NMP2L2878, Core Operating Limits Report
| ML24136A128 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/16/2024 |
| From: | Shultz B Constellation Energy Generation |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMP2L2878 | |
| Download: ML24136A128 (1) | |
Text
Constellation.
Technical Specification 5.6.5 NMP2L2878 April 16, 2024
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-001
Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410
Subject:
Core Operating Limits Report
Enclosed is a copy of the Core Operating Limits Report, Revision 8, for Nine Mile Point Unit 2 Cycle 20. This report is being submitted pursuant to NMP2 Technical Specification 5.6.5.d.
Should you have any questions regarding the information in this submittal, please contact Mr.
Eric Kelsey at (315) 349-7037.
Sincerely,
Digitally signed by Shultz, Shultz, Brandon K. Brandon K.
Date: 2024.04. 16 08:40:00 - 04'00'
Brandon K. Shultz Mgr. Site Regulatory Assurance, Nine Mile Point Clean Energy Center
Enclosure : Core Operating Limits Report, Revision 8 for Nine Mile Point Unit 2, Cycle 20
cc : NRG Regional Administrator, Region I NRG Project Manager NRG Senior Resident Inspector Enclosure
Core Operating Limits Report, Revision 8
for
Nine Mile Point Unit 2, Cycle 20 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
CORE OPERA TING LIMITS REPORT FOR NINE MILE POINT UNIT 2 CYCLE 20
(This is a complete re-write; no revision bars are used)
Mcclure, Kelly Prepared By: 2024.02.12 12:46:14 -05'00' Kelly McClure Preparer, Nuclear Fuels
Digitally signed by Potter, Robert C.
P tt R b C Q er Q ert
- DN:cn=Potter,RobertC.
Reviewed By: I Date:2024,02.1214:11:01 *0S'00' Robert Potter Reviewer, Nuclear Fuels Digitally signed by Norman,
.,,
- Timothy Reviewed By: Date: 2024,02 J 2 J 3-J 4*4J -06'00*
Timothy Norman Reviewer, Engineering Safety Analysis Reviewed By: Kl*m Andrew J1"n DigltallyslgnedbyKlm,AndrewJln, Date: 2024;02.12 14:19:45 -05'00'
Andrew Kim Reviewer, Reactor Engineering
Digitally signed by Mccoskey, Kristin Approved By: ~ Ao/ Date: 2024.02.16 13:05:31 -06'00'
Kristin Mccoskey Senior Manager, Nuclear Fuels
SQR By: Da rweesh John N, Date: 2024.02.27 DlgitallyslgnedbyDarweesh,JohnN 10:47:37 -os*oo*
John Darweesh Station Qualified Reviewer
Page 1 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
Table of Contents
Section Page Number
Summary of Revisions 3
List of Tables / Figures 4
1.0 Terms and Definitions 5
2.0 General Information 7
3.0 MAPLHGR Limits 8 4.0 MCPR Limits 9 5.0 LHGR Limits 13
6.0 Rod Block Monitor Setpoints 16
7.0 Turbine Bypass Valve Parameters 17 8.0 Modes of Operation 18
9.0 Stability Protection 19
10.0 Power Flow Operating Map 20 11.0 Methodology 20
12.0 References 21
Page 2 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
Summary of Revisions
Revision Description
Revision 8 New Issue for Cycle 20
Page 3 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
List of Tables/ Figures
Table 3-1 MAPLHGR Versus Average Planar Exposure, GNF2 Fuel
Table 3-2 MAPLHGR Versus Average Planar Exposure, GNF3 Fuel 8
Table 3-3 MAPLHGR SLO Multiplier, All Fuel Types 8
Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR), All Fuel Types 10
Table 4-2 Power Dependent MCPR Limits (MCPRP) and Multipliers (Kp), All Fuel 11 Types Table 4-3 Flow Dependent MCPR Limits (MCPRF), GNF2 Fuel 12
Table 4-4 Flow Dependent MCPR Limits (MCPRF), GNF3 Fuel 12
Table 4-5 Cycle Specific SLMCPR (MCPR99.9%) 12
Table 5-1 LHGR Limits for UO2 Fuel Rods 13
