NMP2L2807, Core Operating Limits Report

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Core Operating Limits Report
ML22105A066
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 04/07/2022
From: Shultz B
Constellation Energy Generation
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP2L2807
Download: ML22105A066 (1)
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Text

Constellation NMP2L2807 April 7, 2022 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-001

Subject:

Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410 Core Operating Limits Report Technical Specification 5.6.5 Enclosed is a copy of the Core Operating Limits Report, Revision 7, for Nine Mile Point Unit 2 Cycle 19. 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: 2022.04.07 10:49:31 -04'00' Brandon K. Shultz Mgr. Site Regulatory Assurance, Nine Mile Point Nuclear Station Constellation Energy Generation Company, LLC

Enclosure:

Core Operating Limits Report, Revision 7 for Nine Mile Point Unit 2, Cycle 19 cc:

NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector

Enclosure Core Operating Limits Report, Revision 7 for Nine Mile Point Unit 2, Cycle 19

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 Prepared By:

Reviewed By:

Reviewed By:

Reviewed By:

Approved By:

SQR By:

CORE OPERA TING LIMITS REPORT FOR NINE MILE POINT UNIT 2 CYCLE 19 (This is a complete re-write; no revision bars are used)

\\( Qureshi, Ferheen

/*.

l'.i/__:2022.02.2~1~96:01 -05'00' Fer he en Qureshi Preparer, Nuclear Fuels 2022.02.28 14:07:56 -06'00' Date: -----

Magdalena R. Mclynden Independent Reviewer, Nuclear Fuels Bergmann, Brian C.

)

,,rngitally signed by Bergmann, Brian C.

~sate: 2022.02.28 14:14:02-06'00' Date: -----

Brian C. Bergmann Independent Reviewers, Engineering Safety Analysis L, /;,u

~ Digitally signed by Kelsey, Eric A

~

~~-- I \\Qate: 2022.02.28 15:49:38 f -----,

,/ - -05'00' Date: -----

Eric A. Kelsey Reviewer, Reactor Engineering Kova Cs Ash I e

\\}\\Digitally signed by Kovacs, Ashley 1

J-0ate: 2022.03.01 21 :17:54-06'00' 10' Date: -----

Ashley Kovacs Senior Manager, Nuclear Fuels L%~-----

~ Digitally signed by Kelsey, Eric A v\\

/-19ate: 2022.03.02 09:45:24 -05'00' u

Date: -----

Eric A. Kelsey Station Qualified Reviewer Page 1 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Section Summary of Revisions List of Tables 1.0 Terms and Definitions 2.0 General Information 3.0 MAPLHGR Limits 4.0 MCPR Limits 5.0 LHGR Limits Table of Contents 6.0 Rod Block Monitor Setpoints 7.0 Turbine Bypass Valve Parameters 8.0 Modes of Operation 9.0 Stability Protection 10.0 Power Flow Operating Map 11.0 Methodology 12.0 References Page 2 of 21 Document ID: COLR Nine Mile Point 2, Rev. 7 Page Number 3

4 5

7 8

9 13 16 17 18 19 20 20 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Revision Revision 7 Document ID: COLR Nine Mile Point 2, Rev. 7 Summary of Revisions Description New Issue for Cycle 19 Page 3 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure, GNF2 Fuel 8

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) for DLO, GNF2 Fuel 12 Table 4-4 Flow Dependent MCPR Limits (MCPRF) for DLO, GNF3 Fuel 12 Table 4-5 Flow Dependent MCPR Limits (MCPR.F) for SLO, GNF2 Fuel 12 Table 4-6 Flow Dependent MCPR Limits (MCPRF) for SLO, GNF3 Fuel 12 Table 4-7 Cycle Specific SLMCPR (MCPR99.9%)

12 Table 5-1 LHGR Limits for U02 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 9-1 BSP Endpoints for Normal Feedwater Temperature 19 Table 9-2 Automated BSP Setpoints 19 Page 4 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 1.0 Terms and Definitions ADS ADSOOS APLHGR APRM ARTS BSP COLR DLO ECCS EIS EOOS EOR EPU GEH GNF HFCL HTSP ICF INOP ITSP LCO LHGR LHGRFACF LHGRFACP LOCA LTSP MAPFACF MAPFACP MAPLHGR MCPR MCPR99.9%

MCPRF Automatic Depressurization System Automatic Depressurization System Out of Service. ADSOOS is defined as any ADS valve inoperable.

Average Planar Linear Heat Generation Rate Average Power Range Monitor Average Power Range Monitor, Rod Block Monitor, and Technical Specification (ARTS) improvements program Backup Stability Protection Core Operating Limits Report Dual Loop Operation Emergency Core Cooling System Equipment in Service Equipment Out of Service End of Rated. The cycle exposure at which reactor power is equal to 100% rated (3988 MWth), recirculation flow equal to 100% rated (108.5 Mlb/hr), and all control blades are fully withdrawn with equilibrium xenon.

Extended Power Uprate General Electric-Hitachi Global Nuclear Fuel High Flow Control Line High Power Trip Set Point (regarding RBM)

Increased Core Flow Inoperable Intermediate Power Trip Set Point (regarding RBM)

Off-rated power dependent OLMCPR multiplier Limiting Condition for Operation Linear Heat Generation Rate Off-rated flow dependent LHGR multiplier Off-rated power dependent LHGR multiplier Loss of Coolant Accident Low Power Trip Set Point (regarding RBM)

Off-rated flow dependent MAPLHGR multiplier Off-rated power dependent MAPLHGR multiplier Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio 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.

Off-rated flow dependent OLMCPR Page 5 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report l;)ocument ID: COLR Nine Mile Point 2, Rev. 7 MCPRP MELLLA MELLLA+

MSIVOOS MSROOS NCL NRC OLMCPR OPRM PLUOOS PROOS RBM RDF RPTOOS RTP RWE SLMCPR SLO SRVOOS TBV TBVOOS TCV TCVFASOOS TCVOOS TS TSV TSVOOS Off-rated power dependent OLMCPR Maximum Extended Load Line Limit Analysis

. Maximum Extended Load Line Limit Analysis Plus Main Steam Isolation Valve Out of Service Moisture Separator Reheater Out of Service Natural Circulation Line Nuclear Regulatory Commission Operating Limit MCPR Oscillation Power Range Monitor Power Load Unbalance Out of Service Pressure Regulator Out of Service Rod Block Monitor Recirculation Drive Flow Recirculation Pump Trip Out of Service; also known as EOC-RPT Rated Thermal Power (3988 MW1)

Rod Withdrawal Error Safety Limit MCPR Single Loop Operation Safety ReliefValve(s) Out of Service Turbine Bypass Valve 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.

