16 13 8 7 10 16 20 17 13 17 20 20 16 10 7 7 10 15 14 10 17 10 18 14 15 10 7 7 10 16 20 18 10 17 10 20 16 10 7 a 10 15 12 10 19 11 18 12 15 10 8 7 10 16 18 18 12 19 12 18 16 10 7 7 10 16 12 11 19 12 18 12 16 10 7 7 13 12 19 19 12 19 12 19 12 13 7 7 13 12 19 19 12 19 12 19 12 13 7 7 10 16 12 11 19 12 18 12 16 10 7 7 10 16 18 18 12 19 12 18 16 10 7 8 10 15 12 10 19 11 18 12 15 10 8 7 10 16 20 18 10 17 10 20 16 10 7 7 10 15 14 10 17 10 18 14 15 10 7 7 10 16 20 17 13 17 20 20 16 10 7 8 13 16 13 17 10 20 16 13 8 7 12 20 11 18 15 12 7 7 7 12 20 10 11 7 7 20 20 18 7 16 20 14 13 16 15 9 10 10 7 7 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 Fuel Type 7=GE14-PIOCNAB434-8G7.0/7G6.0-120T-I 50-T6-3233 (Cycle 13) 14=GE14-PlOCNAB412-14GZ-120T-150-T6-4043 (Cycle 14) 8=GEl4-PIOCNAB416-I7GZ-l20T-1 50-T6-3235 (Cycle 13) 15=GE14-PIOCNAB430-I5GZ-120T-150-T6-4239 (Cycle 15) 9=-GEI4-PIOCNAB417-17GZ-120T-150-T6-3236 (Cycle 13) I6=GEI4-PIOCNAB430-I4GZ-I20T-1 50-T6-4240 (Cycle 15) 10=GE14-PIOCNAB434-15GZ-120T-150-T6-4039 (Cycle 14) 17=GEI4-PIOCNAB418-15GZ-120T-150-T6-4241 (Cycle 15)
I 0=GE14-PIOCNAB422-17GZ-120T-150-T6-4041 (Cycle 14) I8=GEI4-PIOCNAB4I9-l7GZ-I20T-1 50-T6-4242 (Cycle 15) 12=GE I4-P IOCNAB412-15GZ- 120T- I 50-T6-4040 (Cycle 14) 19=GE14-PIOCNAB418-16GZ-120T-150-T6-4243 (Cycle 15) 13=GEI4-PIOCNAB422-17GZ-120T-150-T6-4042 (Cycle 14) 20=GE14-PIOCNAB422-16GZ-120T-150-T6-4244 (Cycle 15)
Figure 1 Reference Core Loading Pattern Page 25
NINE MILE POINT 2 OOONO I23-SRLR Reload 14 Revision 2 LRNBP ICF-TNMI-EIS KG6 15 140 700 80 1400 600 70 1350 120 60 1300 100 500 1250 ir 400 40%
at80 1200 3 wt30 1150!
so 40 200 20 1100 20 100 10 1050 0 0 1000 0 1 2 3 4 5 a 0 1 2 3 4 5 6 Tkm (fse) Tin- (-)
60 4.0
- St-- Flow
- Twbme Stem Flow 3.5 120 50 3.0 S 2.5 80 40b 220
- 1.5 j40 30 1.0 0 201 0.0
- -0.5
-o.0
-40 10 -1.0
-1 5 0 1 2 3 4 5 6 0 1 2 3 4 5 a Tonis (se)Ti is(see)
Figure 2 Plant Response to Load Rejection w/o Bypass (MOC ICF (HBB))
Page 26
NINE MILE POINT 2 00ON0123-SRLR
ý-*l~oA IA I 11 1)
FWCF ICF-TNMI-EIS KO1 Is 140 560 480 1300 400 1200~
x80 320 ,
At s0 240 1100 160 so 1o0o 0 5 10 15 20 0 5 10 15 20 Tim, (see) Time (in) 160 100 4.0 vwi~ R" Tota N.eadfy riFlow Scram Racetty 140 oStasm FRow 90 3.5 -- Doppler Temperature Reacht~t NRl row' -- vow Readctk4y 3.0 120 80 X 2.5 1::
I 100 7Q1 '2.0 10-so 60!
50 ! 1.0 160 40 40 I ~0-5
- io.o I
20- 30-
- . -0.5 0 20
-1.0
-20. 10 -1.5
-40 I I -11 0 -2.0 0 5 10 15 20 0 5 10 15 20 RLIJA,~
A¶AO~ rew (sec) Tie. (see)
Figure 3 Plant Response to FW Controller Failure (MOC ICF (HBB))
Page 27
NINE MILE POINT 2 00ON0123-SRLR
- Pýl-A 1A I? 11 ; . ;- I TTNBP ICFTNEO-EIS Kai 15 140 80 70 120 60 100 50 1250 40 1200 at
$60 30 1150 40 20 20 10 0 2 3 4 5 0 2 3 4 5 6 Tm (sc) Time (see) 160 60 4.0 3.5 120 50 3.0 ItS 2.5 80 40~
e2 .
