ML18058A739

Nine Mile Point, Unit 2, Submittal of Core Operating Limits Report

ML18058A739
Person / Time
Site:	Nine Mile Point
Issue date:	02/12/2018
From:	Moore D M Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP2L 2668
Download: ML18058A739 (25)

Text

r :* ~,&!!~::7 Exelon Generation NMP2L 2668 February 12, 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 NRC Docket No. 50-410 .

Subject:

Core Operating Limits Report Technical Specification 5.6.5 Enclosed is a copy of the Core Operating Limits Report, Cycle 16, Revision 3, for Nine Mile Point Unit 2 (NMP2). 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) 349-7 444. Dennis M. Moore Regulatory Assurance Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC DMM/KJK

Enclosure:

Core Operating Limits Report for Nine Mile Point Unit 2, Cycle 16, Revision 3 cc: NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector Enclosure Core Operating Limits Report For Nine Mile Point Unit 2, Cycle 16, Revision 3 Exelon Genera lion -Nuclear Fuels Core Operating Limits Report Document ro: COLR Nine Mlle Point 2, Rav. 3 Prepared By: Reviewed By: Reviewed By: CORE OPERATING LIMITS REPORT fOR NINE MILE POINT UNIT 2 CYCLE 16 # -.~,,_ // Date: Tae WookAhn Preparer, Nuclear Fuels Date: Corie A. Glenn Independent Reviewer, Nuclear Fuels ba.lliJ Si: ~f /!,Y Date: David S. Knepper Independent Reviewer, Engineering Safety Analysis 18-JAN-18 } ), g )Ji ' 01/18/2018 Reviewed By:......___ :S: ~0-r~ John N. Darweesh "-Date: l/!'?//J Approved By: Date: 19:JAN IF> Senior Manager, Nuclear Fuels SQR By: Date: January 19,2018 :.i.ndrew M. Ross Station Qualified Reviewer Page 1 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Table of Contents Section. Revision History List of Tables 1.0 Terms and Definitions 2.0 General Information 3.0 MAPLHGR Limits 4.0 MCPR Limits 5.0 LHGR Limits 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 Appendix A Appendix B Page 2 of 23 Document ID: COLR Nine Mile Point 2, Rev. 3 Page Number 3 4 5 7 8 9 12 14 15 15 16 17 17 18 20 22 Exelon Generation -Nuclear Fuels Core Operating Limits Report Revision Revision 3 Revision 2 Revision 1 Revision 0 Document ID: COLR Nine Mile Point 2, Rev. 3 Revision History Description Revised to reflect measured scram time results for Equipment In Service and Turbine Bypass Valve Out Of Service options New Issue for Cycle 16 Revised to reflect MELLLA+ Implementation New Issue for Cycle 15 Page 3 of 23 I . I Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 Table# Table 3-1 Table 3-2 Table 3-3 Table 4-1 Table 4-2 Table 4-3 Table 4-4 Table 5-1 Table 5-2 Table 5-3 Table 5-4 Table 6-1 Table 6-2 Table 7-1 Table 8-1 Table 9-1 Table 9-2 List of Tables Table Name MAPLHGR Versus Average Planar Exposure -GE14C MAPLHGR Versus Average Planar Exposure -GNF2 . MAPLHGR SLO Multiplier Operating Limit Minimum Critical Power Ratio (OLMCPR) Power Dependent MCPR Limit Adjustments and Multipliers (MCPRP) Flow Dependent MCPR Limits (MCPRF) for DLO Flow Dependent MCPR Limits (MCPRF) for SLO LHGR Limits for U02 Fuel LHGR Limits for Gadolinia Rods Power Dependent LHGR Multiplier LHGRFACP Flow Dependent LHGR