Turbine Control Valve Turbine Control Valve Fast Acting Solenoid Out of Service Turbine Control Valve Out of Service Technical Specification Turbine Stop Valve Turbine Stop Valve Out of Service Page 6 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 2.0 General Information Document ID: COLR Nine Mile Point 2, Rev. 7 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. Linear interpolation is to be used for intermediate values.

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 19.

This report provides the following cycle-specific parameter limits for Nine Mile Point Unit 2 Cycle 19 (Reload 18):

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Single Loop Operation (SLO) MAPLHGR multipliers Operating Limit Minimum Critical Power Ratio (OLMCPR)

ARTS MCPR thermal limit adjustments and multipliers Single Loop Operation (SLO) MCPR adjustment Cycle-specific SLMCPRs (MCPR99.9%)

Linear Heat Generation Rate (LHGR)

ARTS LHGR thermal limit multipliers Single Loop Operation (SLO) LHGR multipliers Rod Block Monitor (RBM) Nominal Trip Setpoints, Allowable Values and MCPR Limits 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.

ICF up to 105% 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 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 8)

Avera e Planar Ex osure GWd/ST MAPLHGR Limit 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 9) kW/ft Avera e Planar Ex osure GWd/ST MAPLHGR Limit kW/ft 0.00 21.22 40.82 57.60 63.50 Table 3-3 MAPLHGR SLO Multiplier All Fuel Types (Reference 2 - Table 10) 14.36 13.01 10.75 8.00 6.00 Fuel Type SLO Multiolier GNF2 0.78 GNF3 0.95 Page 8 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 4.0 MCPR Limits Technical Specification Sections 3.2.2, 3.3.4.1, 3.4.1, 3. 7.5 Document ID: COLR Nine Mile Point 2, Rev. 7 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 through 4-6. Table 4-3 for GNF2 fuel and Table 4-4 for GNF3 fuel are valid for DLO conditions. Table 4-5 for GNF2 fuel and Table 4-6 for GNF3 fuel are valid for SLO conditions.

ARTS power and flow dependent thermal limits have been confirmed for the following modes of operation:

1. Base
2. TBVOOS combined with RPTOOS (TBVOOS + RPTOOS)
3. The combination of PLUOOS, PROOS, TCVFASOOS, and RPTOOS (PLUOOS + PROOS

+ 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 4-7 for dual loop and single loop operating conditions. The values in Table 4-7 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

All Fuel Types (Reference 2 - Section 11)

SCRAM Cycle Exposure EOOS Combination Time S 1779

> 1779 MWd/ST &

MWd/ST

< EOR-4001 Option 1 MWd/ST A

1.49 1.49 BASE B

1.43 1.36 A

1.52 1.52 BASE SLO2 B

1.46 1.45 A

1.54 1.54 TBVOOS + RPTOOS B

1.43 1.38 TBVOOS + RPTOOS A

1.57 1.57 SLO2 B

1.46 1.45 PLUOOS + PROOS +

A 1.49 1.49 TCVFASOOS +

RPTOOS B

1.43 1.36 PLUOOS + PROOS +

A 1.52 1.52 TCVFASOOS +

RPTOOS SLO2 B

1.46 1.45 A

1.53 1.54 MSROOS B

1.43 1.40 A

1.56 1.57 MSROOS SLO2 B

1.46 1.45 PLUOOS + PROOS +

A 1.58 1.58 TCVFASOOS +

RPTOOS + MSROOS +

TBVOOS B

1.43 1.42 PLUOOS + PROOS +

A TCVFASOOS +

1.61 1.61 RPTOOS + MSROOS +

1.46 1.45

~ EOR-4001 MWd/ST 1.52 1.39 1.55 1.45 1.55 1.39 1.58 1.45 1.52 1.39 1.55 1.45 1.56 1.42 1.59 1.45 1.58 1.42 1.61 1.45 1 For tau (r) = 0, use SCRAM Time Option B limits. For (r) = 1, use SCRAM Time Option A limits. When tau does not equal O or 1, use linear interpolation in accordance with site procedure to calculate OLMCPR.

2 For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed DLO value. However, a minimum value of 1.45 for all fuel types is required to bound the Recirculation Pump Seizure Event (Reference 2).

Page 10 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 EOOS Combination BASE BASE SLO TBVOOS +

RPTOOS TBVOOS +

RPTOOS SLO PLUOOS +

PROOS +

TCVFASOOS +

RPTOOS PLUOOS +

PROOS +

TCVFASOOS +

RPTOOS SLO MSROOS MSROOS SLO PLUOOS +

PROOS +

TCVFASOOS +

RPTOOS +

MSROOS +

TBVOOS PLUOOS +

PROOS +

TCVFASOOS +

RPTOOS +

MSROOS +

TBVOOS SLO Table 4-2 Power Dependent MCPR Limits (MCPRp} and Multipliers (KP}

All Fuel Types (Reference 2 - Appendix D}

Core Thermal Power [% of rated Core Flow 0

23 S26

>26 30 55 65 S85

>85

[% of rated]

Operating Limit Operating Limit MCPR Multiplier (KP}

MCPRP 2:50 2.33 2.33 2.32 1.278 1.266 1.188 1.130 1.056

<50 2.29 2.29 2.28

.::50 2.36 2.36 2.35 1.278 1.266 1.188 1.130 1.056,,

'f ~

<50 2.32 2.32 2.31 2:50 2.67 2.67 2.56 1.278 1.266 1.188 1.130 1.056

<50 2.54 2.54 2.39 2:50 2.70 2.70 2.59 1.278 1.266 1.188 1.130 1.056

<50 2.57 2.57 2.42

.::50 2.33 2.33 2.33 1.289 1.277 1.198 1.178 1.072 1.056

<50 2.29 2.29 2.28 2:50 2.36 2.36 2.36 1.289 1.277 1.198 1.178 1.072 1.056

<50 2.32 2.32 2.31 2:50 2.34 2.34 2.34 1.278 1.266 1.188 1.130 1.056

<50 2.30 2.30 2.30

.::50 2.37 2.37 2.37 1.278 1.266 1.188 1.130 1.056

<50 2.33 2.33 2.33

.::50 2.67 2.67 2.56 1.289 1.277 1.198 1.178 1.072 1.056

<50 2.54 2.54 2.39 o::50 2.70 2.70 2.59 1.289 1.277 1.198 1.178 1.072 1.056

<50 2.57 2.57 2.42 Page 11 of 21 100 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 Table 4-3 Flow Dependent MCPR Limits (MCPRF) for DLO GNF2 Fuel (Reference 2 - Appendix D)