4U 40, at 10.5 0 201 0.0
.0.5
-40 10 -1.0
-1.5
-80 0 -2.0 0 1 2 3 4 5 a 3
,- .p,* * ,ro Twme (sac) Trn (see)
Figure 4 Plant Response to Turbine Trip w/o Bypass (EOC ICF (HBB))
Page 28
NINE MILE POINT 2 00ON0123-SRLR
,1,*nA I A %IV a V11 FWCF lCFJTNE0-EIS KGt 4Is 140 700 600 1300 500 1200 j80 400 U
3001 1100 2DO 100 1000 0 5 10 15 20 Thiu (see) 160 100 4.0 140 3.5 8o 3.0 120 2.5 100 70 so so 60J j 60 40 50j 40 12,1.0 0.5 20 30~
10.0
-0.5 0 20
-1.0
-20 10 -1.5
-40 0 -2.0 0 10 10 20 Tr.n (uc) Tim. (sec)
Figure 5 Plant Response to FW Controller Failure (EOC ICF (HBB))
Page 29
NINE MILE POINT 2 00ON0123-SRLR Q,*,-*A 1A ev s on LRNBP MLP-TNMI-EIS KG1 IS 120 480 80 1360 70 1300 400 80 1250 320 i I so 1200k
=80 240 40 1150 30 1100 160 z 20 1050 so 1000 10 0 0 950 160 4.0 3.5 120 3.0 2.5 80 2.0 1.I 1.0 140 0.5 0 0.0
-0.5
-40 -1 0
-1.5
-2.0 0 1 3 6 raw (S")
Figure 6 Plant Response to Load Rejection w/o Bypass (MOC LCF (HBB))
Page 30
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 pwVcp MLP-TNMI-EIS KIs 140 40 120 1300 30 100 1200 I
80 20 At 60 1100 40 10 20 1000 0 0 10 15 20 10 15 20 Trm (See) Thiu (ts")
1w0 100 4.0 140 90 3.5 3.0 120 8o 2.5 100 70 2.0 t.5 80 60 40 40 08 10 0.0 20 30V
-0.5 20-j 0
-1 0
-20 10 -1.5
-40 0 -2.0 0 10 15 20 5 10 15 20 Tmf(mm) Tine (usw)
Figure 7 Plant Response to FW Controller Failure (MOC LCF (HBB))
Page 31
NINE MILE POINT 2 00ON0123-SRLR P1-*1 ,A 1A 0 v a1; w" )
LRNBP MLPTNEO-EIS Kai Is ow 560 80 1400
- oe-
- nl
--*- Si.umd Themel Power Neutm Fkux 70 1350 120 480 60 1300 100 2400 50 1250o 180 1200;
.240j 1 30 1150 z
40 160 20 1100 20 80 10 1050 0 0 0S 1000 0 1 2 3 4 5 6 0 1 2 3 4 5 6 a*(eec) (atmc)
T ek,
-1eem Fo 80 4.0
-- Stnw Flow
- Turbk Stown Flow 3.5 9-NR level 50 3.0 Z 2.S 40 22.0 1.5 V40 30 1.:
0 20 10.0
-0.5
-40 10 -1.0
-1.5 0 -2.0 0 2 3 4 5 6 0 2 3 4 5 6 Tim S(ec) Tin w(see)
Figure 8 Plant Response to Load Rejection w/o Bypass (EOC LCF (HBB))
Page 32
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 FWCF MLPTNEO-EIS KG1 15 140 CM Inlet Flow 40 1-- RV. SV, nd/WoSRVFIoW Swmilated Thwmw Poe Bypm V".. Flow
-- Newon Flux Vessel Dome Presse 120 480 1300 30 100 so
- 400 f 1 1l200 i.
80 320 020 at 80240j 11001 z
40 1S0 10 2080 1000 0 .... ... 4... 0 0 0 5 10 15 20 0 5 10 15 20 Tim. (s") Time (sec) 100 Feidll100 Rw 4.0 T__ Reecliufty
- Total
-SeFw-b-- Scram Reactivity 140 F 0 Doppler TeNRr*9 Recvy Void Revctvky 3.0 120 8O
. 2.5 100 70 j 80 60 1.5 050 1.0 40 40 0.5 0.0 20 30
-0.5 0 20
-1.0
-20 10
-40 , , , i , , , , , , 0 -2.0 ,. .
0 5 10 15 20 0 5 10 15 20
,,.-J.... Thu. (lee) Time lime)
Figure 9 Plant Response to FW Controller Failure (EOC LCF (HBB))
Page 33
NINE MILE POINT 2 000N0123-SRLR Reload 14 Revision 2 FWCF ICF TNEO-TBVOOS KG1 140 8o 1400 70 1350 120 80 1300 100 50 1250.
140 1200 60 30 11501 40 20 1100 20 10 1050 0 1000 0 5 10 15 20 0 5 10 15 20 Time (sac) Time (,,c) 140 100 4.0 120 go 3.5 3.0 100 so 2.5 70 -20 80 so U 40 20 0.5 10.0 30 i so 0.5 20
-1.0
-40{ 10 -1.5 0 -2.0 0 5 10 15 20 0 5 10 15 20
~(&CA*P
~UflS ~ ren (mc) Traw (69c)
Figure 10 Plant Response to FW Controller Failure (EOC ICF with TBVOOS (HBB))
Page 34
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 FWCF MLPTNEO-TBVOOS K91 15 140 *580 80 .V SVc ta400
.. Core InletFlow 5W 9 RV. SV,' W/o SRV Flow 10 Simulaed Thermal Power Bypass Valve Flow Neubon Flux Venal Dorm Pressure 120 - 480 70 1350 80- 1300 100- 400 50 1250 T
-280 EL~
S40 - 1200 it 60 240 1 a' M..
30 15 40 160 20 1100 20 480 10 1050 0 . . . . . .. . * . .0 0 . . . . . 1000 0 5 10 15 20 0 5 10 15 20 Uinm ("ec) Time ("ec) 140 Fted tr 100 4.0 -,- Total Reactiity Stelam Flow --- Scram ReacWily 120 Turbine Steam Flow go 3.5 - Ooppler Temperatre React-"ity
- NR lev I- Void Reac y 3.0 100 s0 800 72.
60 60 1.