Table 5-2 LHGR Limits for Gadolinia Rods 13
Table 5-3 Power Dependent LHGR Multipliers (LHGRFACp), GNF2 Fuel, DLO and 14 SLO Table 5-4 Power Dependent LHGR Multipliers (LHGRFACp), GNF3 Fuel, DLO and 14 SLO Table 5-5 Flow Dependent LHGR Multipliers (LHGRFACF), GNF2 Fuel, All Modes of 15 Operation Table 5-6 Flow Dependent LHGR Multipliers (LHGRFACF), GNF3 Fuel, All Modes of 15 Operation Table 6-1 Rod Block Monitor Setpoints 16
Table 6-2 ARTS RWE Validated MCPR Values 16
Table 7-1 Turbine Bypass Valve Response Time 17
Table 8-1 Modes of Operation 18
Table 8-2 EOOS Conditions Included under BASE Option 18
Table 8-3 Power Level Restrictions 18
Table 9-1 BSP Endpoints for Normal Feedwater Temperature 19
Table 9-2 Automated BSP Setpoints 19 Figure 1 Power/Flow Operating Map for MELLLA+ in Dual Loop Operation;." 20
Page 4 of 21 ConstellaUon Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
1.0 Terms and Definitions
ADS Automatic Depressurization System ADSOOS Automatic Depressurization System Out of Service. ADSOOS is defined as any ADS valve inoperable.
APLHGR Average Planar Linear Heat Generation Rate APRM Average Power Range Monitor ARTS Average Power Range Monitor, Rod Block Monitor, and Technical Specification (ARTS) improvements program BSP Backup Stability Protection COLR Core Operating Limits Report DLO Dual Loop Operation ECCS Emergency Core Cooling System EIS Equipment In Service EOOS Equipment Out of Service EOR End of Rated. The cycle exposure at which reactor power is equal to 100% rated (3988 MW1h), recirculation flow equal to 100% rated (108.5 Mlb/hr), and all control blades are fully withdrawn with equilibrium xenon.
EPU Extended Power Uprate GEH General Electric-Hitachi GNF Global Nuclear Fuel HFCL High Flow Control Line HTSP High Power Trip Set Point (regarding RBM)
ICF Increased Core Flow
!TSP Intermediate Power Trip Set Point (regarding RBM)
KP Off-rated power dependent OLMCPR multiplier LCO Limiting Condition for Operation LHGR Linear Heat Generation Rate LHGRFACF Off-rated flow dependent LHGR multiplier LHGRFACP Off-rated power dependent LHGR multiplier LOCA Loss of Coolant Accident LTR Licensing Topical Report LTSP Low Power Trip Set Point (regarding RBM)
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 MCPR99.9% Limiting MCPR value such that 99.9 percent of the fuel in the core is not susceptible to boiling transition. Also known as the cycle-specific SLMCPR.
MCPRF Off-rated flow dependent OLMCPR
Page 5 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
MCPRP Off-rated power dependent OLMCPR MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ Maximum Extended Load Line Limit Analysis Plus MSIVOOS Main Steam Isolation Valve Out of Service MSROOS Moisture Separator Reheater Out of Service NCL Natural Circulation Line NRC Nuclear Regulatory Commission OLMCPR Operating Limit MCPR OPRM Oscillation Power Range Monitor PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service RBM Rod Block Monitor RDF.Recirculation Drive Flow RPTOOS Recirculation Pump Trip Out of Service; also known as EOC-RPTOOS RTP Rated Thermal Power (3988 MW1)
RWE Rod Withdrawal Error SER Safety Evaluation Report SLMCPR Safety Limit MCPR SLO Single Loop Operation SRVOOS Safety ReliefValve(s) Out of Service TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valve Out of Service. TBVOOS supports 3 of 5 TBVs slow open and 2 of 5 TBVs do not slow open (stuck closed). TBVOOS also supports 5 TBV to not fast open (Reference 10).
