ML18143B457

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Submittal of Core Operating Limits Report
ML18143B457
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/15/2018
From: Moore D
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP2L 2678
Download: ML18143B457 (22)
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~ Exelon Generation Technical Specification 5.6.5 NMP2L 2678 May 15, 2018 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 NRG Docket No. 50-410

Subject:

Core Operating Limits Report Enclosed is a copy of the Core Operating Limits Report, Revision 4, for Nine Mile Point Unit 2, Cycle 17. 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.

John Darweesh at (315) 349-7444.

Sincerely, Dennis M. Moore Regulatory Assurance Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC DMM/KJK

Enclosure:

Core Operating Limits Report, Revision 4, for Nine Mile Point Unit 2, Cycle 17 cc: NRG Regional Administrator, Region I NRG Project Manager NRG Senior Resident Inspector

Enclosure Core Operating Limits Report, Revision 4 For Nine Mile Point Unit 2, Cycle 17

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report CORE OPERATING LIMITS REPORT FOR NINE MILE POINT UNIT 2 CYCLE 17 (This is a complete re-write; no revision bars are used)

Prepared By: Date: 06-APR-18 Tae Wook Ahn Preparer, Nuclear Fuels Reviewed By: Date: 4/6/18 Megan A. Doerzbacher jlndependent Reviewer, Nuclear Fuels Reviewed By: htviJ S,- rnPJQkleK Date: _o4_I0_61_20_1s_

David S. Knepper fl Independent Reviewer, Engineering Safety Analysis Reviewed ,By: c-- ~  : (:).,__..~ Date: 'Ill /1 Y John N. Darweesh Reviewer, Reactor Engineering Approved By: Date: 10APR18 Armando R. Johnson Senior Manager, Nuclear Fuels SQR By: Date: V,fe/ lo18 Andrew M. Ross Station Qualified Reviewer Page 1 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report Table of Contents Section Page Number Summary of Revisions 3 List of Tables 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 11 6.0 Rod Block Monitor Setpoints 13 7.0 Turbine Bypass Valve Parameters 14 8.0 Modes of Operation 15 9.0 Stability Protection 16 10.0 Power Flow Operating Map 17 11.0 Methodology 17 12.0 References 18 Appendix A 19 Page 2 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report Summary of Revisions Revision Description Revision 4 New Issue for Cycle 17 Page 3 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure - GE14C 8 Table 3-2 MAPLHGR Versus Average Planar Exposure - GNF2 8 Table 3-3 MAPLHGR SLO Multiplier 8 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 9 Table 4-2 Power Dependent MCPR Limits (MCPRP) and Multipliers (KP) 10 Table 4-3 Flow Dependent MCPR Limits (MCPRF) for DLO 10 Table 4-4 Flow Dependent MCPR Limits (MCPRF) for SLO 10 Table 5-1 LHGR Limits for U02 Fuel Rods 11 Table 5-2 LHGR Limits for Gadolinia Rods 11 Table 5-3 Power Dependent LHGR Multipliers (LHGRFACP) 12 Table 5-4 Flow Dependent LHGR Multipliers (LHGRFACF) 12 Table 6-1 Rod Block Monitor Setpoints 13 Table 6-2 ARTS RWE Validated MCPR Values 13 Table 7-1 . Turbine Bypass Valve Response Time 14 Table 8-1 Modes of Operation 15 Table 8-2 EOOS Conditions Included under BASE Option 15 Table 9-1 BSP Endpoints for Normal Feedwater Temperature 16 Table 9-2 Automatic BSP Setpoints 16 Page 4 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 1.0 Terms and Definitions ADSOOS Automatic Depressurization System Out of Service APLHGR Average Planar Linear Heat Generation Rate APRM Average Power Range Monitor ARTS APRM and RBM Technical Specification Analysis BPV Bypass Valve BSP Backup Stability Protection COLR Core Operating Limits Report CRD Control Rod Drive DLO Dual Loop Operation ECCS Emergency Core Cooling System EIS Equipment in Service ELLLA Extended Load Line Limit Analysis EOC End of Cycle EOC-RPT See RPTOOS EOOS Equipment Out of Service EOR 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.