4050 1.0 20 40 10.5
~g 0.0 0
30 K0.-0.5
-20 20
-1 0
-40 10 -1.5 0 5 10 15 20 0 5 10 15 20
.Tme (lec) Time (see)
Figure 11 Plant Response to FW Controller Failure (EOC LCF with TBVOOS (HBB))
Page 35
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 TTNBP ICF-TNMI-RPTOOS KG1 Is 140 700 80 1400
). 70 1350 120 800
), so 1300 100 400 1250 40 1200 300J 30 11501 40 200 20 1100 20 100 10 1050 0 0 0 1000 0 1 2 3 4 5 6 0 1 2 3 4 5 6 Tim (Ise) Tihm (uS) 160-, 60 120 50
~40 30 0
20,
-40 10 0
0 1 2 3 4 5 6 0 1 2 3 4 5 6 Tim. (se) Tim. (sec)
Figure 12 Plant Response to Turbine Trip w/o Bypass (MOC ICF with RPTOOS (HBB))
Page 36
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revirinn Revision 2 FWCF ICF-TNMI-RPTOOS KWI is 140 700 40 RV, SV. UIEoI SRV Flow
-- SimywletedThermal Power Bypass Velve Flow N-*"Weonnkxx,0x Vessel Dome Pressure 120 1300 30+
100-400 1200 s8
~ 20 aKs 300j '
11001 40 200 0 20 1 100 1000 0 1. .. 4 0 0 0 5 10 15 20 0 5 10 15 20 Thin (sac) Thie (sac) 100 100 4.0
-F*edwder Fkyw -e-Total Reseetlty
- Stean Flow -~Scramn Reoctlv*t 140 Turbine Stean Flow 3.5 -~Doppler Temperature Reactviay go 4 NRlevel '-Void fteacllMry 3.0 120 1 80
- " 2.5 100 70 S 2.0 110 60 1.:
50 . 1.0 40 40 40 0.5
- _. 10.0 20 -30
- 6 -0.5 0 20
-1.0
-20 S10 -1.5
-40 td 0 5 10 15 20 0 5 10 15 20
~~LQ%.fJ~
AV.'rein (Sec) Tie. (am)
Figure 13 Plant Response to FW Controller Failure (MOC ICF with RPTOOS (HBB))
Page 37
NINE MILE POINT 2 000N0123-SRLR Reload 14 Revision 2 LRNBP ICF.TNEO-RPTOOS KG1 11 140 C 700 100 WS W ___ 1450 SwmsAed Thermal Power -- Bypass Vule Flow Neuron Flnu 90 Vessel Dome Prese 1400 120 00 80 1350 100 500 70 1300 60 6800 12501 80/*4 1250j
~ 5o 1200j
- 860 -- 300E a aes 01 40 1150 1 z
40 200 30 1100 2 20 1050 20 100 10 1000 0 .. 0 090 0 1 2 3 4 5 8 0 1 2 3 4 5 6 Time (sec) Time (see) 1-00 F omrw 00 4.0 Total RsCdvky
- Steam Flow --- Scram, Re*atk Twbne Slem Flow 3.5 - Doppler Temperaur e Ree-tivty NoA.wl -- voi Reo a.y . ...
120 50 3.0 Z 2.5 so 40 9 2 ,0 1.5 40 30 -. 0
-0. -0.5
-40 10 -1.0
-80 I0 -2.0 0 1 2 3 4 5 6 0 1 2 3 4 5 6
~ Time (owa) Tame (eeC)
Figure 14 Plant Response to Load Rejection w/o Bypass (EOC ICF with RPTOOS (HBB))
Page 38
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 FWCF ICFTNEO-RPTOOS K101 15 140.-- or 700 80 10 140 Ca Inle Flow 700 s RV. sv. uwdfoSRkV Flow 10 Sinileted Th mmlPower BWy s Vefre Flow
-e- Vessel Dom Pressure 120 600 50 1260 100 500 40 1200
~ 30 1150 z 20 1100 40 200 10 1050 20 100 0 5 10 15 20 0 5 10 15 20 Thms(eec) Time (sac) 1600--- Feedder Rw 100 4.0 ToM Reactivty Stown Flow -. a- Scraiw Rowty 140Tbine Flow -3.5 Dopler Temperature Reactivity 1-NR* 90 - VoI Readiy 3.0 120 80
- " 2.5 100 701 80 60 60 50' 40 40 ! 0.-5 S 0.0 20 30
-0.5 0 20
-1.0
-20 10 -.
-40 : . . : . . . . 0 -2.0 0 5 10 1s 20 0 5 10 1s 20
.Tin (8e) Time (ae)
Figure 15 Plant Response to FW Controller Failure (EOC ICF with RPTOOS (HBB))
Page 39
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 LRNBP MLP-TNM1-RPT00S KG1 Is 140 80 1400 70 1350 120 6o 1300 100 50 1250 "11 140 1200 A 60 30 1150!
40 20 1100 20 10 1050 0 1000 0 1 2 3 4 5 a 0 1 2 3 4 5 6 Tim (sec) Trn* (sac) 100 - P~~Fedwr Flow s0 4.0 TS*= Flow
--*-- Steam Ftow 3.5
-- NA alow 120 50 3.0 L" 2.5 80 40_ 2 .0 40 301 1.:
0 20 0.0
- -0.5
-O.
-40 10 -1.0
-1.5 0 -2.0 0 1 2 3 4 5 a 0 1 2 3 5 a
,,:*-**.-,*,,*,,, Time (Sw) Tm. (s0C)
Figure 16 Plant Response to Load Rejection w/o Bypass (MOC LCF with RPTOOS (HBB))
Page 40
NINE MILE POINT 2 00ON0123-SRLR Rei1nnd 14 Rpevkinnc 9 Revision 2 FWCp MLP-TNM1-RPTOOS K(01 15 140 40 120 1300 30 100 1200 80 20 11001 2t0 10 40 1000 120 0 5 10 15 20 0 5 10 15 20 Thm (*) Thu. (see) 10 100 4.0 120 go 3.0 3.0 80 S 2.5 100 80 40 so 40 jo. 0-5 40 30 j 0.0
-0.5
-20 20
-1.0 10 -1.5
-40 0 -2.0 10 0 5 10 15 20 Tim(e) Tim. (Jac)
Figure 17 Plant Response to FW Controller Failure (MOC LCF with RPTOOS (HBB))
Page 41
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revkinin 2 Revision 2 LRNBP MLP-TNEO-RPTOOS KG1 15 140 80 1400 70 1350 120 so 1300 100 so 1250w 80 140 1200~
a60 30 11501 40 20 1100 20 10 1050 0 0 1000 2 3 4 5 6 a 1 2 3 4 5 6 Thu (sac) Time (eet) 160 80 4.0 3.5 120 50 3.0
- " 2.5 80 40 -20 I40 30O 1.0 0 20 0.0
-0.5
-40 10 -1.0
-1.5
-80 -.- :-: 0 -2.0 0 1 2 3 4 5 6 2 3 4 5 a Tine (eec) Tune (mec)
Figure 18 Plant Response to Load Rejection w/o Bypass
Page 42
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 9*
Revision 2 pWCF MLPJTNEO-RPTOOS KOI Is 140 40 120 1300 30 100 so 1200 ik 20 a'60 1100 40 10 20 1000 0 0 10 10 15 20 Tim (see) Tims (c) 160 F 100 4.0 l """*--
- Steam Flow 140 Tebmin Ste*m Flow go 3.5
-- NR level 3.0 120 so i i 2.5 100 70 2.