TCV Turbine Control Valve TCVFASOOS Turbine Control Valve Fast Acting Solenoid Out of Service TCVOOS Turbine Control Valve Out of Service TS Technical Specification TSV Turbine Stop Valve TSVOOS Turbine Stop Valve Out of Service
Page 6 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
2.0 General Information
This report is prepared in accordance with Technical Specification (TS) 5.6.5 of Reference 1. Power and flow dependent limits are listed for various power and flow levels. For all power, flow, and exposure-dependent tables, linear interpolation should be used to determine intermediate values unless directed otherwise.
This report provides the values of the power distribution limits, control rod withdraw block instrumentation, and stability protection setpoints for Nine Mile Point Unit 2 Cycle 20.
This report provides the following cycle-specific parameter limits for Nine Mile Point Unit 2 Cycle 20 (Reload 19):
- Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
- Operating Limit Minimum Critical Power Ratio (OLMCPR)
- Cycle-specific SLMCPRs (MCPR99.9%)
- Linear Heat Generation Rate (LHGR)
- Turbine Bypass Valve (TBV) parameters
- Backup Stability Protection (BSP) parameters
The BASE thermal limit values shown in the tables are for normal, equipment in service (EIS), two loop operation. Analysis also supports Increased Core Flow (ICF) for operational flexibility. Additional equipment out of service (EOOS) applicability can be found in Section 8.0, Modes of Operation.
The data presented in this report is valid for all licensed operating domains on the operating map, including (Reference 2):
- Maximum Extended Load Line Limit Analysis Plus (MELLLA+) to a minimum core flow of 85% of rated.
- I CF up to 105% of rated (rated core flow is 108. 5 Mlb/hr).
- Extended Power Uprate (EPU) to 3988 MWth-
- Coastdown operation down to 40% Rated Thermal Power (RTP)
Page 7 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
3.0 MAPLHGR Limits
Technical Specification Sections 3.2.1. 3.4.1
The MAPLHGR limits obtained from the ECCS analysis are provided in Table 3-1 and Table 3-2 for GNF2 and GNF3 fuel, respectively. The limiting MAPLHGR value for the most limiting lattice of each fuel type as a function of exposure is given. For SLO, a multiplier is used as shown in Table 3-3.
The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for the off-rated conditions from an ECCS*LOCA analysis perspective and there is no need for MAPLHGR multipliers in addition to off-rated LHGR multipliers, per Reference 2 - Section 16.
Table 3-1 MAPLHGR Versus Average Planar Exposure GNF2 Fuel (Reference 2 - Table 9)
Average Planar Exposure [GWd/ST] MAPLHGR Limit [kW/ft]
0.00 13.78 17.15 13.78 60.78 6.87 63.50 5.50
Table 3-2 MAPLHGR Versus Average Planar Exposure GNF3 Fuel (Reference 2-Table 10)
Average Planar Exposure [GWd/STl MAPLHGR Limit rkW/ftl 0.00 14.36 21.22 13.01 40.82 10.75 57.60 8.00 63.50 6.00
Table 3-3 MAPLHGR SLO Multiplier All Fuel Types (Reference 2-Table 11)
Fuel Type SLO Multiplier GNF2 0.78 GNF3 0.95
Page 8 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
4.0 MCPR Limits
Technical Specification Sections 3.2.2, 3.3.4.1, 3.4.1, 3.7.5
OLMCPR values listed in Table 4-1 cover all conditions listed in Section 8.0, Modes of Operation.
Additional EOOS information can be found in Section 8.0. ARTS provides for power and flow dependent thermal limits adjustments, which allow for a more reliable administration of the MCPR thermal limit. Per TS 3.2.2, all MCPR's shall be verified in accordance with limits specified in this section.