Flow [% of rated]

MCPRF Limit 0.0 2.01 30.0 1.78 94.2 1.29 112.0 1.29 Table 4-4 Flow Dependent MCPR Limits (MCPRF) for DLO GNF3 Fuel (Reference 2 - Appendix D)

Flow[% of rated]

MCPRF Limit 0.0 1.82 30.0 1.61 89.5 1.20 105.0 1.20 Table 4-5 Flow Dependent MCPR Limits (MCPRF)for SLO GNF2 Fuel (Reference 2 - Appendix D)

Flow [% of rated]

MCPRF Limit 0.0 2.04 30.0 1.81 94.2 1.32 112.0 1.32 Table 4-6 Flow Dependent MCPR Limits (MCPRF) for SLO GNF3 Fuel (Reference 2 - Appendix D)

Flow [% of rated]

MCPRF Limit 0.0 1.85 30.0 1.64 89.5 1.23 105.0 1.23 Table 4-7 Cycle Specific SLMCPR (MCPR99.9%)

I Reference 2 - Section 11)

Flow Mode MCPR99.9%

< 8500 MWd/ST

~ 8500 MWd/ST DLO 1.10 1.11 SLO 1.12 1.12 Page 12 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 5.0 LHGR Limits Technical Specification Section 3.2.3 The LHGR limit is the product of the exposure dependent LHGR limit and the minimum of the LHGRFACp or the LHGRFACF.

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).

Table 5-1 LHGR Limits for U02 Fuel Rods (Reference 3, Reference 5, Reference 11, Reference 12)

Fuel Type LHGR Limit [kW/ft]

GNF2 See Reference 5 GNF3 See Reference 12 Table 5-2 LHGR Limits for Gadolinia Rods (Reference 3, Reference 5, Reference 11, Reference 12)

Fuel Type LHGR Limit [kW/ft]

GNF2 See Reference 5 GNF3 See Reference 12 Page 13 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 EOOS Combination BASE TBVOOS + RPTOOS PLUOOS + PROOS +

TCVFASOOS +

RPTOOS MSROOS PLUOOS + PROOS +

TCVFASOOS +

RPTOOS + MSROOS

+ TBVOOS Table 5-3 Power Dependent LHGR Multipliers (LHGRFACp)

GNF2 Fuel DLO and SLO (Reference 2 - Appendix D)

Core Flow Core Thermal Power [% of rated

[% of rated]

0 23

S26

>26 55

~75 0.613 0.720

<75 0.495 0.495 0.502 f;

~75 0.613 0.720

<75 0.475 0.475 0.502

~75 0.613 0.720

<75 0.495 0.495 0.502

~75 0.613 0.720

<75 0.495 0.495 0.502

~75 0.613 0.720

<75 0.475 0.475 0.502 Table 5-4 Power Dependent LHGR Multipliers (LHGRFACP)

GNF3 Fuel DLO and SLO (Reference 2 - Appendix D) 60 0.791 0.791 0.740 0.791 0.740 85 0.922 0.922 0.831 0.922 0.831 EOOS Core Flow Core Thermal Power [% of rated]

Combination

[% of rated]

0 23

S26

>26 30 55 65 85

~50 0.430 0.430 0.440 BASE 0.630 0.650 0.760 0.980 1.000

<50 0.430 0.430 0.440 TBVOOS +

~50 0.430 0.430 0.440 RPTOOS 0.630 0.650 0.760 0.870 0.970

<50 0.430 0.430 0.440 PLUOOS + PROOS

~50 0.430 0.430 0.440

+ TCVFASOOS +

0.630 0.650 0.760 0.850 0.960 RPTOOS

<50 0.430 0.430 0.440

~50 0.430 0.430 0.440 MSROOS 0.630 0.650 0.760 0.980 1.000

<50 0.430 0.430 0.440 PLUOOS + PROOS

+ TCVFASOOS +

~50 0.430 0.430 0.440 RPTOOS +

0.630 0.650 0.760 0.810 0.920 MSROOS +

<50 0.430 0.430 0.440 TBVOOS Page 14 of 21 100 1.000 1.000 1.000 1.000 1.000 100 1.000 1.000 1.000 1.000 1.000

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 EOOS Condition DLO SLO EOOS Condition DLO SLO Table 5-5 Flow Dependent LHGR Multipliers (LHGRFACF)

GNF2 Fuel All Modes of Operation (Reference 2 -Appendix D and Table 10)

Core.Flow[% of rated' 0

30 40 52.7 85 0.241 0.580 0.693 I,.;./ ' ".., t:\\if) 1.000 0.241 0.580 0.693 0.780 0.780 Table 5-6 Flow Dependent LHGR Multipliers (LHGRFACF)

GNF3 Fuel All Modes of Operation (Reference 2 -Appendix D and Table 10)

Core Flow [% of ratedl 0

30 74.3 80 0.298 0.561

(,li\\((

    • };
  • i:. J 1.000 0.298 0.561 0.950 0.950 Page 15 of 21 105 1.000 0.950 112 1.000 0.780

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Do~ument ID: COLR Nine Mile Point 2, Rev. 7 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 as the time filter constant is set to zero. (Reference 7 - Table 5B). The RBM operability requirements have been evaluated and shown to be sufficient to ensure that the cycle specific exposure dependent SLM CPR 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 for use in Cycle 19. The RWE MCPR values have been analyzed at discrete setpoint values and unblocked (continuous withdrawal) conditions.

Table 6-1 Rod Block Monitor Setpoints3 (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 [% of Rated]

MCPR

<90%

~1.76

~90%

~1.45 3 See Reference 8 for filtered values. NMP2C19 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 Core Operating Limits Report 7.0 Turbine Bypass Valve Parameters Technical Specification Section 3.7.5 Document ID: COLR Nine Mile Point 2, Rev. 7 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 the 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 8.0 Modes of Operation The following conditions are supported by the Cycle 19 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.