80 60 1.5 50 1.0 Wt 40 40 ! 0.5 0.0 20 30 '
20 -0.5 0
-1.0
-20 10 -1.5
-40 0 -2.0 0 10 15 20 0 5 10 20 ThOI ki- (,gc)
Figure 19 Plant Response to FW Controller Failure (EOC LCF with RPTOOS (HBB))
Page 43
NINE MILE POINT 2 00ON0123-SRLR Relnnd 14 Revikinn 2 MSIVF ICFTNEO-Overpress KOI i1 140 420 100 1450 gO 1400 120 380 80 1350 100 300 70 1300 60
- 80 240 1200o Or 60 180 N 40 1150 z
40 120 30 1100 1050 20 1000 0 950 2 3 4 5 6 7 0 1 2 3 4 5 6 7 Tkm~ (see) Tkne (sec) 120 - eowsirP 00 4.0
-Soarn Flow 3.5 1 NR leve 100 50 3.0 Z" 2.5 80 40 2.0 30 1.0 460 0.5 I.
20 0.0
.15 -
40 10 -1.0
-1.5 0 -2.0 0 1 2 3 4 5 6 0 1 2 3 4 5 6 7 flU~tt.PSAW.ISS 1'.i.r (-~) Tume (60c)
Figure 20 Plant Response to MSIV Closure (Flux Scram) - ICF (HBB)
Page 44
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 MSIVF MLP.TNEO-Overpress KO1 Is 140 -- 420 100 - 1460 go 120 350 80 1350 100 300 70 1300 50 1250 f 80 240 ° 180 5 1200;g 60 40 1150!
40 120 3 1100 20 1050 20 60 10 1000 0 0 0 - 950 2 3 4 5 6 7 0 1 2 3 4 5 a 7 Time (see) Time (se) 120 60 4.0 3.5 100 50 3.0 Z 2.5 40 i2-0 80 0.5
~60 40 20a 10.0
- 0.5 20 10 -1.0
-1.5 0 -2.0 0 1 2 3 4 5 a 7 0 1 2 3 4 5 6 7 Time (ee) Tune (eea)
Figure 21 Plant Response to MSIV Closure (Flux Scram) - LCF (HBB)
Page 45
NINE MILE POINT 2 00ON0123-SRLR Reload 14 RPvk~in 9 Revision 2 120 1
110
- Manual BSP Scram Region 100 - Manual BSP Controliled Entry Region
- BSP Boundary 90 80 70 I 60 50 40 51 30 20 o:
0 10 20 30 40 50 60 70 80 90 100 110 120 Core now t')
Figure 22 Manual BSP Regions and BSP Boundary for Normal Feedwater Temperature Operation Page 46
NINE MILE POINT 2 000N0123-SRLR Reload 14 Revision 2 Appendix A Analysis Conditions The reactor operating conditions used in the reload licensing analysis for this plant and cycle are presented in Table A-1. The pressure relief and safety valve configuration for this plant are presented in Table A-2. Additionally, the operating flexibility options listed in Section 8 are supported by the reload licensing analysis.
Table A-1 Reactor Operating Conditions Analysis Value ICF LCF16 Parameter NFWT NFWT Thermal power, MWt 3988.0 3988.0 Core flow, Mlb/hr 114.0 92.2 Reactor pressure (core mid-plane), psia 1051.0 1047.2 Inlet enthalpy, Btu/Ib 530.0 525.2 Non-fuel power fraction1 7 N/A N/A Steam flow, Mlb/hr 17.63 17.63 Dome pressure, psig 1020.2 1020.2 Turbine pressure, psig 975.5 975.6 Table A-2 Pressure Relief and Safety Valve Configuration 16 The low core flow analysis condition used a bounding core flow value.
17 For TRACG methodology, the direct moderator heating is a function of moderator density.
Page 47
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Appendix B Thermal-Mechanical Compliance A thermal-mechanical compliance check is performed for all analyzed transients to assure that the fuel will operate without violating the thermal-mechanical design limits. These limits are designed such that reactor operation within these limits provides assurance that the fuel will not exceed any thermal-mechanical design or licensing limits during steady-state operation and postulated AOOs. The fuel thermal-mechanical limits are met for the current cycle.
Page 48
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Appendix C Decrease in Core Coolant Temperature Event The Loss-of-Feedwater Heating event was analyzed at 100% rated power using the BWR Simulator Code. The use of this code is consistent with the approved methodology. The transient plots, neutron flux and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, those items are not included in this document. The OLMCPR result is shown in Section 11.
Page 49
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Appendix D Off-Rated Limits Off-Rated Power Dependent Limits ARTS power dependent thermal limits have been confirmed for operation with Equipment In-Service, Turbine Bypass Valves Out-Of-Service (TBVOOS), Recirculation Pump Trip Out-Of-Service (RPTOOS) and Pressure Regulator Out-Of-Service (PROOS). The Kp/MCPRp and LHGRFACp thermal limits applicable to the Equipment In-Service, TBVOOS and RPTOOS conditions are documented in Reference D-4. The Kp/MCPRp and LHGRFACp thermal limits applicable to the PROOS condition are documented in References D-4 and D-2. The off-rated power dependent limits provided in References D-4 and D-2 have been validated for this cycle.
The MCPRp limits provided in References D-4 and D-2 are based on a SLMCPR of 1.07; therefore, a SLMCPR adjustment is required for this cycle. The off-rated power dependent limits have been scaled by (1.09/1.07). The Reference D-2 limits for PROOS below 55% power have been adjusted as a result of the shift in fuel thermal monitor threshold and scaling of Pbypass similar to the adjustment shown in Reference D-3.
The MCPRp and LHGRFACp limits below the turbine power/scram bypass setpoint of 26% rated power have only been evaluated for core flow less than or equal to 75% of rated core flow. Therefore, the MCPRp and LHGRFACp limits below 26% power are not applicable above 75% of rated core flow.
The LOSC report in Reference D-6 has been confirmed to be applicable to the MELLLA+ operating domain.
