NMP2L2878, Core Operating Limits Report

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Core Operating Limits Report
ML24136A128
Person / Time
Site: Nine Mile Point Constellation icon.png
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.

NMP2L2878 April 16, 2024 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 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 Prepared By:

Reviewed By:

Reviewed By:

Reviewed By:

Approved By:

SQR By:

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 2024.02.12 12:46:14 -05'00' Kelly McClure Preparer, Nuclear Fuels P tt R b C

Digitally signed by Potter, Robert C.

Q er Q ert

  • DN:cn=Potter,RobertC.

I Date:2024,02.1214:11:01 *0S'00' Robert Potter Reviewer, Nuclear Fuels Digitally signed by Norman, Timothy Date: 2024,02 J 2 J 3-J 4*4J -06'00*

Timothy Norman Reviewer, Engineering Safety Analysis Kl*m Andrew J1"n DigltallyslgnedbyKlm,AndrewJln Date: 2024;02.12 14:19:45 -05'00' Andrew Kim Reviewer, Reactor Engineering

~ Ao/

Kristin Mccoskey Digitally signed by Mccoskey, Kristin Date: 2024.02.16 13:05:31 -06'00' Senior Manager, Nuclear Fuels Darweesh John N DlgitallyslgnedbyDarweesh,JohnN Date: 2024.02.27 10:47:37 -os*oo*

John Darweesh Station Qualified Reviewer Page 1 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Section Summary of Revisions List of Tables / Figures 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. 8 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 8 Document ID: COLR Nine Mile Point 2, Rev. 8 Summary of Revisions Description New Issue for Cycle 20 Page 3 of 21

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 List of Tables/ Figures Table 3-1 MAPLHGR Versus Average Planar Exposure, GNF2 Fuel Table 3-2 MAPLHGR Versus Average Planar Exposure, GNF3 Fuel Table 3-3 MAPLHGR SLO Multiplier, All Fuel Types Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR), All Fuel Types Table 4-2 Power Dependent MCPR Limits (MCPRP) and Multipliers (Kp), All Fuel Types Table 4-3 Flow Dependent MCPR Limits (MCPRF), GNF2 Fuel Table 4-4 Flow Dependent MCPR Limits (MCPRF), GNF3 Fuel Table 4-5 Cycle Specific SLMCPR (MCPR99.9%)

Table 5-1 LHGR Limits for UO2 Fuel Rods Table 5-2 LHGR Limits for Gadolinia Rods Table 5-3 Power Dependent LHGR Multipliers (LHGRFACp), GNF2 Fuel, DLO and SLO Table 5-4 Power Dependent LHGR Multipliers (LHGRFACp), GNF3 Fuel, DLO and SLO Table 5-5 Flow Dependent LHGR Multipliers (LHGRFACF), GNF2 Fuel, All Modes of Operation Table 5-6 Flow Dependent LHGR Multipliers (LHGRFACF), GNF3 Fuel, All Modes of Operation Table 6-1 Rod Block Monitor Setpoints Table 6-2 ARTS RWE Validated MCPR Values Table 7-1 Turbine Bypass Valve Response Time Table 8-1 Modes of Operation Table 8-2 EOOS Conditions Included under BASE Option Table 8-3 Power Level Restrictions Table 9-1 BSP Endpoints for Normal Feedwater Temperature Table 9-2 Automated BSP Setpoints Figure 1 Power/Flow Operating Map for MELLLA+ in Dual Loop Operation;."

Page 4 of 21 8

8 10 11 12 12 12 13 13 14 14 15 15 16 16 17 18 18 18 19 19 20

ConstellaUon Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 1.0 Terms and Definitions ADS ADSOOS APLHGR APRM ARTS BSP COLR DLO ECCS EIS EOOS EOR EPU GEH GNF HFCL HTSP ICF

!TSP KP LCO LHGR LHGRFACF LHGRFACP LOCA LTR 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 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 Licensing Topical Report 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. 8 MCPRP MELLLA MELLLA+

MSIVOOS MSROOS NCL NRC OLMCPR OPRM PLUOOS PROOS RBM RDF RPTOOS RTP RWE SER 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-RPTOOS Rated Thermal Power (3988 MW1)

Rod Withdrawal Error Safety Evaluation Report 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 (Reference 10).

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. 8 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)

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.

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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 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 21.22 40.82 57.60 63.50 Table 3-3 MAPLHGR SLO Multiplier All Fuel Types (Reference 2-Table 11) 14.36 13.01 10.75 8.00 6.00 Fuel Type SLO Multiplier 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. 8 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
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 4-5 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 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 Option1 MWd/ST MWd/ST A

1.47 1.47 DLO 8

1.41 1.34 BASE A

1.50 1.50 SL02 8

1.45 1.45 A

1.52 1.52 DLO TBVOOS +

B 1.41 1.36 RPTOOS A

1.55 1.55 SL02 B

1.45 1.45 A

1.47 1.47 PLUOOS +

DLO PROOS +

B 1.41 1.34 TCVFASOOS A

1.50 1.50

+ RPTOOS SL02 B

1.45 1.45 A

1.51 1.51 DLO 8

1.41 1.37 MSROOS A

1.54 1.54 SL02 B

1.45 1.45 PLUOOS +

A 1.55 1.56 PROOS+

DLO TCVFASOOS B

1.41 1.40

+ RPTOOS +

A 1.58 1.59 MSROOS+

SL02 TBVOOS B

1.45 1.45

~ EOR-3782 MWd/ST 1.50 1.37 1.53 1.45 1.55 1.39 1.58 1.45 1.50 1.37 1.53 1.45 1.55 1.41 1.58 1.45 1.59 1.43 1.62 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 MCPR Multiplier (KP) rated]