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 (Ref 4). Refer to site power-flow map drawings for allowed SLO regions.

Table 8-1 Modes of Operation (Reference 2, Reference 1 Ol Options4 BASE BASE SLO TBVOOS + RPTOOS5 TBVOOS + RPTOOS SL05 PLUOOS + PROOS + TCVFASOOS + RPTOOS6 PLUOOS + PROOS + TCVFASOOS + RPTOOS SL06 MSROOS MSROOS SLO PLUOOS + PROOS + TCVFASOOS + RPTOOS +

MSROOS + TBVOOS5*6*7 PLUOOS + PROOS + TCVFASOOS + RPTOOS +

MSROOS + TBVOOS SL05*6*7 Table 8-2 Allowed Operatina Reaion Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes EOOS Conditions Included under BASE Option (Reference 2, Reference 10)

EOOS Condition8 SRVOOS ADSOOS 9 MSIVOOS10 TCV/TSVOOS5*6 4 The EOOS Options listed apply to both Option A and Option B 5 TCV/TSVOOS not analyzed concurrent with TBVOOS + RPTOOS or PLUOOS + PROOS + TCVFASOOS + RPTOOS

+ MSROOS + TBVOOS 6 1 TCV /TSVOOS limited to 85% rated thermal power.

7 MSROOS + TBVOOS is restricted to 92% power (Reference 14) 8 Base includes 2 SRVOOS, 1 MSIVOOS (limited to 75% power), 1 TCV/TSVOOS (limited to 85% power), and 1 ADSOOS 9 ADSOOS defined as 1 ADS valve out of service only in the relief function. LCO 3.5.1 (Reference 1) allows a single ADS valve inoperable for 14 days.

10 1 MSIVOOS limited to 75% rated thermal power Page 18 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 9.0 Stability Protection Technical Specification Section 3.3.1.1 Document ID: COLR Nine Mile Point 2, Rev. 7 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 Temperature11*12 Reference 2 - Table 4)

Endpoint Power Flow Definition

[% of rated]

[% of rated]

A1 70,4 45.3

. Scram Region Boundary, HFCL

  • 81 39.5 29.5 Scram Region Boundary, NCL A2 64.5 50.0 C0ntrolled Entry Region Boundary, HFCL 82 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 13 (Reference 2 - Table 5)

Parameter Symbol Slope of Automated BSP APRM flow-biased trip mTRIP linear segment.

Automated BSP APRM flow-biased trip setpoint power intercept. Constant Power Line for Trip from PssP-TRIP zero Drive Flow to Flow Breakpoint value.

Automated BSP APRM flow-biased trip setpoint WssP-TRIP drive flow intercept. Constant Flow Line for Trip.

Flow Breakpoint value.

WssP-BREAK 11 Bounding for both DLO and SLO Value 1.26 39.5% RTP 39.2% RDF 20.4% RDF 12 Station may elect to place additio.nal administrative margin on the endpoints provided in Table 9-1 13 Applicable to both DLO and SLO Page 19 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 10.0 Power Flow Operating Map Document ID: COLR Nine Mile Point 2, Rev. 7 Per M+L TR SER Limitation and Condition 12.5.c, the MELLLA+ Power/Flow operating map is provided as Figure 1.

Core Flow (21Ilbmlhr) 0 10 20 30 40 50 60 70 so 90 100 110 120 130 120 +-+-+-+-+-+-+-+-+-+--+-+-+-+-+-+-+-+-+-+-+-+--+-<--+-<i-+-i-+-,_,_ ___

+-+-+-+-+-+-+-+-+-+-+-+--+-+-+-+-+-+-+-+-+-+-+-+--+-<_....,

110 100 90 80 10* CL!P

= 3935 MW~

86.9% CL-P {Pre-EPU) = 3467 H~t 100% Core n,:.-,1

= lVS. S Mlbn/hr A:

47.9%: Pu*,.'==/ 29.5% Flcr~

B:

54.St P*y,.'f.:r/ 37.5% now C:

36. 9-% Po..,':r/ 8-0. 0%, Fl.Ch' D: 100. 0% P,;,*.,..~r/ 99. 0%- Flc-,:

E: 100. Olk P:Y,c"er/100. 0% nu... *

': 100. D!/z P.:iif.""er/105. c~ E"lcr.."

G:

96. 91 P:.it..~r/lDS. 0-k FlU.1' H:

SB. Ilk P.:i'v.':=/105.0% Flcr,.*

I: 53.Zt P:.*.. ~=/100.0%. FlC!A

.J:

22. 8% Po..._~; 55. Ola. P'lcw K:

22.St Pvwer/ 28.1% Fl~

£ L:

68. 4~ Po*.. ~=/ 55. 0% Flcr,1

..:,wt-70

  • M:

?7.6% ?o-.e=I ss.o. :le-.*

U: 100.0% Po!,_-e:r/ 85.0% =la..

ICF 4500 3500 3000 i

t 60 I

  • 2500 ~

~

Na!UCIIC:irculation / i.ow Low Recite Pump Speed i H

i

i:

~:: :~~~~;

rBorCVsMa~.Pos

/

  • -*** L... ~...... -..

., ~,,,_.. -*--**'"

2000 ~

i==

1500 1000 20 500 10 0++-+-+-t=l=+-+-+-++-+-+-H.-+-+-+-+-+-H-t--<>-+-H-+-+-H.......,>-+-+-l-+-+-+-+-+-<;-;-+-+-+-t--+-1-+-!-+-+-+-+-+-t-<--+-H0 0

10 20 30 40 50 60 70 so 90 100 110 120 Core Flow(%)

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.

Page 20 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 12.0 References Document ID: COLR Nine Mile Point 2, Rev. 7

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 Relo~d Licensing Report for Nine Mile Point Unit 2 Reload 18 Cycle 19", Global Nuclear Fuel Document, No. 006N2197, Revision 0, January 2022.

. 3. "Fuel Bundle Information Report for Nine Mile Point Unit 2 Reload 18 Cycle 19", Global Nuclear Fuel Document, No. 006N2198, Revision 0, December 2021.

4. "Nine Mile Point Nuclear Station Unit 2 Cycle 2 Equipment Out of Service Analysis", GE Nuclear Energy Document, No EAS 18-0390, 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, Revision 1, March 2008.
9. "Nine Mile Point Unit 2 Cycle 19 Completed OPL-3 Form", Constellation Document, NF210576, Revision 0, September 2021.
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. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)", Global Nuclear Fuel Document, No. NEDC-33270P, Revision 11, August 2020.
12. "GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR 11)", Global Nuclear Fuel Document, No NEDC-33879P, Revision 4, August 2020.
13. "Nine Mile Point Unit 2 Option B' Scram Speed Implementation", GEH Document, No.