Page 50
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 MCPRp Limits for:
Equipment In-Service Limits for Power < 26.0%
Flow > 75.0% Flow < 75.0%
Power (%) Limit Power (%) Limit MCPRp MCPRp 23.0 Not Analyzed 23.0 2.52 26.0 Not Analyzed 26.0 2.43 Limits for Power Ž26.0%
Power (%) Limit Kp 26.0 1.511 55.0 1.336 55.0 1.193 60.0 1.150 85.0 1.056 100.0 1.000 MCPRp Limits for:
TBVOOS Limits for Power < 26.0%
Flow > 75.0% Flow < 75.0%
Power (%) Limit Power (%) Limit MCPRp MCPRp 23.0 Not Analyzed 23.0 3.33 26.0 Not Analyzed 26.0 3.06 Limits for PowerŽ26.0%
Power (%) Limit Kp 26.0 1.511 55.0 1.336 55.0 1.193 60.0 1.150 85.0 1.056 100.0 1.000 Page 51
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 MCPRp Limits for:
RPTOOS Limits for Power < 26.0%
Flow > 75.0% Flow < 75.0%
Power (%) Limit Power (%) Limit MCPRp MCPRp 23.0 Not Analyzed 23.0 2.52 26.0 Not Analyzed 26.0 2.43 Limits for Power Ž26.0%
Power (%) Limit Kp 26.0 1.511 55.0 1.336 55.0 1.193 60.0 1.150 85.0 1.062 100.0 1.000 MCPRp Limits for:
PROOS Limits for Power < 26.0%
Flow > 75.0% Flow < 75.0%
Power (%) Limit Power (%) Limit MCPRp MCPRp 23.0 Not Analyzed 23.0 2.52 26.0 Not Analyzed 26.0 2.43 Limits for PowerŽ 26.0%
Power (%) Limit Kp 26.0 1.511 90.0 1.122 90.0 1.038 100.0 1.000 LHGRFACp Limits for:
Equipment In-Service Limits for Power < 26.0%
Flow > 75.0% Flow < 75.0%
Power (%) Limit Power (%) Limit 23.0 Not Analyzed 23.0 0.597 26.0 Not Analyzed 26.0 0.613 Limits for PowerŽ_26.0%
Power (%) Limit 26.0 0.613 100.0 1.000 Page 52
NINE MILE POINT 2 00N01 23-SRLR Reload 14 Revision 2 LHGRFACp Limits for:
TBVOOS Limits for Power < 26.0%
Flow > 75.0% Flow < 75.0%
Power (%) Limit Power (%) Limit 23.0 Not Analyzed 23.0 0.535 26.0 Not Analyzed 26.0 0.556 Limits for Power Ž_26.0%
Power (%) Limit 26.0 0.613 100.0 1.000 LHGRFACp Limits for:
RPTOOS Limits for Power < 26.0%
Flow > 75.0% Flow < 75.0%
Power (%) Limit Power (%) Limit 23.0 Not Analyzed 23.0 0.597 26.0 Not Analyzed 26.0 0.613
Ž_
Limits for Power 26. 0%
Power (%) Limit 26.0 0.613 100.0 1.000 LHGRFACp Limits for:
PROOS Limits for Power< 26.0%
Flow > 75.0% Flow < 75.0%
Power (%) Limit Power (%) Limit 23.0 Not Analyzed 23.0 0.597 26.0 Not Analyzed 26.0 0.6 13 Limits for Power Ž_26.0%
Power (%) Limit 26.0 0.613 90.0 0.850 90.0 0.948 100.0 1.000 Page 53
NINE MILE POINT 2 000N0123-SRLR lQl*-,A 1,A Off-Rated Flow Dependent Limits ARTS flow dependent thermal limits are documented in Reference D- 1 and confirmed for MELLLA+ in Reference D-5. The off-rated flow dependent limits provided in Reference D-1 have been validated for this cycle.
The MCPRf limits provided in Reference D-I are based on a SLMCPR of 1.07; therefore, a SLMCPR adjustment is required for this cycle. The off-rated flow dependent limits have been scaled by (1.09/1.07).
MCPRf Limits for:
Equipment In-Service Limits for a Maximum Runout Flow of 112.0%
Flow (%) Limit MCPRf 30.0 1.69 87.3 1.27 112.0 1.27 MCPRf Limits for:
TBVOOS Limits for a Maximum Runout Flow of 112.0%
Flow (%) Limit MCPRf 30.0 1.69 87.3 1.27 112.0 1.27 MCPRf Limits for:
RPTOOS Limits for a Maximum Runout Flow of 112.0%
Flow (%) Limit MCPRf 30.0 1.69 87.3 1.27 112.0 1.27 MCPRf Limits for:
PROOS Limits for a Maximum Runout Flow of 112.0%
Flow (%) Limit MCPRf 30.0 1.69 87.3 1.27 112.0 1.27 Page 54
NINE MILE POINT 2 00ON0123-SRLR DVIl- A IA D, ,; ;* ")
flX'.~~flS.~ULS 1' IIUIL aT LHGRFACf Limits for:
Equipment In-Service Limits for a Maximum Runout Flow of 112.0%
Flow (%) Limit 30.0 0.625 85.0 1.000 112.0 1.000 LHGRFACf Limits for:
TBVOOS Limits for a Maximum Runout Flow of 112.0%
Flow (%) Limit 30.0 0.625 85.0 1.000 112.0 1.000 LHGRFACf Limits for:
RPTOOS Limits for a Maximum Runout Flow of 112.0%
Flow (%) Limit 30.0 0.625 85.0 1.000 112.0 1.000 LHGRFACf Limits for:
PROOS Limits for a Maximum Runout Flow of 1120%
Flow (%) Limit 30.0 0.625 85.0 1.000 112.0 1.000 Page 55
NINE MILE POINT 2 000N0123-SRLR Reload 14 Revision 2 References D-I Nine Mile Point Nuclear Station Unit 2 - APRM/RBM/Technical Specifications / Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Revision 0, March 2007.
D-2 Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900: Transient Analysis, GE-NE-0000-0055-2373-RO, Revision 0, February 2007.
D-3 Nine Mile PointNuclear Station Unit 2 Extended Power Uprate, Task T0900: Transient Analysis, 0000-0069-6612-Ri, Revision 1, January 2009.
D-4 Nine Mile Point Nuclear Power Plant, Unit 2, TRACG Implementation for Reload Licensing TransientAnalysis (T1309), 0000-0157-9895-RI, Revision 1, October 2013.
D-5 Nine Mile Point Nuclear Station Unit 2 MELLLA +, Task T0900: TransientAnalysis, 0000-0130-0603-R3, Revision 3, July 2013.
D-6 Evaluation of Loss of Stator Water Coolingfor Nine Mile Point Units I and 2, 0000-0158-1307-RO, March 2013.