Control rod scram time verification is also required per TS 3.1.4, Control Rod Scram Times. The applicable MCPR thermal limit set shall be determined with Tau (r), a measure of scram time performance throughout the cycle based on the cumulative plant scram time test results (Reference 13). The calculation of Tau shall be performed in accordance with site procedures.
The power dependent MCPR limits (MCPRp) and multipliers (Kp) are provided in Table 4-2 for all fuel types. The flow dependent MCPR limits (MCPRF) are provided in Tables 4-3 and 4-4, Table 4-3 for GNF2 fuel and Table 4-4 for GNF3 fuel.
ARTS power and flow dependent thermal limits have been confirmed for the following modes of operation:
- 1. Base
+ TCVFASOOS + RPTOOS)
- 4. MSROOS
- 5. The combination of PLUOOS, PROOS, TCVFASOOS, RPTOOS, MSROOS, and TBVOOS (PLUOOS + PROOS + TCVFASOOS + RPTOOS + MSROOS + TBVOOS)
The cycle-specific exposure-dependent SLMCPRs, known as MCPR99.9%, can be found in Table 4-5 for dual loop and single loop operating conditions. The values in Table 4-5 or conservative values were used to calculate the MCPR limits and off-rated limits in this section.
Page 9 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)
All Fuel Types (Reference 2 - Section 11)
SCRAM Cycle Exposure > 1724 MWd/ST EOOS Combination Time :S 1724 & < EOR-3782 ~ EOR-3782 Option 1 MWd/ST MWd/ST MWd/ST
DLO A 1.47 1.47 1.50
BASE 8 1.41 1.34 1.37
SL0 2 A 1.50 1.50 1.53
8 1.45 1.45 1.45
DLO A 1.52 1.52 1.55
TBVOOS + B 1.41 1.36 1.39 RPTOOS A 1.55 1.55 1.58 SL0 2 B 1.45 1.45 1.45
A 1.47 1.47 1.50 PLUOOS + DLO 1.37 PROOS + B 1.41 1.34 TCVFASOOS A 1.50 1.50 1.53
+ RPTOOS SL0 2 B 1.45 1.45 1.45
A 1.51 1.51 1.55 DLO 8 1.41 1.37 MSROOS 1.41
A 1.54 1.54 1.58 SL0 2 B 1.45 1.45 1.45
PLUOOS + A 1.55 1.56 1.59 PROOS+ DLO 1.43 TCVFASOOS B 1.41 1.40
+ RPTOOS + A 1.58 1.59 1.62 MSROOS+ SL0 2 TBVOOS B 1.45 1.45 1.46
1 For tau (T) = 0, use SCRAM Time Option B limits. For (r) = 1, use SCRAM Time Option A limits.\\1Wffermda'i:1;)
does not equal O or 1, use linear interpolation in accordance with site procedure to calculate OLMCPRH,n*,
2 For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed DLO value. However, a minimum SLO value of 1.45 for all fuel types is required to bound the Recirculation Pump Seizure Event (Reference 2).