EPU Extended Power Uprate FWHOOS Feedwater Heater(s) Out of Service GEH General Electric-Hitachi GNF Global Nuclear Fuel GPM Gallons Per Minute HFCL High Flow Control Line HTSP High Trip Set Point (regarding RBM)

ICF Increased Core Flow INOP Inoperable ITSP Intermediate Trip Set Point (regarding RBM)

KP OLMCPR Multiplier LCO Limiting Condition for Operation LHGR Linear Heat Generation Rate LHGRFACF ARTS LHGR thermal limit flow dependent adjustments and multipliers LHGRFACP ARTS LHGR thermal limit power dependent adjustments and multipliers Page 5 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report LOCA Loss of Coolant Accident LTSP Low 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 MCPRF ARTS MCPR thermal limit flow dependent adjustments and multipliers MCPRP ARTS MCPR thermal limit power dependent adjustments and multipliers MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ Maximum Extended Load Line Limit Analysis Plus MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Service NCL Natural Circulation Line NRC Nuclear Regulatory Commission OLMCPR Operating Limit MCPR OPRM Oscillation Power Range Monitor PROOS Pressure Regulator Out of Service RDF Recirculation Drive Flow RPTOOS Recirculation Pump Trip Out of Service; also known as EOC-RPT RTP Rated Thermal Power (3988 MW1)

RBM Rod Block Monitor RWE Rod Withdraw Error SLMCPR Safety Limit MCPR SLO Single Loop Operation SRV Safety Relief Valve SRVOOS Safety Relief Valve Out of Service TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valve Out of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Service TS Technical Specification TSV Turbine Stop Valve TSVOOS Turbine Stop Valve Out of Service Page 6 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 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. 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 17.

OPERATING LIMIT TECHNICAL SPECIFICATION REQUIREMENTS Operating Limit Requirement APLHGR TS LCO 3.2.1 MCPR TS LCO 3.2.2 LHGR TS LCO 3.2.3 This report provides the following cycle-specific parameter limits for Nine Mile Point Unit 2 Cycle 17 (Reload 16):

  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
  • Operating Limit Minimum Critical Power Ratio (OLMCPR)
  • ARTS MCPR thermal limit adjustments and multipliers
  • Single Loop Operation (SLO) MCPR adjustment
  • Linear Heat Generation Rate (LHGR)
  • Single Loop Operation (SLO) LHGR multipliers
  • Rod Block Monitor (RBM) Analytical Limits, Allowable Values and MCPR Limits
  • Backup Stability Protection (BSP) parameters Per TS 5.6.5, these values have been determined using NRG-approved methodology and are established such that all applicable limits of the plant safety analysis are met. The limits specified in this COLR support both DLO and SLO as required by TS LCO 3.4.1 and Main Turbine Bypass System inoperable as required by TS LCO 3.7.5.

The BASE thermal limit values shown in 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).
  • Coastdown operation down to 40%
  • Page 7 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 3.0 MAPLHGR Limits The MAPLHGR limits obtained from the ECCS analysis are provided in Table 3-1 and Table 3-2. 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 MAPLHGR multipliers, MAPFACP and MAPFACF, are set to unity for all power and flow conditions per Reference 2 - Section 16.

Table 3-1 MAPLHGR Versus Average Planar Exposure GE14C (Reference 2 - Table 16.3-1}

Average Planar Exposure [GWD/ST] MAPLHGR Limit [KW/ft]

0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 Table 3-2 MAPLHGR Versus Average Planar Exposure GNF2 (Reference 2 - Table 16.3-2)

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 3-3 MAPLHGR SLO Multiplier All Fuel Types (Reference 2 - Table 16.3-3)

Fuel Type SLO Multiplier GE14C 0.78 GNF2 0.78 Page 8 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 4.0 MCPR Limits 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. The calculation of Tau shall be performed in accordance with site procedures.

ARTS power dependent thermal limits have been confirmed for operation with Equipment In-Service (EIS), Turbine Bypass Valves Out-Of-Service (TBVOOS), Recirculation Pump Trip Out-Of-Service (RPTOOS) and Pressure Regulator Out-Of-Service (PROOS).

Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

All Fuel Types (Reference 2 - Section 11)

SCRAM Time Cycle Exposure EOOS Combination Option <EOR-2017 MWD/ST ~EOR-2017 MWD/ST A 1.65 1.67 BASE B 1.45 1.47 A 1.67 1.69 BASE SLO B 1.48 1.49 A 1.72 1.72 TBVOOS B 1.49 1.49 A 1.74 1.74 T.BVOOS SLO B 1.51 1.51 A 1.69 1.71 RPTOOS B 1.45 1.47 A 1.71 1.73 RPTOOS SLO B 1.48 1.49 A 1.65 1.67 PROOS B 1.45 1.47 Page 9 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 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 <26 ;;::25 55 60 85 100 EOOS Combination

[% of rated] Operating Limit Operating Limit MCPR Multiplier MCPRP (KP)

>75 >I', ,,/, -',, \ '.*'*

BASE "'

1.218 1.180 1.150 1.056 1.000 S75 2.70 2.70 2.61

>75 ' '

BASE SLO 1.218 1.180 1.150 1.056 1.000 S75 2.72 2.72 2.63

>75 '

TBVOOS ' '

1.218 1.180 1.150 1.056 1.000 S75 3.57 3.57 3.28

>75  ;::. i;~i: ' .. ' ' ~<' ' \'_'.

TBVOOS SLO 1.218 1.180 1.150 1.056 1.000 S75 3.59 3.59 3.30

>75 '

RPTOOS ,'"

1.218 1.180 1.150 1.056 1.000 S75 2.70 2.70 2.61 RPTOOS SLO

>75

    • ,,. ;>':, .v, . ,' *:,*,  ;'  :. 1.218 1.180 1.150 1.056 1.000 S75

>75 *r 2.72 I<

2.72

',cc* ,, 2.63 PROOS S75 2.70 2.70 2.61 1.218 1.180 1.172 1.056 1.000 Table 4-3 Flow Dependent MCPR Limits (MCPRF) for DLO All Fuel Types (Reference 2 - Appendix D)

Flow r% ratedl MCPRF Limit 0.0 2.04 30.0 1.81 96.8 1.29 112.0 1.29 Table 4-4 Flow Dependent MCPR Limits (MCPRF) for SLO All Fuel Types (Reference 2 - Appendix D)

Flow [% rated] MCPRF Limit 0.0 2.06 30.0 1.83 96.8 1.31 112.0 1.31 Page 10 of 20 L

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 5.0 LHGR Limits 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 GE14C See Reference 5 - Table D-2 GNF2 See Reference 11 - Table B-1 Table 5-2 LHGR Limits for Gadolinia Rods (Reference 3, Reference 5, Reference 11)

Fuel Type LHGR Limit [KW/ft]

GE14C See Reference 5 - Table D-4 GNF2 See Reference 11 - Table B-2 Page 11 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report Table 5-3 Power Dependent LHGR Multipliers (LHGRFACP)

All Fuels Types Reference 2 - A endix D EOOS Core Flow Core Thermal Power % of rated Combination [% of rated] 0 23 <26 i::26 55 60 85 100

>75 BASE

  • 0.613 0.720 0.791 0.922 1.000 S75

>75 BASE SLO 0.613 0.720 0.791 0.922 1.000 S75

>75 TBVOOS 0.613 0.720 0.791 0.922 1.000 S75

>75 TBVOOS SLO 0.613 0.720 0.791 0.922 1.000 S75

>75 0.922. 1.000 RPTOOS 0.613 0.720 0.791 S75

>75 RPTOOS SLO 0.613 0.720 0.791 0.922 1.000 S75

>75 PROOS 0.613 0.720 0.740 0.831 1.000 S75 0.495 0.495 0.502 Table 5-4 Flow Dependent LHGR Multipliers (LHGRFACF)

All Fuel Types and Modes of Operation Reference 2 - A endix D EOOS Core Flow % of rated Condition 0 30 52.7 85 112 DLO 0.420 1.000 SLO 0.420 0.625 0.780 0.780 0.780 Page 12 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 6.0 Rod Block Monitor Setpoints 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, Reference 4 - Attachment 1 Table 4-5). The RBM operability requirements have been evaluated and shown to be sufficient to ensure that the SLMCPR and cladding 1% plastic strain criteria will not be exceeded in the event of a Rod Withdraw Error.

The ARTS RWE analysis validated the MCPR values in Table 6-2 below for use in Cycle

17. The RWE MCPR values have been analyzed at discrete setpoint values and unblocked (continuous withdraw) conditions.

Table 6-1 Rod Block Monitor Setpoints 1 (Reference 2 - Section 10, Reference 6 - Section 5.1.3, Reference 8 - Section 3)

Power Level Allowable Value Nominal Trip Setpoint Analytical Limit LTSP 121.6% 121.2% 124.0%

ITSP 116.6% 116.2% 119.0%

HTSP 111.6% 111.2% 114.0%

INOP N/A N/A N/A Table 6-2 ARTS RWE Validated MCPR Values (Reference 2 - Section 10)

Power Level r% Ratedl MCPR

<90% ~1.86

~90% ~1.53 1 See Reference 8 for filtered values.