Page 56
NINE MILE POINT 2 000N0123-SRLR Reload 14 Revision 2 Appendix E Expanded Operating Domain Analyses Expanded operating domain analyses were performed for Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operation, Increased Core Flow (ICF) operation up to 105% of rated core flow, turbine bypass valve out-of-service (TBVOOS), recirculation pump trip out-of-service (RPTOOS), and pressure regulator out-of-service (PROOS).
Coastdown operation beyond full power to 40% power under conditions bounded by 105% core flow is conservatively bounded by the MCPR operating limits given in Section II of this document at the applicable core flow and feedwater temperature conditions in the expanded operating domain. The basis for this statement is contained in Reference E-1 & E-3.
100% Core Flow (Standard Domain)
It has been established that ICF and/or MELLLA+ domain results bound the standard (rated core flow) domain. Therefore, a cycle-specific analysis is not performed for the 100% rated core flow.
Maximum Extended Load Line Limit Analysis Plus The operating domain MELLLA+ was established for Nine Mile Point Unit 2 in Reference E-2.
Increased Core Flow Operation with ICF throughout the operating cycle was justified for Nine Mile Point Unit 2 in Reference E-2.
The MSIV closure event (flux scram) was analyzed at 100% rated thermal power and both 85% and 105% rated core flow at the rated dome pressure.
An operational band of - 20'F from nominal feedwater temperature is supported this cycle for all Application Conditions specified in Section 11.
Turbine Bypass Valve Out of Service (TBVOOS)
Operation with TBVOOS was justified for Nine Mile Point Unit 2 in Reference E-2.
EOC Recirculation Pump Trip Out of Service (EOC RPTOOS)
Operation with EOC RPTOOS was justified for Nine Mile Point Unit 2 in Reference E-2.
Pressure Regulator Out of Service (PROOS)
Operation with PROOS was addressed for Nine Mile Point Unit 2 from a thermal limits perspective only in Reference E-2.
Page 57
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 References for Appendix E:
E-1 General Electric Standard Application for Reactor Fuel (GESTAR II), NEDE-240 11-P-A-i19, May 2012 and the U.S. Supplement, NEDE-2401 1-P-A-19-US, May 2012.
E-2 Project Task Report, Constellation Energy Nuclear Group, Nine Mile Point Nuclear Station Unit 2 MELLLA+, Task T0900: TransientAnalysis, 0000-0130-0603-R3, Revision 3, July 2013.
E-3 Amendment 39 to NEDE-24011-P-A-19 andNEDE-24011-P-A-19-US, GeneralElectric Standard Application for Reactor Fuel (GESTAR II) and the US Supplement, MFN 13-074, September 2013.
Page 58
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Appendix F TRACG04 AOO Supplementary Information Reference F-1 provides the results of the evaluations supporting the application of TRACG04 for AOO analyses for Nine Mile Point 2.Section II of this report presents the MCPR limits based on the TRACG04 methodology of Reference F-2.
The safety evaluation report for licensing topical report NEDE-32906P (Reference F-2) concluded that the application of TRACG04 methods to AOO and overpressure transient analyses were acceptable subject to certain limitations and conditions. Nine Mile Point 2 Cycle 15 is in compliance with these limitations and conditions.
References for Appendix F F-I. Nine Mine Point Nuclear Power Plant, Unit 2, TRACG Implementation for Reload Licensing TransientAnalysis (T1309), 0000-0157-9895-R1, Revision 1, October 2013.
F-2. Migration to TRACGO4/PANAC11 from TRACGO2/PANACIO for TRACG AO0 and ATWS OverpressureTransients, NEDE-32906P, Supplement 3-A, Revision 1, April 2010.
Page 59
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Appendix G Interim Methods LTR (NEDC-33173P-A Revision 4)
Supplementary Information The safety evaluation for licensing topical report NEDC-33173P-A (Reference G-1) concluded that the application of GEH/GNF methods to expanded operating domains was acceptable subject to certain limitations and conditions. Several of these conditions request that additional, application-specific information be provided in the SRLR. The information provided below responds these requests for the identified items.
Limitation and Condition 9.5 (SLMCPR 2)
Limitation and Condition 9.5 states:
"For operation at MELLLA+, including operation at the EPU power levels at the achievable core flow state-point, a 0.01 value shall be added to the cycle-specific SLMCPR value for power-to-Ilow ratios up to 42 MWt/Mlbm/hr, and a 0. 02 value shall be added to the cycle-specific SLMCPR value for power-to-flow ratios above 42 MWt/Mlbrn/hr. "
For operation at MELLLA+, a 0.02 value was added to the cycle specific SLMCPR. The SLMCPR values reported in Section 11 reflect this adder.
Limitation and Condition 9.8 (ECCS-LOCA 2)
Limitation and Condition 9.8 states:
"The ECCS-LOCA will be performed for all statepoints in the upper boundary of the expanded operatingdomain, including the minimum core flow statepoints, the transition statepoint, as defined in Reference G-2 and the 55 percent core flow statepoint. The plant-specific application will report the limiting ECCS-LOCA results as well as the ratedpower andflow results. The SRLR will include both the limiting statepoint ECCS-LOCA results and the rated conditions ECCS-LOCA results. "
This limitation and condition is satisfied by the Appendix K PCTs reported in Reference 16.4. The SRLR reports the bounding Licensing Basis PCT for all statepoints analyzed.
Limitation and Condition 9.10 (Transient LHGR 2)
Limitation and Condition 9.10 states:
"Each EPU and MELLLA + fiuel reload will document the calculation results of the analyses demonstratingcompliance to transient T-M acceptance criteria. Tihe plant T-M response will be provided with the SRLR or COLR, or it will be reported directly to the NRC as an attachment to the SRLR or COLR. "
Page 60
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Table G-I summarizes the percent margin to the Thermal Overpower and Mechanical Overpower acceptance criteria.
Table G-I Margin to the Thermal Overpower and Mechanical Overpower Acceptance Criteria Criteria GE14C Thermal Overpower 28.5%
Mechanical Overpower 14.9%
Limitation and Condition 9.11 (Transient LHGR 3)
Limitation and Condition 9.11 states:
"To accountfor the impact of the void history bias, plant-specific EPU and MELLLA +
applicationsusing either TRACG or ODYN will demonstrate an equivalent to 10 percent margin to the fuel centerline melt and the 1 percent cladding circumferential plastic strain acceptance criteriadue to pellet-claddingmechanical interactionfor all oflimiting AO0 transient events, including equipment out-of-service. Limiting transients in this case, refers to transients where the void reactivity coefficient plays a significant role (such as pressurizationevents). If the void history bias is incorporatedinto the transient model within the code, then the additional 10 percent margin to the fiuel centerline melt and the I percent cladding circumferentialplastic strain is no longer required."