Multiplier LHGRFACF Rod Block Monitor Setpoints ARTS RWE Validated MCPR Values Turbine Bypass Valve Response Time Modes of Operation BSP Endpoints for Normal Feedwater Temperature Automatic BSP Setpoints Page 4 of 23 Page 8 8 9 10 11 11 12 12 12 13 13 14 14 15 15 16 17 Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 1.0 Terms and Definitions ADSOOS APLHGR APRM ARTS BPV BSP COLR CRD DLO ECCS EIS ELLLA EOC EOC-RPT EOOS EOR FWHOOS GEH GNF GPM HFCL HTSP ICF INOP ITSP KP LCO LHGR LHGRFACF LHGRFACP Automatic Depressurization System Out of Service Average Planar Linear Heat Generation Rate Average Power Range Monitor APRM and RBM Technical Specification Analysis Bypass Valve Backup Stability Protection Core Operating Limits Report Control Rod Drive Dual Loop Operation Emergency Core Cooling System Equipment In Service Extended Load Line Limit Analysis End of Cycle See RPTOOS. 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. Feedwater Heater(s) Out of Service General Electric-Hitachi Global Nuclear Fuel Gallons Per Minute High Flow Control Line High Trip Set Point (regarding RBM) Increased Core Flow Inoperable Intermediate Set Point (regarding RBM) OLMCPR Multiplier Limiting Condition for Operation Linear Heat Generation Rate ARTS LHGR thermal limit flow dependent adjustments and multipliers ARTS LHGR thermal limit power dependent adjustments and multipliers Page 5 of23 Exelon Generation -Nuclear Fuels Core Operating Limits Report . Document ID: COLR Nine Mile Point 2, Rev. 3 LOCA LTSP MAPFACF MAPFACP MAPLHGR MCPR MCPRF MCPRP MELLLA MELLLA+ MSIV MSIVOOS NCL NRG OLMCPR OPRM PROOS RDF RPTOOS RTP RBM RWE SLMCPR SLO SRV SRVOOS TBVOOS TS Loss of Coolant Accident Low Jrip 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 ARTS MCPR thermal limit flow dependent adjustments and multipliers ARTS MCPR thermal limit power dependent adjustments and multipliers Maximum Extended Load Line Limit Analysis Maximum Extended Load Line Limit Analysis Plus Main Steam Isolation Valve Main Steam Isolation Valve Out of Service Natural Circulation Line Nuclear Regulatory Commission Operating Limit MCPR Oscillation Power Range Monitor Pressure Regulator Out of Service Recirculation Drive Flow Recirculation Pump Trip Out of Service; also known as EOC-RPT Rated Thermal Power (3988 MWt) Rod Block Monitor Rod Withdraw Error Safety Limit MCPR Single Loop Operation Safety Relief Valve Safety Relief Valve Out of Service Turbine Bypass Valve Out of Service Technical Specification Page 6 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report 2.0 General Information Document ID: COLR Nine Mile Point 2, Rev. 3 This report is prepared in accordance with Technical Specification 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 setpoints and stability protection setpoints for Nine Mile Point Unit 2 Cycle 16. OPERATING LIMIT TECHNICAL SPECIFICATION REQUIREMENTS Requirement Operating Limit APLHGR MCPR LHGR Technical Specification LCO 3.2.1 Technical Specification LCO 3.2.2 Technical Specification LCO 3.2.3 This report provides the following cycle-specific parameter limits for Nine Mile Point Unit 2 CYCLE 16 (RELOAD 15):