004N0521-R0, September 2017.

14. "Nine Mile Point Unit 2 Cycle 19 Power Restriction with Moisture Separator Reheater Out Of Service", Global Nuclear Fuel Document, No. 006N9862-R0, February 2022.

Page 2.1 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 Prepared By:

Reviewed By:

Reviewed By:

CORE OPERA TING LIMITS REPORT FOR NINE MILE POINT UNIT 2 CYCLE 19 (This is a complete re-write; no revision bars are used) i Qureshi, Ferheen

,:f~o22.02.2&J1HiP6:01 -os*oo*

~"-----

Fer he en Qureshi Preparer, Nuclear Fuels 2022.02.28 14:07:56 -06'00' Date: -----

Magdalena R. Mclynden Independent Reviewer, Nuclear Fuels Bergmann, Br*1an C.

~rngitally signed by Bergmann, Brian c.

j-E>ate: 2022.02.28 14:14:02 -06'00' Date:

Brian C. Bergmann Independent Reviewers, Engineering Safety Analysis L //// -~~--

y Digitally signed by Kelsey, Eric A

~

/\\Qate: 2022.02:28 15:49:38

(--------:~---

Reviewed By:

// -05'00' Date: ____

Eric A. Kelsey Reviewer, Reactor Engineering Approved By:

f; Kova Cs Ash I e

,/pigitally signed by Kovacs, Ashley 1

J--E>ate: 2022.03.01 21 :17:54-06'00'

~

D~e: -----

Ashley Kovacs Senior Manager, Nuclear Fuels SQR By:

L~

f'

)

. Digitally signed by Kelsey, Eric A

~E>ate: 2022.03.02 09:45:24 -05'00' t

D~e:

Eric A. Kelsey Station Qualified Reviewer Page 1 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Section Summary of Revisions List of Tables 1.0 Terms and Definitions 2.0 General Information 3.0 MAPLHGR Limits 4.0 MCPR Limits 5.0 LHGR Limits Table of Contents 6.0 Rod Block Monitor Setpoints 7.0 Turbine Bypass Valve Parameters 8.0 Modes of Operation 9.0 Stability Protection 10.0 Power Flow Operating Map 11.0 Methodology 12.0 References Page 2 of 21 Document ID: COLR Nine Mile Point 2, Rev. 7 Page Number 3

4 5

7 8

9 13 16 17 18 19 20 20 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Revision Revision 7 Document ID: COLR Nine Mile Point 2, Rev. 7 Summary of Revisions Description New Issue for Cycle 19 Page 3 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure, GNF2 Fuel 8

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) for DLO, GNF2 Fuel 12 Table 4-4 Flow Dependent MCPR Limits (MCPRF) for DLO, GNF3 Fuel 12 Table 4-5 Flow Dependent MCPR Limits (MCPRF) for SLO, GNF2 Fuel 12 Table 4-6 Flow Dependent MCPR Limits (MCPRF) for SLO, GNF3 Fuel 12 Table 4-7 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 9-1 BSP Endpoints for Normal Feedwater Temperature 19 Table 9-2 Automated BSP Setpoints 19 Page 4 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 1.0 Terms and Definitions ADS ADSOOS APLHGR APRM ARTS BSP COLR DLO EGGS EIS EOOS EOR EPU GEH GNF HFCL HTSP ICF INOP ITSP LCO LHGR LHGRFACF LHGRFACP LOCA LTSP MAPFACF MAPFACP MAPLHGR MCPR MCPR99.9%

MCPRF Automatic Depressurization System Automatic Depressurization System Out of Service. ADSOOS is defined as any ADS valve inoperable.

Average Planar Linear Heat Generation Rate Average Power Range Monitor Average Power Range Monitor, Rod Block Monitor, and Technical Specification (ARTS) improvements program Backup Stability Protection Core Operating Limits Report Dual Loop Operation Emergency Core Cooling System Equipment in Service Equipment Out of Service 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.

Extended Power Uprate General Electric-Hitachi Global Nuclear Fuel High Flow Control Line High Power Trip Set Point (regarding RBM)

Increased Core Flow Inoperable Intermediate Power Trip Set Point (regarding RBM)

Off-rated power dependent OLMCPR multiplier Limiting Condition for Operation Linear Heat Generation Rate Off-rated flow dependent LHGR multiplier Off-rated power dependent LHGR multiplier Loss of Coolant Accident Low Power Trip Set Point (regarding RBM)

Off-rated flow dependent MAPLHGR multiplier Off-rated power dependent MAPLHGR multiplier

  • Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio 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.

Off-rated flow dependent OLMCPR Page 5 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 MCPRP MELLLA MELLLA+

MSIVOOS MSROOS NCL NRC OLMCPR OPRM PLUOOS PROOS RBM RDF RPTOOS RTP RWE SLMCPR SLO SRVOOS TBV TBVOOS TCV TCVFASOOS TCVOOS TS TSV TSVOOS Off-rated power dependent OLMCPR Maximum Extended Load Line Limit Analysis Maximum Extended Load Line Limit Analysis Plus Main Steam Isolation Valve Out of Service Moisture Separator Reheater Out of Service Natural Circulation Line Nuclear Regulatory Commission Operating Limit MCPR Oscillation Power Range Monitor Power Load Unbalance Out of Service Pressure Regulator Out of Service Rod Block Monitor Recirculation Drive Flow Recirculation Pump Trip Out of Service; also known as EOC-RPT Rated Thermal Power (3988 MWt)

Rod Withdrawal Error Safety Limit MCPR Single Loop Operation Safety Relief Valve(s) Out of Service Turbine Bypass Valve 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.

Turbine Control Valve Turbine Control Valve Fast Acting Solenoid Out of Service Turbine Control Valve Out of Service Technical Specification Turbine Stop Valve Turbine Stop Valve Out of Service Page 6 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 2.0 General Information Document ID: COLR Nine Mile Point 2, Rev. 7 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. Linear interpolation is to be used for intermediate values.

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 19.