Page 10of21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
Table 4-2 Power Dependent MCPR Limits (MCPRP) and Multipliers (KP)
All Fuel Types (Reference 2 - Appendix D)
Core Core Thermal Power % of rated EOOS Combination Flow 0 23 S26 >26 30 55 65 S85 >85 100 [% of Operating Limit Operating Limit rated] MCPRP MCPR Multiplier (KP)
DLO 1.278 1.266 1.188 1.130 1.056 1.000 250 2.33 2.33 2.32 BASE ?:50 2.36 2.36 2.35 <50 2.29 2.29 2.28 SLO 1.278 1.266 1.188 1.130 1.056 1.000 <50 2.32 2.32 2.31 DLO 1.278 1.266 1.188 1.130 1.056 1.000 ?:50 2.67 2.67 2.56 TBVOOS + <50 2.54 2.54 2.39 RPTOOS ~50 2.70 2.70 2.59 SLO 1.278 1.266 1.188 1.130 1.056 1.000 <50 2.57 2.57 2.42
250 2.33 2.33 2.33 PLUOOS + DLO 1.289 1.277 1.198 1.178 1.072 1.056 1.000 PROOS + <50 2.29 2.29 2.28 TCVFASOOS ?:50 2.36 2.36 2.36
+ RPTOOS SLO 1.289 1.277 1.198 1.178 1.072 1.056 1.000
<50 2.32 2.32 2.31 DLO 1.278 1.266 1.188 1.130 1.056 1.000 250 2.34 2.34 2.34 MSROOS ?:50 2.37 2.37 2.37 <50 2.30 2.30 2.30 SLO 1.278 1.266 1.188 1.130 1.056 1.000 <50 2.33 2.33 2.33
PLUOOS + 250 2.67 2.67 2.56 PROOS + DLO 1.289 1.277 1.198 1.178 1.072 1.056 1.000 TCVFASOOS <50 2.54 2.54 2.39
+ RPTOOS + 250 2.70 2.70 2.59 MSROOS + SLO 1.289 1.277 1.198 1.178 1.072 1.056 1.000 TBVOOS <50 2.57 2.57 2.42
Page 11 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
Table 4-3 Flow Dependent MCPR Limits (MCPRF)
GNF2 Fuel All Modes of Operation (Reference 2 - Appendix D)
Flow [% of rated] MCPRF Limit DLO SLO 0.0 2.01 2.04 30.0 1.78 1.81 94.2 1.29 1.32 112.0 1.29 1.32
Table 4-4 Flow Dependent MCPR Limits (MCPRF)
GNF3 Fuel All Modes of Operation (Reference 2 -Appendix Dl Flow[% of rated] MCPRF Limit DLO SLO 0.0 1.82 1.85 30.0 1.61 1.64 89.5 1.20 1.23 105.0 1.20 1.23
Table4-5 Cycle Specific SLMCPR (MCPR99.9%)
(Reference 2 - Section 11)
Flow Mode MCPR99.9% < 8500 MWd/ST ~ 8500 MWd/ST DLO 1.11 1.11 SLO 1.11 1.12
Page 12 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
5.0 LHGR Limits
Technical Specification Section 3.2.3
The LHGR limit is the product of the exposure dependent LHGR limit from Table 5-1 or 5-2 and the minimum of the LHGRFACp or the LHGRFACF from Tables 5-3 through 5-6.
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 MELLLA+ operation. The off-rated LHGR multipliers provide adequate protection for MELLLA+ operation (Reference 2 -Appendix F).
Table 5-1 LHGR Limits for U02 Fuel Rods (Reference 3, Reference 5, Reference 12)
FuelTvDe LHGR Limit fkW/ft]
GNF2 See Reference 5 Table 2-1 GNF3 See Reference 12 Table A-1
Table 5-2 LHGR Limits for Gadolinia Rods (Reference 3, Reference 5, Reference 12)
FuelType LHGR Limit [kW/ft]
GNF2 See Reference 5 Table 2-2 GNF3 See Reference 12 Table A-2
Page 13 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
Table 5-3 Power Dependent LHGR Multipliers (LHGRFACp)
GNF2 Fuel DLOand SLO Reference 2 - A endix D EOOS Combination Core Flow Core Thermal Power % of rated
[% of rated] S26 >26 55 60 85 100 BASE 2:75 0.613 0.720 0.791 0.922
<75 1.000
2:75 0.613 0.720 TBVOOS + RPTOOS <75 0.791 0.922 1.000
PLUOOS + PROOS + 2:75 0.613 0.720 TCVFASOOS + 0.740 0.831 1.000 RPTOOS <75 MSROOS ~75 0.613 0.720 0.791 0.922 1.000
<75
PLUOOS + PROOS + ~75 0.613 0.720 TCVFASOOS + RPTOOS + 0.740 0.831 1.000 MSROOS + TBVOOS <75