• 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

• Linear Heat Generation Rate (LHGR)

• ARTS LHGR thermal limit multipliers

• Single Loop Operation (SLO) LHGR multipliers

• Rod Block Monitor (RBM) Analytical Limits, Allowable Values and MCPR Limits

• Turbine Bypass Valve Parameters

• EOG Recirculation Pump Trip (EOC-RPT) Parameters

• Backup Stability Protection 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 ICF for operational flexibility. Additional equipment out of service applicability can be found in Section 8.0, Modes of Operation. The EIS and Turbine Bypass Valves Out-Of-Service (TBVOOS) for rated and off-rated conditions are based on measured scram times. The remainder of the rated and off-rated conditions are based on the improved scram time. The measured and improved scram time limits are both referred to as Option B. Page 7 of 23

• , Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 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 to a minimum core flow of 85% of rated.

• Increased Core Flow up to 105% rated (Rated Core Flow is 108.5 Mlb/hr).

• Extended Power Uprate to 3988 MWth. 3.0 MAPLHGR Limits The Maximum Average Planar Linear Heat Generation Rate limits, in K'/:., 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. 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 Page 8 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 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 Note that per TS LCO 3.4.1, Single Loop Operation in the MELLLA or MELLLA+ domains is prohibited. The MAPLHGR multipliers, MAPFACP and MAPFACF, are set to unity for all power and flow conditions per Reference 2 -Section 16. 4.0 MCPR Limits The Operating Limit MCPRs 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 equations listed below are the generic equations for Boiling Water Reactors listed in Reference 8 -Item 2, "CRD Scram Insertion Time Conformance Procedure". Nine Mile Unit 2 specific coefficients are provided in Reference 17 -Section 5.0. Tau (r) is determined based on the cumulative plant scram time test results. rA is the control rod average scram insertion time limit to notch 39 per TS 3.1.4, "Control Rod Scram Times". This corresponds to the SCRAM Time Option A MCPR thermal limit set in Table 4-1. The SCRAM Time Option B MCPR thermal limit set takes credit for measured plant SCRAM speeds that are faster than the rA SCRAM insertion time limit. The lower Option B limits may be used provided that the actual plant average scram speed (rAvE) is faster or equal to the Option B SCRAM time speed limit (r8). This is determined by ensuring that r :::; O. The calculation of Tau shall be performed in accordance with site procedures. Linear interpolation shall be used to calculate the OLMCPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A). The equations for Tau are defined as follows: Page 9 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Where: Tave -Ts T=---rA = 0.866 seconds Document ID: COLR Nine Mile Point 2, Rev. 3 (Reference 1, Section 3.1.4) rs = 0.556 + 1.65

• Jr.r~:Ni

• 0.0098 seconds (Reference 17, Section 5.0) n is the number of surveillance tests performed in the cycle; Ni is the number of active control rods measured in surveillance test i; N1 is the total number of active rods measured; ri is the average scram time to notch 39 for rods in surveillance test i; 0.556 is the mean distribution for average scram insertion time to position 39 drop-out; 0.0098 is the standard deviation of the distribution for average scram insertion time to position 39 drop-out at NMP2 (Reference 8 -Item 2, Reference 17 -Section 5.0). Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) All Fuel Types (Reference 2 -Section 11) EOOS Combination SCRAM Time Cycle Exposure Option <EOR-2404 MWD/ST ~EOR-2404 MWD/ST BASE A 1.68 1.68 B 1.48 1.48 BASE SLO A 1.71 1.71 B 1.51 1.51 TBVOOS A 1.73 1.73 B 1.50 1.50 TBVOOS SLO A 1.76 1.76 B 1.53 1.53 RPTOOS A 1.78 1.78 B 1.55 1.57 RPTOOS SLO A 1.81 1.81 B 1.58 1.60 PROOS A 1.73 1.75 B 1.55 1.57 Page 10 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers (MCPRP) All Fuel Types (Reference 2 -Appendix D, Reference 16 -Section 7, Reference 17 -Section 4) Core Thermal Power [% of rated] Core Flow 0 23 <26 ~26 55 60 85 100 EOOS Combination [% of rated] Operating Limit Operating Limit MCPR Multiplier MCPR (KP) >75 '. __ ,. ', '* '"' *"' .. . *: ,z. BASE S.75 2.65 2.65 2.57 1.218 1.180 1.150 1.056 >75 .. ' . .. : 1 .;,, ' BASE SLO : ',',, M>' ' ' :,;, 1.218 1.180 1.150 1.056 S.75 2.68 2.68 2.60 >75 I: ; ;, 'p* TBVOOS ,. ~-s **-, ,,, < * . 1.218 1.180 1.150 1.056 S.75 3.51 3.51 3.22 >75 . '_;: '* . ,'~ ... .*' ;** < TBVOOS SLO '"" ,*"' * .. : .: 1.218 1.180 1.150 1.056 S.75 3.54 3.54 3.25 >75 I':.* '. *' : .. >:. , _ _; -;:, *"* ,.:.'* RPTOOS * .. , .. ' ' 1.190 1.167 1.150 1.068 S.75 2.65 2.65 2.57 >75 **_.;, .. :. '*,,.(_,. ',.,,, . '*' *, ':,; RPTOOS SLO ,, ,. ,: *** d" 1.190 1.167 1.150 1.068 S.75 2.68 2.68 2.60 >75 *. <,, '* .* ' ::i ' ;' :,* *' ' ;, ,' , .. . *,, ; PROOS S.75 2.65 2.65 2.57 1.190 1.167 1.158 1.056 ARTS power dependent thermal limits have been confirmed for operation with Equipment In-Service, Turbine Bypass Valves Out-Of-Service (TBVOOS), Recirculation Pump Trip Out-Of-Service (RPTOOS) and Pressure Regulator Out-Of-Service (PROOS). Table 4-3 Flow Dependent MCPR Limits (MCPRF) for DLO All Fuel Types (Reference 2 -Appendix D, Reference 16 -: Table 7-20, Reference 17 -Table 4-17) Flow [% rated] MCPRF Limit 0.0 2.01 30.0 1.78 94.2 1.29 112.0 1.29 Page 11 of 23 1.000 1.000 1.000 1.000 1.000 1.000 1.000 Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 5.0 LHGR Limits Table 4-4 Flow Dependent MCPR Limits (MCPRF) for SLO Ali Fuel Types (Reference 2 -Appendix D, Reference 16 -Table 7-20, Reference 17 -Table 4-17) Flow [% rated] MCPRF Limit 0.0 2.04 30.0 1.81 94.2 1.32 112.0 1.32