This report provides the following cycle-specific parameter limits for Nine Mile Point Unit 2 Cycle 19 (Reload 18):

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

Single Loop Operation (SLO) MAPLHGR multipliers Operating Limit Minimum Critical Power Ratio (OLMCPR)

ARTS MCPR thermal limit adjustments and multipliers Single Loop Operation (SLO) MCPR adjustment Cycle-specific SLMCPRs (MCPR99.9%)

Linear Heat Generation Rate (LHGR)

ARTS LHGR thermal limit multipliers Single Loop Operation (SLO) LHGR multipliers Rod Block Monitor (RBM) Nominal Trip Setpoints, Allowable Values and MCPR Limits 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.

ICF up to 105% 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. 7 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 8)

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 9)

Averaae Planar Exposure [GWd/ST]

MAPLHGR Limit [kW/ft]

0.00 21.22 40.82 57.60 63.50 Table 3-3 MAPLHGR SLO Multiplier All Fuel Types (Reference 2 - Table 10) 14.36 13.01 10.75 8.00 6.00 Fuel Type I

SLO Multiplier GNF2 GNF3 Page 8 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 4.0 MCPR Limits Technical Specification Sections 3.2.2, 3.3.4.1, 3.4.1, 3. 7.5 Document ID: COLR Nine Mile Point 2, Rev. 7 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 through 4-6. Table 4-3 for GNF2 fuel and Table 4-4 for GNF3 fuel are valid for DLO conditions. Table 4-5 for GNF2 fuel and Table 4-6 for GNF3 fuel are valid for SLO conditions.

ARTS power and flow dependent thermal limits have been confirmed for the *following modes of operation:

1. Base
2. TBVOOS combined with RPTOOS (TBVOOS + RPTOOS)
3. The combination of PLUOOS, PROOS, TCVFASOOS, and RPTOOS (PLUOOS + PROOS

+ 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 4-7 for dual loop and single loop operating conditions. The values in Table 4-7 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

All Fuel Types (Reference 2 - Section 11)

SCRAM Cycle Exposure S 1779

> 1779 MWd/ST &

EOOS Combination Time MWd/ST

< EOR-4001 Option 1 MWd/ST A

1.49 1.49 BASE B

1.43 1.36 A

1.52 1.52 BASE SLO2 B

1.46 1.45 A

1.54 1.54 TBVOOS + RPTOOS B

1.43 1.38 TBVOOS + RPTOOS A

1.57 1.57 SLO2 B

1.46 1.45 PLUOOS + PROOS +

A 1.49 1.49 TCVFASOOS +

RPTOOS B

1.43 1.36 PLUOOS + PROOS +

A 1.52 1.52 TCVFASOOS +

RPTOOS SLO2 B

1.46 1.45 A

1.53 1.54 MSROOS B

1.43 1.40 A

1.56 1.57 MSROOS SLO2 B

1.46 1.45 PLUOOS + PROOS +

A 1.58 1.58 TCVFASOOS +

RPTOOS + MSROOS +

TBVOOS B

1.43 1.42 PLUOOS + PROOS +

A 1.61 1.61 TCVFASOOS +

RPTOOS + MSROOS +

TBVOOS SLO2 B

1.46 1.45

~ EOR-4001 MWd/ST 1.52 1.39 1.55 1.45 1.55 1.39 1.58 1.45 1.52 1.39 1.55 1.45 1.56 1.42 1.59 1.45 1.58 1.42 1.61 1.45 1 For tau (1) = 0, use SCRAM Time Option B limits. For (1) = 1, use SCRAM Time Option A limits. When tau does not equal O or 1, use linear interpolation in accordance with site procedure to calculate OLMCPR.

2 For single-loop operation, the MCPR operating limit is 0.03 greater than the analyzed DLO value. However, a minimum value of 1.45 for all fuel types is required to bound the Recirculation Pump Seizure Event (Reference 2).

Page 10 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 EOOS Combination BASE BASE SLO TBVOOS +

RPTOOS TBVOOS +

RPTOOS SLO PLUOOS +

PROOS +

TCVFASOOS +

RPTOOS PLUOOS +

PROOS +

TCVFASOOS +

RPTOOS SLO MSROOS MSROOS SLO PLUOOS +

PROOS +

TCVFASOOS +

RPTOOS +

MSROOS +

TBVOOS PLUOOS +

PROOS +

TCVFASOOS +

RPTOOS +

MSROOS +

TBVOOS SLO Table 4-2 Power Dependent MCPR Limits {MCPRP) and Multipliers {KP)

All Fuel Types

{Reference 2 - Appendix D)

Core Thermal Power [% of rated]

Core Flow 0

23 S26

>26 30 55 65 S85

>85

[% of rated]

Operating Limit Operating Limit MCPR Multiplier {KP)

MCPRP o::50 2.33 2.33 2.32 1.278 1.266 1.188 1.130 1.056

<50 2.29 2.29 2.28 o::50 2.36 2.36 2.35 1.278 1.266 1.188 1.130 1.056

<50 2.32 2.32 2.31 o::50 2.67 2.67 2.56 1.278 1.266 1.188 1.130 1.056

<50 2.54 2.54 2.39 o::50 2.70 2.70 2.59 1.278 1.266 1.188 1.130 1.056

<50 2.57 2.57 2.42 o::50 2.33 2.33 2.33 1.289 1.277 1.198 1.178 1.072 1.056

<50 2.29 2.29 2.28 o::50 2.36 2.36 2.36 1.289 1.277 1.198 1.178 1.072 1.056

<50 2.32 2.32 2.31 o::50 2.34 2.34 2.34 1.278 1.266 1.188 1.130 1.056

<50 2.30 2.30 2.30 o::50 2.37 2.37 2.37 1.278 1.266 1.188 1.130 1.056

<50 2.33 2.33 2.33 o::50 2.67 2.67 2.56 1.289 1.277 1.198 1.178 1.072 1.056

<50 2.54 2.54 2.39 o::50 2.70 2.70 2.59 1.289 1.277 1.198 1.178 1.072 1.056

<50 2.57 2.57 2.42 Page 11 of 21 100 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 Table 4-3 Flow Dependent MCPR Limits (MCPRF} for DLO GNF2 Fuel (Reference 2 - Aooendix D)

Flow [% of rated]

MCPRF Limit 0.0 2.01 30.0 1.78 94.2 1.29 112.0 1.29 Table 4-4 Flow Dependent MCPR Limits (MCPRF} for DLO GNF3 Fuel (Reference 2 - Appendix D)

Flow ro/o of rated]

MCPRF Limit 0.0 1.82 30.0 1.61 89.5 1.20 105.0 1.20 Table 4-5 Flow Dependent MCPR Limits (MCPRF} for SLO GNF2 Fuel (Reference 2 - Appendix D)

Flow [% of rated]

MCPRF Limit 0.0 2.04 30.0 1.81 94.2 1.32 112.0 1.32 Table 4-6 Flow Dependent MCPR Limits (MCPRF}for SLO GNF3 Fuel (Reference 2 - Appendix D)

Flow[% of rated]

MCPRF Limit 0.0 1.85 30.0 1.64 89.5 1.23

'105.0 1.23 Table 4-7 Cycle Specific SLMCPR (MCPR99.9%}

(Reference 2 - Section 11)

Flow Mode.