The void history bias was incorporated into the transient model within the TRACG04 code, and therefore the 10 percent margin to the fuel centerline melt and the 1 percent cladding circumferential plastic strain acceptance criteria are no longer required.
Limitation and Condition 9.17 (Steady-State 5 Percent Bypass Voiding)
Limitation and Condition 9.17 states:
"The instrumentationspecification design bases limit the presence of bypass voiding to 5 percent (LRPM (sic) levels). Limiting the bypass voiding to less than 5 percent for long term steady operation ensures that instrumentation is operated within the specification.
For EPU and MELLLA + operation, the bypass voiding will be evaluated on a cycle-specific basis to confirm that the void fraction remains below 5 percent at all LPRM levels when operating at steady-state conditions within the MELLLA+ upper boundary.
The highest calculatedbypass voiding at any LPRM level will be provided with the plant-specific SRLR. "
Page 61
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 The bypass voiding was evaluated for the licensed core loading and confirmed that the bypass void fraction remained below 5 percent at all LPRM levels when operating at steady-state conditions within the licensed upper boundary.
Limitation and Condition 9.18 (Stability Setpoints Adjustment)
Limitation and Condition 9.18 states:
"The NRC staff concludes that the presence bypass voiding at the low-flow conditions where instabilities are likely can result in calibration errors of less than 5 percent for OPRM cells and less than 2 percentfor APRM signals. These calibrationerrors must be accounted for while determining the setpoints for any detect and suppress long term methodology. The calibrationvalues for the different long-term solutions are specified in the associatedsections of this SE, discussing the stability methodology."
This limitation and condition is not applicable to DSS-CD because the significant conservatisms in the current licensing methodology and associated MCPR margins are more than sufficient to compensate for the overall uncertainty in the OPRM instrumentation.
Limitation and Condition 9.19 (Void-Quality Correlation 1)
Limitation and Condition 9.19 states:
"For applications involving PANCEA(sic)/ODYN/ISCORITASC for operation at EPU and MELLLA+, an additional 0.01 will be added to the OLMCPR, until such time that GE expands the experimental database supporting the Findlay-Dix void-quality correlationto demonstrate the accuracy and performance of the void-quality correlation based on experimental data representative of the current fuel designs and operating conditions duringsteady-state, transient,and accident conditions."
The OLMCPR limitation requiring an additional 0.01 adder on the OLMCPR does not apply to EPU or MELLLA+ licensing calculations when TRACG04 methods are used (Reference G-3). Therefore, the OLMCPR adder is not applied to NMP2 Cycle 15.
References for Appendix G G-1. Applicability of GE Methods to Expanded Operating Domains, NEDC-33173P-A, Revision 4, November 2012.
G-2. General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus, NEDC-33006P-A, Revision 3, June 2009.
G-3. Migration to TRACG04 / PANACll from TRACGO2 / PANACIO for TRACG AO0 and ATWS Overpressure Transients,NEDE-32906P, Supplement 3-A, Revision 1, April 2010.
Page 62
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Appendix H MELLLA+ LTR (NEDC-33006P-A Revision 3)
Supplementary Information The safety evaluation for licensing topical report NEDC-33006P-A Revision 3 (Reference H-i) approved the operation of GE BWRs in the MELLLA+ expanded operating domain, subject to certain limitations and conditions. Several of these limitations and conditions request that additional, application-specific information be provided in the SRLR. The information provided below responds to these requests for the identified items.
The pressurization transients are generally limiting at high core flow conditions. However, the transients were performed at both the minimum MELLLA+ flow (85%) and the maximum ICF flow (105%). This ensures that the pressurization transient results bound MELLLA, MELLLA+ and ICF operating conditions. Additionally, the loss of feedwater heating (LFWH) transient, which is more limiting at low core flow, was performed at the minimum MELLLA+ flow. Therefore, the limiting subcooling transient bounds MELLLA, MELLLA+ and ICF operating conditions. Single loop operation (SLO) will not be allowed in conjunction with operation in the MELLLA+ domain.
Limitation and Condition 12.6 (SLMCPR Statepoints and CF Uncertainty)
Limitation and Condition 12.6 states:
"Until such time when the SLMCPR methodology (References H-2 and H-3) for off-rated SLMCPR calculation is approved by the stafffor MELLLA + operation, the SLMCPR will be calculatedat the rated statepoint (120 percent P/I00 percent CF), the plant-specific minimum CF statepoint (e.g., 120 percent P/80 percent CF), and at the 100 percent OLTP at 55 percent CF statepoint. The currently approved off-rated CF uncertainty will be used for the minimum CF and 55 percent CF statepoints. The uncertainty must be consistent with the CF uncertainty currently applied to the SLO operation or as NRC-approved for MELLLA+ operation. The calculated values will be documented in the SRLR. "
As requested, the SLMCPR calculated results at specified off-rated power/flow conditions are reported in Table H-i below, including the low CF statepoint.
Page 63
NINE MILE POINT 2 OOONO 123-SRLR Reload 14 Revision 2 Table H-1 Two-Loop SLMCPR Results for MELLLA+ Conditions Power (% Rated) Flow (% Rated) SLMCPR 100 100 1.04 100 85 1.06 77.6 55.0 1.07 100 105 1.04 Limitation and Condition 12.10.b (ECCS-LOCA Off-Rated Multiplier)
Limitation and Condition 12.10.b states:
"LOCA analysis is not peiformed on cycle-specific basis; therefore, the thermal limits applied in the A'I+SAR LOCA analysisfor the 55 percent CF MELLLA + statepoint and/or the transition statepoint must be either bounding or consistent with cycle-specific off-rated limits. The COLR and the SRLR will contain confirmation that the off-rated limits assumed in the ECCS-LOCA analyses bound the cycle-specific off-rated limits calculated for the MELLLA + operation. Every future cycle reload shall confirm that the cycle-specific off-rated thermal limits applied at the 55 percent CF and/or the transition statepoints are consistent with those assumed in the plant-specific ECCS-LOCA analyses. "
The off-rated limits assumed in the ECCS-LOCA analyses are confirmed to be consistent with the cycle-specific off-rated LHGR multipliers calculated for the MELLLA+ operation.