• 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 rated LHGR multipliers provide adequate protection for MELLLA+ operation (Reference 2). Table 5-1 LHGR Limits for U02 Fuel (Reference 5, Reference 6, Reference 13) Fuel Type LHGR Limit [KW/ft] GE14C See Reference 6 -Table D-2 GNF2 See Reference 13...:.. Table 8-1 Table 5-2 LHGR Limits for Gadolinia Rods (Reference 5, Reference 6, Reference 13) Fuel Type LHGR Limit [KW/ft] GE14C See Reference 6 -Table D-4 <;3NF2 See Reference 13 -Table 8-2 Page 12 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 EOOS Combination BASE BASE SLO TBVOOS TBVOOS SLO RPTOOS RPTOOS SLO PROOS Table 5-3* Power Dependent LHGR Multiplier LHGRFACP All Fuels Types (Reference 2 -Appendix D, Reference 16 -Section 7, Reference 17 -Section 4) Core Flow Core Thermal Power [% of rated] [% of rated] 0 23 <26 ~26 55 60 85 >75 0.613 0.720 0.791 0.922 S75 0.495 0.495 0.502 >75 0.613 0.720 0.791 0.922 S75 0.495 0.495 0.502 >75 ,. ' ' .. . ' 0.613 0.720 0.791 0.922 S75 0.475 0.475 0.502 . >75 S75 0.475 0.475 0.502 0.613 0.720 0.791 0.922 " >75 : ' 0.613 0.720 0.791 0.922 S75 0.495 0.495 0.502 >75 ' ; 0.613 0.720 0.791 0.922 S75 0.495 0.495 0.502 >75 '.' ' .. . ' S75 0.495 0.495 0.502 0.613 0.720 0.740 0.831 100 1.000 1.000 1.000 1.000 1.000 1.000 1.000

• BASE limits were used if EOOS limits are less limiting than BASE case. Reference 2 -A EOOS Condition DLO SLO Table 5-4 Flow Dependent LHGR Multiplier LHGRFACF All Fuel Types and Modes of Operation endix D, Reference 16 -Section 7, Reference 17 -Section 4) Core Flow % of rated 0 30 52.7 85 112 0.420 0.625 1.000 0.420 0.625 0.780 Page 13 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Repor:t Document ID: COLR Nine Mile Point 2, Rev. 3 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 9 -Table 5B, 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. Table 6-1 Rod Block Monitor Setpoints1 (Reference 2 -Section 10, Reference 7 -Section 5.1.3, Reference 10 -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% INOP N/A N/A N/A The ARTS RWE analysis validated the MCPR values in Table 6-2 below for use in Cycle 16. The RWE MCPR values have been analyzed at discrete setpoint values and unblocked (continuous withdraw) conditions. The most limiting RBM OLMCPR of 1.45 is less limiting than the minimum cycle-specific OLMCPR. Table 6-2 ARTS RWE Validated MCPR Values (Reference 2 -Section 10) Power Level [% Rated] MCPR <90% ~1.70 ~90% ~1.40 1 Values given are unfiltered; for filtered values see Reference 10. Page 14 of 23