MCPR99.9%

< 8500 MWd/ST

~ 8500 MWd/ST DLO 1.10 1.11 SLO 1.12 1.12 Page 12 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 5.0 LHGR Limits Technical Specification Section 3.2.3 The LHGR limit is the product of the exposure dependent LHGR limit and the minimum of the LHGRFACp or the LHGRFACF.

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).

Table 5-1 LHGR Limits for U02 Fuel Rods (Reference 3, Reference 5, Reference 11, Reference 12)

Fuel Type LHGR Limit [kW/ft]

GNF2 See Reference 5 GNF3 See Reference 12 Table 5-2 LHGR Limits for Gadolinia Rods (Reference 3, Reference 5, Reference 11, Reference 12)

Fuel Type LHGR Limit [kW/ft]

GNF2 See Reference 5 GNF3 See Reference 12 Page 13 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 EOOS Combination BASE TBV00S + RPT00S PLU00S + PR00S +

TCVFAS00S +

RPT00S MSR00S PLU00S + PR00S +

TCVFAS00S +

RPT00S + MSR00S

+TBV00S Table 5-3 Power Dependent LHGR Multipliers (LHGRFACp)

GNF2 Fuel DLO and SLO (Reference 2 - Appendix D)

Core Flow Core Thermal Power [% of rated

[% of rated]

0 23 S26

>26 55 I'**,;,*.-,,,

1:,;-,

. "{'*. '

~75 Ii,c.,

'I_

'1r I-'

V*,,

0.613 0.720

<75 0.495 0.495 0.502 I'." ' : *.

~75 0.613 0.720

<75 0.475 0.475 0.502 10:,:.*>',.

',~"

~75 0.613 0.720

<75 0.495 0.495 0.502

~75 0.613 0.720

<75 0.495 0.495 0.502

~75 0.613 0.720

<75 0.475 0.475 0.502 Table 5-4 Power Dependent LHGR Multipliers (LHGRFACp)

GNF3 Fuel DLO and SLO (Reference 2 - Appendix D) 60 0.791 0.791 0.740 0.791 0.740 EOOS Core Flow Core Thermal Power r% of rated]

Combination

[% of rated]

0 23 S26

>26 30 55 65

~50 0.430 0.430 0.440 BASE 0.630 0.650 0.760 0.980

<50 0.430 0.430 0.440 TBV00S +

~50 0.430 0.430 0.440 RPT00S 0.630 0.650 0.760 0.870

<50 0.430 0.430 0.440 PLU00S + PRO0S

~50 0.430 0.430 0.440

+ TCVFAS00S +

0.630 0.650 0.760 0.850 RPT00S

<50 0.430 0.430 0.440

~50 0.430 0.430 0.440 MSR00S 0.630 0.650 0.760 0.980

<50 0.430 0.430 0.440 PLU00S + PR00S

+ TCVFAS00S +

~50 0.430 0.430 0.440 RPT00S +

0.630 0.650 0.760 0.810 MSR00S +

<50 0.430 0.430 0.440 TBV00S Page 14 of 21 85 100 0.922 1.000 0.922 1.000 0.831 1.000 0.922 1.000 0.831 1.000 85 100 1.000 1.000 0:910 1.000 0.960 1.000 1.000 1.000 0.920 1.000

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 EOOS Condition DLO SLO EOOS Condition DLO SLO Table 5-5 Flow Dependent LHGR Multipliers (LHGRFACF)

GNF2 Fuel All Modes of Operation (Reference 2 -A endix D and Table 10 Core Flow % of rated 0

30 40 52.7 85 0.241 0.580 0.693 1.000 0.241 0.580 0.693 0.780 0.780 Table 5-6 Flow Dependen t LHGR Multipliers (LHGRFACF)

GNF3 Fuel All Modes of Operation (Reference 2 -A endix D and Table 10 Core Flow % of rated 0

3 0 7~3 80 0.298

0. 561 1.000 0.298
0. 561 0.950 0.950 Page 15 of 21 105 1.000 0.950 112 1.000 0.780

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 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 as the time filter constant is set to zero. (Reference 7 - Table 58). The RSM operability requirements have been evaluated and shown to be sufficient to ensure that the cycle specific exposure dependent SLM CPR 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 Tabl~ 6-2 below for use in Cycle 19. The RWE MCPR values have been analyzed at discrete setpoint values and unblocked (continuous withdrawal) conditions.

Table 6-1 Rod Block Monitor Setpoints3 (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 [% of Rated]

MCPR

<90%

~1.76

~90%

~1.45 3 See Reference 8 for filtered values. NMP2C19 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 Core Operating Limits Report 7.0 Turbine Bypass Valve Parameters Technical Specification Section 3.7.5 Document ID: COLR Nine Mile Point 2, Rev. 7 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 the 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 Res onse Time sec Maximum delay time before start of bypass valve opening following initial turbine inlet

'valve movement Maximum time after initial turbine inlet valve movement for bypass valve position to reach 80% of full flow (includes the above delay time Page 17 of 21 0.15 0.30

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 7 8.0 Modes of Operation The following conditions are supported by the Cycle 19 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.

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 (Ref 4). Refer to site power-flow map drawings for allowed SLO regions.