Table 5-4 Power Dependent LHGR Multipliers (LHGRFACp)
GNF3 Fuel DLO and SLO (Reference 2 -Appendix D)
Core Core Thermal Power [% of rated]
EOOS Combination Flow[% 0 23 S26 >26 30 55 65 85 100 of rated]
2:50 0.430 0.430 0.440 0.630 0.650 0.760 0.980 BASE <50 0.430 0.430 0.440 1.000 1.000
TBVOOS + RPTOOS ~50 0.430 0.430 0.440 0.630 0.650 0.760 0.870 0.970
<50 0.430 0.430 0.440 1.000
PLUOOS + PROOS + 2:50 0.430 0.430 0.440 0.630 0.650 0.760 0.850 TCVFASOOS + RPTOOS 0.960 1.000
<50 0.430 0.430 0.440 MSROOS ~50 0.430 0.430 0.440 0.630 0.650 0.760 0.980
<50 0.430 0.430 0.440 1.000 1.000
PLUOOS + PROOS + 2:50 0.430 0.430 0.440 I TCVFASOOS + RPTOOS + 0.630 0.650 0.760;
- 0;810 0.920 ' 1.000 MSROOS + TBVOOS <50 0.430 0.430 0.440 {. j._1*
Page 14 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
Table 5-5 Flow Dependent LHGR Multipliers (LHGRFACF)
GNF2 Fuel All Modes of Operation Reference 2 - A endix D and Table 11 EOOS Core Flow % of rated Condition 0 30 DLO 0.241 0.580 SLO 0.241 0.580
Table 5-6 Flow Dependent LHGR Multipliers (LHGRFACF)
GNF3 Fuel All Modes of Operation (Reference 2 -Appendix D and Table 11)
EOOS Core Flow [% of rated]
Condition 0 30 74.3 80 105 DLO 0.298 0.561 ~ 1.000 1.000 SLO 0.298 0.561 0.950 0.950 0.950
Page 15 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
6.0 Rod Block Monitor Setpoints
Technical Specification Section 3.3.2.1
Per Technical Specifications 3.3.2.1, the RBM instrumentation channels will be operable with the allowable values set to the values shown in Table 6-1. The values given in Table 6-1 are unfiltered; these unfiltered values are applicable since the time filter constant is set to zero. (Reference 7 -
Table 58). The RBM operability requirements have been evaluated and shown to be sufficient to ensure that the cycle-specific exposure-dependent SLMCPR and cladding 1 % plastic strain criteria will not be exceeded in the event of a Rod Withdrawal Error.
The ARTS RWE analysis validated the MCPR values in Table 6-2 below provide the required margin for full withdrawal of any control rod during Cycle 20. The RWE MCPR values have been analyzed at discrete setpoint values and unblocked (continuous withdrawal) conditions.
Table 6-1 Rod Block Monitor Setpoints 3 (Reference 2 - Section 10, Reference 8 - Section 3)
Power Level Allowable Value Nominal Trip Setpoint Analytical Limit LTSP 124.6% 124.2% 127.0%
ITSP 119.6% 119.2% 122.0%
HTSP 114.6% 114.2% 117.0%
Table 6-2 ARTS RWE Validated MCPR Values (Reference 2 - Section 10)
Power Level f% of Rated] MCPR
<90% 2!1.76 2!90% 2!1.45
3 See Reference 8 for filtered values. NMP2C20 is analyzed for the following RBM set points, which correspond to set D from Reference 8. However, the station may elect to have more restrictive state points listed in Reference 8 Section 3.
Page 16 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
7.0 Turbine Bypass Valve Parameters
Technical Specification Section 3.7.5
Per Technical Specification LCO 3.7.5, whenever the reactor power is at or above 23% RTP the main turbine bypass system shall be operable or the plant must operate with TBVOOS penalties.
The definition of operable is given in Table 7-1 below.