MCPRP 250 2.33 2.33 2.32 DLO 1.278 1.266 1.188 1.130 1.056 1.000

<50 2.29 2.29 2.28 BASE

?:50 2.36 2.36 2.35 SLO 1.278 1.266 1.188 1.130 1.056 1.000

<50 2.32 2.32 2.31

?:50 2.67 2.67 2.56 DLO 1.278 1.266 1.188 1.130 1.056 1.000 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 2.31 250 2.34 2.34 2.34 DLO 1.278 1.266 1.188 1.130 1.056 1.000

<50 2.30 2.30 2.30 MSROOS

?:50 2.37 2.37 2.37 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 EOOS Combination BASE TBVOOS + RPTOOS PLUOOS + PROOS +

TCVFASOOS +

RPTOOS MSROOS PLUOOS + PROOS +

TCVFASOOS + RPTOOS +

MSROOS + TBVOOS 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 DLOand SLO Reference 2 - A endix D Core Flow Core Thermal Power % of rated

[% of rated]

S26

>26 55 2:75 0.613 0.720

<75 2:75 0.613 0.720

<75 2:75 0.613 0.720

<75

~75 0.613 0.720

<75

~75 0.613 0.720

<75 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 Core Core Thermal Power [% of rated]

Flow[%

0 23 S26

>26 30 55 65 of rated]

2:50 0.430 0.430 0.440 0.630 0.650 0.760 0.980

<50 0.430 0.430 0.440

~50 0.430 0.430 0.440 0.630 0.650 0.760 0.870

<50 0.430 0.430 0.440 2:50 0.430 0.430 0.440 0.630 0.650 0.760 0.850

<50 0.430 0.430 0.440

~50 0.430 0.430 0.440 0.630 0.650 0.760 0.980

<50 0.430 0.430 0.440 2:50 0.430 0.430 0.440 I

0.630 0.650 0.760; 85 0.922 0.922 0.831 0.922 0.831 85 1.000 0.970 0.960 1.000

  • 0;810 0.920

<50 0.430 0.430 0.440

{

j

._1*

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. 8 EOOS Condition DLO SLO EOOS Condition DLO SLO Table 5-5 Flow Dependent LHGR Multipliers (LHGRFACF)

GNF2 Fuel 0

0.241 0.241 All Modes of Operation Reference 2 - A endix D and Table 11 30 0.580 0.580 Core Flow % of rated Table 5-6 Flow Dependent LHGR Multipliers (LHGRFACF)

GNF3 Fuel All Modes of Operation (Reference 2 -Appendix D and Table 11)

Core Flow [% of rated]

0 30 74.3 80 0.298 0.561

~ 1.000 0.298 0.561 0.950 0.950 Page 15 of 21 105 1.000 0.950

Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 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.

Power Level LTSP ITSP HTSP Table 6-1 Rod Block Monitor Setpoints3 (Reference 2 - Section 10, Reference 8 - Section 3)

Allowable Value Nominal Trip Setpoint 124.6%

124.2%

119.6%

119.2%

114.6%

114.2%

Table 6-2 ARTS RWE Validated MCPR Values (Reference 2 - Section 10)

Analytical Limit 127.0%

122.0%

117.0%

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 Core Operating Limits Report 7.0 Turbine Bypass Valve Parameters Technical Specification Section 3.7.5 Document ID: COLR Nine Mile Point 2, Rev. 8 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 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)

Options4 Allowed Operatina Region BASE DLO SLO TBVOOS + RPTOOS5 DLO SLO PLUOOS + PROOS + TCVFASOOS +

DLO RPTOOS SLO MSROOS DLO SLO PLUOOS + PROOS + TCVFASOOS +

DLO RPTOOS + MS ROOS + TBVOOS5 SLO Table 8-2 EOOS Conditions Included under BASE Option

{Reference 2, Reference 10)

EOOS Condition 2 SRVOOS 1 ADSOOS 1 MSIVOOS 1 TCV/TSVOOS5 Table 8-3 Power Level Restrictions

{Reference 2 - Appendix D)

Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes 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 Core Operating Limits Report 9.0 Stability Protection Technical Specification Section 3.3.1.1 Document ID: COLR Nine Mile Point 2, Rev. 8 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 Temperature6*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 Setpoints6 (Reference 2 - Table 5)

Parameter Symbol Slope of Automated BSP APRM flow-biased trip mrRIP 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 6 Bounding for both DLO and SLO Value 1.26 39.5% RTP 39.2% RDF 20.4% RDF 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 Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 8 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 110 100 90 so 20

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  • 500 10 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 Core Operating Limits Report 12.0 References Document ID: COLR Nine Mile Point 2, Rev. 8
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.
13. "Nine Mile Point Unit 2 Option B' Scram Speed Implementation", GEH Document, No.

004N0521-R0, September 2017.

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