Table 8-1 Modes of Operation (Reference 2, Reference 1 Ol Ootions4 BASE BASE SLO TBVOOS + RPTOOS 5 TBVOOS + RPTOOS SL05 PLUOOS + PROOS + TCVFASOOS + RPTOOS6 PLUOOS + PROOS + TCVFASOOS + RPTOOS SL06 MSROOS MSROOS SLO PLUOOS + PROOS + TCVFASQOS + RPTOOS +

MSROOS + TBVOOS5*6*7 PLUOOS + PROOS + TCVFASOOS + RPTOOS +

MSROOS + TBVOOS SLQ5,6,7 Table 8-2 Allowed Operating Region Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes EOOS Conditions Included under BASE Option (Reference 2, Reference 10)

EOOS Condition8 SRVOOS ADS00S 9 MSIV00S10 rcvrrsvoos5*6 4 The EOOS Options listed apply to both Option A and Option B S TCVrrsvoos not analyzed concurrent with TBVOOS + RPTOOS or PLUOOS + PROOS + TCVFASOOS + RPTOOS

+ MS ROOS + TBVOOS 6 1 TCV/TSVOOS limited to 85% rated thermal power.

7 MSROOS + TBVOOS is restricted to 92% power (Reference 14) 8 Base includes 2 SRVOOS, 1 MSIVOOS (limited to 75% power), 1 Tcvrrsvoos (limited to 85% power), and 1 ADSOOS 9 ADSOOS defined as 1 ADS valve out of service only in the relief function. LCO 3.5.1 (Reference 1) allows a single ADS valve inoperable for 14 days.

10 1 MSIVOOS limited to 75% rated thermal power Page 18 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 9.0 Stability Protection Technical Specification Section 3.3.1.1 Document ID: COLR Nine Mile Point 2, Rev. 7 The OPRM Amplitude Discriminator Setpoint (SAo) is 1.1 O (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 Temperature11*12 Reference 2 - Table 4)

Endpoint Power Flow Definition

[% of rated]

[% of rated]

A1 70.4 45.3 Scram Region Boundary, HFCL 81 39.5 29.5 Scram Region Boundary, NCL A2 64.5 50.0 Controlled Entry Region Boundary, HFCL 82 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 13 (Reference 2 - Table 5)

Parameter Symbol Slope of Automated BSP APRM flow-biased trip mTRIP linear segment.

Automated BSP APRM flow-biased trip setpoint power intercept. Constant Power Line for Trip from PBSP-TRIP zero Drive Flow to Flow Breakpoint value.

Automated BSP APRM flow-biased trip setpoint WBSP-TRIP drive flow intercept. Constant Flow Line for Trip.

Flow Breakpoint value.

WBSP-BREAK 11 Bounding for both DLO and SLO Value 1.26 39.5% RTP 39.2% RDF 20.4% RDF 12 Station may elect to place additional administrative margin on the endpoints provided in Table 9-1 13 Applicable to both DLO and SLO Page 19 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 10.0 Power Flow Operating Map Document ID: COLR Nine Mile Point 2, Rev. 7 Per M+LTR SER Limitation and Condition 12.5.c, the MELLLA+ Power/Flow operating map is provided as Figure 1.

Core Flow (Mlbmlbr) 0 10 20 30 40 50 60 70 80 90 llO 120 130 120 ++++-+-+""'"+-+-+-+-+-+-+-+-t-+-<-+-<-H>-+->-+-t-+-+-+--H-+-+-+-+-+-+-+++++-+-+-+++-++-+-+-+-+--+-'-+-'-+-!~H-1-+-+-I 110 100% CLTP c:

392S !ffi~

86.9-\\ Cl"l"P (Pre:-EP"JJ = 34'67 Hh"t 100~ Coro: Flo-J

= 103. 5 Mlli::L/h::

A:

47.9\\ Po"J.":r./ 29.5% Flo.,,

100 B:

54. 5\\ P.:r,;;:/ 37. 5% F!.o-.,..

c:

86. 91 p.j-,.,;::::/ eo. O\\: Fla...
  • D: 100. Ot-Frr,:er/ 99. 0% Fl.o-..
  • 90 *
i~~
g: ::~~~i~;: g: ~i:

G;

86. 91 P:i"'"::::::/105.0\\ Flc.,,.

H:

59. 7% ?:i-,.-=:::/105.43%.Flo-a*

80 I:

S3. 2% P.:r.. ~:::/100. 0% F1..v,1

.J:

22. Et Po*..,'::/ 55. <J% Flw K:
22. et P~;::;:r I 28. 1% F.!.C"... *

~ 70 d

L:

ee. 4~ p.~..,':.-=I ss. oi FlO'....

M:

77.6% Po.-,,r/ SS.0% nc-.

n: 100. O\\ Po;:::::/ es. o-t no~

~

50 t-40 20 10

      • i*" *----

MEl.l.l.A+ Bound")*

I l

... iiE{'

. djcy..

... i.......

JH7l1Wt I

--i 0 -t-+-+-+--t='l=+-1-t-+-t--+-+--t-4-!-t-+-+-+-t---+--+-1-+-!--+-+-+-t-+--+-1-+-t-+--+-+-+-+--t--<-+-<--+-+-+........ -+-!1-+-+-+-++-t-t-t-t-+

0 10 20 30 40 50 60 70 so 90 100 110 120 Core Flow(%)

4500 3500 3000

~

2500 ~

~

=

2000 ~

f'.::

1500 1000 500 0

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.

Page 20 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report 12.0 References Document ID: COLR Nine Mile Point 2, Rev. 7

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 18 Cycle 19", Global Nuclear Fuel Document, No. 006N2197, Revision 0, January 2022.
3. "Fuel Bundle Information Report for Nine Mile Point Unit 2 Reload 18 Cycle 19", Global Nuclear Fuel Document, No. 006N2198, Revision 0, December 2021.
4. "Nine Mile Point Nuclear Station Unit 2 Cycle 2 Equipment Out of Service Analysis", GE Nuclear Energy Document, No EAS 18-0390, 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, Revision 1, March 2008.
9. "Nine Mile Point Unit 2 Cycle 19 Completed OPL-3 Form", Constellation Document, NF210576, Revision 0, September 2021.
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. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR 11)", Global Nuclear Fuel Document, No. NEDC-33270P, Revision 11, August 2020.
12. "GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR 11)\\ Global Nuclear Fuel Document, No NEDC-33879P, Revision 4, August 2020.
13. "Nine Mile Point Unit 2 Option B' Scram Speed Implementation", GEH Document, No.

004N0521-R0, September 2017.

14. "Nine Mile Point Unit 2 Cycle 19 Power Restriction with Moisture Separator Reheater Out Of Service", Global Nuclear Fuel Document, No. 006N9862-R0, February 2022.

Page 21 of 21.

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