Table 7-1 Turbine Bypass Valve Response Time (Reference 9 - Section 1.6)
Event Response Time [sec]
Maximum delay time before start of bypass valve opening following initial turbine inlet 0.15 valve movement Maximum time after initial turbine inlet valve movement for bypass valve position to reach 0.30 80% of full flow (includes the above delay time)
Page 17 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
8.0 Modes of Operation
The following conditions are supported by the Cycle 20 licensing analysis; operation in a condition (or conditions) is controlled by station procedures. If a combination of options is not listed, it is not supported. Table 8-1 provides allowed modes of operation with thermal limit sets in the COLR. Table 8-2 provides allowed modes of operation that do not contain explicit thermal limit sets but are included in the BASE option. Table 8-3 outlines power restrictions associated with various EOOS options.
Note that per TS LCO 3.4.1, SLO in the MELLLA and MELLLA+ domains is prohibited (Reference 1). The MELLLA+ domain and the MELLLA domain upper boundary are defined in Figure 1. The MELLLA domain lower boundary is bounded by the 95% load line (Reference 4). Refer to site power flow map drawings for allowed SLO regions.
Table 8-1 Modes of Operation (Reference 2, Reference 10)
Options 4 Allowed Operatina Region BASE DLO Yes SLO Yes TBVOOS + RPTOOS 5 DLO Yes SLO Yes PLUOOS + PROOS + TCVFASOOS + DLO Yes RPTOOS SLO Yes MSROOS DLO Yes SLO Yes PLUOOS + PROOS + TCVFASOOS + DLO Yes RPTOOS + MS ROOS + TBVOOS 5 SLO Yes
Table 8-2 EOOS Conditions Included under BASE Option
{Reference 2, Reference 10)
EOOS Condition 2 SRVOOS 1 ADSOOS 1 MSIVOOS 1 TCV/TSVOOS 5
Table 8-3 Power Level Restrictions
{Reference 2 - Appendix D)
Condition Power Level Restriction [% of rated]
1 MSIVOOS s 75 1 TCV/TSVOOS s 85 MSROOS ::.92
4 The EOOS Options listed apply to both Scram Time Option A and Option B
5 TCV/TSVOOS not analyzed concurrent with TBVOOS + RPTO.OS or PLUOOS + PRO OS + TCVFASOOS + RPTOOS
+ MS ROOS + TBVOOS Page 18 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
9.0 Stability Protection
Technical Specification Section 3.3.1.1
The OPRM Amplitude Discriminator Setpoint (SAo) is 1.10 (Reference 2 - Section 15.1 ). Results have been validated with rated feedwater temperature ~ 420.5°F as described by Reference 2. Per TS 5.6.5.a.4, the Backup Stability Protection (BSP) regions and values are as shown below in Tables 9-1 and 9-2. The manual BSP region boundary endpoints are connected using the Generic Shape Function. A graphical representation of the BSP regions can be found in Reference 2 - Figure 1.
Table 9-1 BSP Endpoints for Normal Feedwater Temperature 6*7
'R f 2 T bl 4) e erence - a e Endpoint Power Flow Definition [% of rated] [% of rated]
A1 69.8 44.5 Scram Region Boundary, HFCL
B1 39.7 29.5 Scram Region Boundary, NCL
A2 64.5 50.0 Controlled Entry Region Boundary, HFCL
B2 27.5 28.9 Controlled Entry Region Boundary, NCL
Note: The BSP Boundary for Normal Feedwater Temperature is defined by the MELLLA boundary line, per Reference 2. See Figure 1 in Reference 2.
Table 9-2 Automated BSP Setpoints 6 (Reference 2 - Table 5)
Parameter - Symbol Value Slope of Automated BSP APRM flow-biased trip mrRIP 1.26 linear segment.
Automated BSP APRM flow-biased trip setpoint power intercept. Constant Power Line for Trip from PssP-TRIP 39.5% RTP zero Drive Flow to Flow Breakpoint value.
Automated BSP APRM flow-biased trip setpoint WssP-TRIP 39.2% RDF drive flow intercept. Constant Flow Line for Trip.