Page 13 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 7 .0 Turbine Bypass Valve Parameters 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 0.15 turbine inlet valve movement Maximum time after initial turbine inlet valve movement for bypass valve 0.30 position to reach 80% of full flow (includes the above delay time)

Page 14 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 8.0 Modes of Operation The following conditions are supported by the Cycle 17 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 or MELLLA+ domains is prohibited.

Table 8-1 Modes of Operation (Reference 2, Reference 10, Reference 12)

Options 2 Allowed Operating Region BASE Yes BASE SLO Yes TBVOOS 5 Yes TBVOOS SL05 Yes RPTOOS Yes RPTOOS SLO Yes PROOS Yes Table 8-2 EOOS Conditions Included under BASE Option (Reference 2, Reference 13)

EOOS Condition SRVOOS ADSOOS MSIVOOS3 TCV/TSVOOS4 *5 2 The EOOS Options listed apply to both Option A and Option B 3 1 MSIVOOS limited to 75% rated thermal power 4 1 TCV/TSVOOS limited to 85% rated thermal power 5 TCV/TSVOOS not analyzed concurrent with TBVOOS Page 15 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 9.0 Stability Protection 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 25.

Table 9-1 BSP Endpoints for Normal Feedwater Temperature6 *7 (Reference 2 - Table 15-2)

Power Flow Endpoint Definition r'Yo of rated] [% of rated]

A1 69.1 43.6 Scram Region Boundary, HFCL 81 39.7 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 A3 100.0 92.7 BSP Boundary Intercept, HFCL 83 79.4 69.6 BSP Boundary Intercept, MELLLA Boundary Table 9-2 Automatic BSP Setpoints 8 (Reference 2 - Table 15-3)

Parameter Symbol Value Slope of Automatic BSP APRM flow-

  • mTRIP 1.26 biased trip linear seQment Automatic BSP APRM flow-biased trip setpoint power intercept. Constant PBSP-TRIP 39.7% RTP Power Line for Trip from zero Drive Flow to Flow Breakooint value.

Automatic BSP APRM flow-biased trip setpoint drive flow intercept. Constant WesP-TRIP 36.9% RDF Flow Line for Trio.

Flow Breakpoint value WssP-BREAK 19.2% 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 8 Applicable to both DLO and SLO Page 16 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 10.0 Power Flow Operating Map See Appendix A for a Power Flow Map (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)", NEDE-24011-P-A-26, January 2018.
2. "General Electric Standard Application for Reactor Fuel (GESTAR II) (Supplement for United States)", NEDE-24011-P-A-26-US, January 2018.

Page 17 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report 12.0 References

1. "Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License",

Exelon Document, Docket No. 50-410, Renewed License No. NPF-69, Revision 20180111.01, January 2018.

2. "Supplemental Reload Licensing Report for Nine Mile Point Unit 2 Reload 16 Cycle 17", Global Nuclear Fuel Document, No. 003N8948, Revision 0, January 2018.
3. "Fuel Bundle Information Report for Nine Mile Point Unit 2 Reload 16 Cycle 17",

GNF Document, No. 003N8949, Revision 0, January 2018.

4. "Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900: Transient Analysis", GE Energy Document, No. GE-NE-0000-0055-2373-RO, Revision 0, February 2007.
5. "GE14 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR II), NEDC-32868P, Revision 6, March 2016," GNF Document, No. MFN 16-015, March 2016.
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", Exelon Document, No. 007242, Revision 1, April 2008.
8. "Instrumentation 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. "Final resolved OPL-3 parameters for NMP2 C17", Exelon Document, ENSAF ID No. ES1700015, Revision 1, September 2017.
10. "Nine Mile Point 2 GNF2 NFI T0900 Coincident Equipment Out-of-Service (EOOS)

Report", GEH Document, No. 003N2077-RO Revision 0, February 2016.

11. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)", GNF Document, No. NEDC-33270P, Revision 9, December 2017.
12. "GNF2 Fuel Design Cycle-Independent Analyses for Exelon Nine Mile Point Nuclear Station Unit 2", GEH Document, No. 003N2003 Revision 3, September 2017.
13. "Nine Mile Point Unit 2 Option B' Scram Speed Implementation", GEH Document, No. 004N0521-RO, September 2017.

Page 18 of 20

Exelon Generation - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 4 Core Operating Limits Report Appendix A Page 19 of 20

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