Limitation and Condition 12.18.d (ATWS TRACG Analysis)
Limitation and Condition 12.18.d states:
"In general, the plant-specific application will ensure that operation in the MELLLA+
domain is consistent with the assumptions used in the ATWS analysis, including equipment out of service (e.g., FWHOOS, SLO, SRVs, SLC pumps, and RHR pumps, etc.).
If assumptions are not satisfied, operation in MELLLA+ is not allowed. The SRLR will specify the prohibitedflexibility options for plant-specific MELLLA + operation, where applicable. For key input parameters, systems and engineering safety features that are important to simulating the ATWS analysis and are specified in the Technical Specification (TS) (e.g., SLCS parameters,A TWS RPT, etc.), the calculation assumptions must be consistent with the allowed TS values and the allowedplant conifiguration. If the analyses deviate from the allowed TS configurationfor long term equipment out of Page 64
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 service (i.e., beyond the TS LCO), the plant-specific application will specify andjustify the deviation. In addition, the licensee must ensure that all operability requirements are met (e.g., NPSH) by equipment assumed operable in the calculations."
This ATWS TRACG Analysis limitation and condition requires that the SRLR specify the prohibited flexibility options for plant-specific MELLLA+ operation, where applicable, as expressed by EOOS options in Section 8.
References for Appendix H H-I. General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus, NEDC-33006P-A, Revision 3, June 2009.
H-2. Methodology and Uncertainties for Safety Limit MCPR Evaluations, NEDC-32601P-A, August 1999.
H-3. Power Distribution Uncertainties for Safety Limit MCPR Evaluations, NEDC-32694P-A, August 1999.
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NINE MILE POINT 2 00ON0123-SRLR D1* A 1A W ýv a vil Appendix I List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective 2RPT (2PT) Two Recirculation Pump Trip ADS Automatic Depressurization System ADSOOS Automatic Depressurization System Out of Service AOO Anticipated Operational Occurrence APRM Average Power Range Monitor ARTS APRM, Rod Block and Technical Specification Improvement Program BOC Beginning of Cycle BSP Backup Stability Protection BWROG Boiling Water Reactor Owners Group COLR Core Operating Limits Report CPR Critical Power Ratio DIRPT Delta MCPR over Initial MCPR for a two-Recirculation Pump Trip DIVOM Delta CPR over Initial MCPR vs. Oscillation Magnitude DR Decay Ratio DS/RV Dual Mode Safety/Relief Valve ECCS Emergency Core Cooling System ELLLA Extended Load Line Limit Analysis EOC End of Cycle (including all planned cycle extensions)
EOR End of Rated (All Rods Out 100%Power / I00%Flow / NFWT)
EPU Extended Power Uprate ER Exclusion Region FFWTR Final Feedwater Temperature Reduction FMCPR Final MCPR FOM Figure of Merit FWCF Feedwater Controller Failure FWHOOS Feedwater Heaters Out of Service FWTR Feedwater Temperature Reduction GESTAR General Electric Standard Application for Reactor Fuel GETAB General Electric Thermal Analysis Basis GSF Generic Shape Function HAL Haling Bum HBB Hard Bottom Burn HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection ICA Interim Corrective Action ICF Increased Core Flow IMCPR Initial MCPR Page 66
NINE MILE POINT 2 00ON0123-SRLR I A4 1A Acronym Description IVM Initial Validation Matrix Kf Off-rated flow dependent OLMCPR multiplier Kp Off-rated power dependent OLMCPR multiplier L8 Turbine Trip on high water level (Level 8)
LCF Low Core Flow LHGR Linear Heat Generation Rate LHGRFACf Off-rated flow dependent LHGR multiplier LHGRFACp Off-rated power dependent LHGR multiplier LOCA Loss of Coolant Accident LOSC Loss of Stator Cooling LPRM Local Power Range Monitor LRHBP Load Rejection with Half Bypass LRNBP Load Rejection without Bypass LTR Licensing Topical Report MAPFACf Off-rated flow dependent MAPLHGR multiplier MAPFACp Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPRf Off-rated flow dependent OLMCPR MCPRp Off-rated power dependent OLMCPR MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ MELLLA Plus MOC Middle of Cycle MRB Maximal Region Boundaries MSF Modified Shape Function MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Service MSR Moisture Separator Reheater MSROOS Moisture Separator Reheater Out of Service MTU Metric Ton Uranium MWd Megawatt day MWd/ST Megawatt days per Standard Ton MWd/MT Megawatt days per Metric Ton MWt Megawatt Thermal N/A Not Applicable NBP No Bypass NCL Natural Circulation Line NFWT Normal Feedwater Temperature NMP2 Nine Mile Point 2 NOM Nominal Bum NTR Normal Trip Reference OLMCPR Operating Limit MCPR OOS Out of Service OPRM Oscillation Power Range Monitor Page 67
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Acronym Description Pbypass Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed Pdome Peak Dome Pressure Psi Peak Steam Line Pressure Pv Peak Vessel Pressure PCT Peak Clad Temperature PHE Peak Hot Excess PLHGR Peak Linear Heat Generation Rate PLU Power Load Unbalance PLUOOS Power Load Unbalance Out of Service PRFDS Pressure Regulator Failure Downscale PROOS Pressure Regulator Out of Service Q/A Heat Flux RBM Rod Block Monitor RC Reference Cycle RCF Rated Core Flow RDF Recirculation Drive Flow RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS Recirculation Pump Trip Out of Service RTP Rated Thermal Power RV Relief Valve RVM Reload Validation Matrix RWE Rod Withdrawal Error SC Standard Cycle SL Safety Limit SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRLR Supplemental Reload Licensing Report S/RV (SRV) Safety/Relief Valve SRVOOS Safety/Relief Valve(s) Out of Service SS Steady State SSV Spring Safety Valve STU Short Tons (or Standard Tons) of Uranium TBSOOS Turbine Bypass System Out of Service TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valves Out of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Service TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TRF Trip Reference Function TSIP Technical Specifications Improvement Program TSV Turbine Stop Valve Page 68
NINE MILE POINT 2 00ON0123-SRLR Reload 14 Revision 2 Acronym Description TSVOOS Turbine Stop Valve Out of Service TT Turbine Trip TTHBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Bum Page 69