Flow Breakpoint value. WssP-BREAK 20.4% RDF
6 Bounding for both DLO and SLO 7 Station may elect to place additional administrative margin on the endpoints provided in Table 9-1 Page 19 of 21 Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
10.0 Power Flow Operating Map
Per MELLLA+ L TR SER Limitation and Condition 12.5.c, the MELLLA+ Power/Flow operating map*
is provided as Figure 1.
Con* Flow ~Obmibr)
0 10 30 so 60 70 so 90 100 110 120 130 l:?O+-+-....,_....,_...-........ _,_.__i--+--1-Ht--+i'-+-i-+-t-t-+-i-+-+----+-+-+-+-+-+-+-1---<-+-+--+-+--+-,__>-+-;,..-_,-t-+--+-+--H
.1,1:1,:1:,:it?
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0 -l-+-+-+--r=i=++-+-+-+-<--t-4--+-+-....... -,..+-+-+-+-+-+-<-+-s>-+-l-t-+-+-+-+-++-...... +-+-+-+--+-lf-,-,--+-+-+-+-++-+-+--+-l 0 o 10 10 30 50 70 so 90 100 110 110 Cor* Flow r**>
Figure 1: Power/Flow Operating Map for MELLLA+ in Dual Loop Operation (Reference 6)
11.0 Methodology
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the Nuclear Regulatory Commission, particularly those described in the following documents:
- 1. "General Electric Standard Application for Reactor Fuel (GESTAR II) (Supplement for United States)", NEDE-24011-P-A-31-US, November 2020. ;,_i
Page 20 of 21
- I '..
Constellation Energy Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 8 Core Operating Limits Report
12.0 References
- 1. "Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License", Constellation Document, Docket No. 50-410, Renewed License No. NPF-69.
- 2. "Supplemental Reload Licensing Report for Nine Mile Point Unit 2 Reload 19 Cycle 20", Global Nuclear Fuel Document, No. 007N4299, Revision 0, January 2024.
- 3. "Fuel Bundle Information Report for Nine Mile Point Unit 2 Reload 19 Cycle 20", Global Nuclear Fuel Document, No. 007N4300, Revision 0, January 2024.
- 4. "Nine Mile Point Nuclear Station Unit 2 Cycle 2 Equipment Out of Service Analysis", GE Nuclear Energy Document, No. EAS 18-0390 (FCMS document No. MISC167105005),
Revision 0, April 1990.
- 5. "Revised GNF2 Thermal Mechanical Operating Limits for Nine Mile Point Unit 2" Global Nuclear Fuel Document, No. 005N5546, Revision 1, January 2020.
- 6. "Safety Analysis Report for Nine Mile Point Unit 2 Maximum Extended Load Line Limit Analysis Plus", GEH Document, No. NEDC-33576P, Revision 0, October 2013.
- 7. "Revise 22A2843AM", Engineering Change Notice for NSSS161405000 "Design Spec Data Sheet, Neutron Monitoring System", Constellation Document, No. 007242, Revision 1, April 2008.
- 8. "Instrument Limits Calculation Constellation Generation Group Nine Mile Point Nuclear Station Unit 2 Rod Block Monitor (NUMAC ARTS-MELLLA)", GEH Document, No. 0000-0053-1006 NMP2 A-M-T506-RBM-Calc-2006 (FCMS document No. NSSS168805002),
Revision 1, March 2008.
- 9. "Nine Mile Point Unit 2 Cycle 20 OPL-3", Constellation TODI, No. NF230480, Revision 0, August 2023.
- 10. "GNF3 Fuel Design Cycle-Independent Analyses for Exelon Nine Mile Point Nuclear Station Unit 2", GEH Document, No. 006N6601, Revision 1, January 2022.
11. Deleted.
- 12. "GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR 11)", Global Nuclear Fuel Document, No. NEDC-33879P, Revision 4, August 2020.
004N0521-R0, September 2017.
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