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Exelon Generation -Nuclear Fuels Core Operating Limits Report 7.0 Turbine Bypass Valve Parameters Document ID: COLR Nine Mile Point 2, Rev. 3 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 11 -Section 1.6) Event Response 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) 8.0 Modes of Operation Table 8-1 Modes of Operation 0.15 0.30 (Reference 2, Reference 12 -Table 15.0-6, Reference 16) Options2 Allowed Operating Region BASE Yes BASE SLO Yes TBVOOS Yes TBVOOS SLO Yes RPTOOS Yes RPTOOS SLO Yes PROOS Yes MSIVOOS Yes MSIVOOS SLO Yes The ADSOOS and SRVOOS conditions are included in the BASE analysis and are therefore the same as the BASE OLMCPRs. There are no thermal limit penalties for combining any operating condition with the ADSOOS and/or the SRVOOS conditions. For Automatic Depressurization System (ADS) valves out of service, all conditions support only one ADSOOS (Reference 16 -Section 7.2.1, Reference 1 -Section 3.5.1 ). For Safety Relief Valves (SRV) Out of Service, all conditions support up to 2 SRVOOS (Refere'nce 16-Section 7.2.1). 2 The EOOS Options listed apply to both Option A and Option B Page 15 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 For Main Steam Isolation Valve (MSIV) Out of Service, only .one MSIV may be inoperable and reactor power must be maintained s 75% rated power (Reference 16-Section 7.2.1). There are no thermal limit penalties associated with MSIV out of service. Analogous to the ADSOOS and SRVOOS conditions, the MSIVOOS condition can be treated as the BASE case in the thermal limit tables. SLO is restricted by two parameters, namely recirculation flow and rod line. The maximum allowable SLO recirculation drive flow is 41,800 GPM due to recirculation piping vibration limitations and the maximum SLO rod line is 89% (ELLLA boundary). Where these two parameters intersect on the Power Flow Maps restricts SLO maximum power. The SLO rod line restriction is also governed by Tech Spec 3.4.1 LCO (Reference 1 ). Operation in SLO is restricted to the ELLLA region; this region and applicable restrictions are described in the SLO Loop Power Flow Maps (References 14 and 15). Operation with RPTOOS was justified for Nine Mile Point Unit 2 (Reference 16 -Section 7.2.1). There is no formally analyzed option for FWHOOS, however per Reference 7 -Section 1.2.4 there is a 20°F decrease from the rated temperature within analyzed conditions. 9.0 Stability Protection The OPRM Amplitude Discriminator Setpoint (SAo) is 1.10 (Reference 2 -Section 15.2). Results have been validated with feedwater temperature ;:: 420.5°F in accordance with Reference 7. Per TS 5.6.5.a.4, the BSP regions and values are as shown below in Tables 9-1 and 9-2. A graphical representation of these values can be found in Appendix A (Reference 2). Table 9-1 BSP Endpoints for Normal Feedwater Temperature3 (Reference 2 -Table 15-2) Endpoint Power Flow Definition [% of rated] [% of rated] A1 69.1 43.6 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 Boundarv, NCL A3 96.0 79.7 BSP Boundary Intercept with MELLLA+ Boundary B3 72.3 55.0 BSP Boundary Intercept with MELLLA+ Boundary 3 Bounding for both DLO and SLO Page 16 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 Parameter Slope of Automatic BSP APRM flow-biased trip linear segment Automatic BSP APRM flow-biased trip setpoint power intercept. Constant Power Line for Trip from zero Drive Flow to Flow Breakpoint value. Automatic BSP APRM flow-biased trip setpoint drive flow intercept. Constant Flow Line for Trip. Flow Breakpoint value Table 9-2 Automatic BSP Setpoints4 (Reference 2 -Table 15-3) Symbol mrRIP PssP-TRIP WssP-TRIP WssP-BREAK 10.0 Power Flow Operating Map See Appendix B for a Power Flow Map (Reference 7). 11.0 Methodology Value 1.26 39.7% RTP 36.9% RDF 16-.4% RDF 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)", A-21, May 2015 2. "General Electric Standard Application for Reactor Fuel (GESTAR II) (Supplement for United States)", NEDE-24011-P-A-21-US, May 2015 4 Applicable to both DLO and SLO. Page 17 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report 12.0 References Document ID: COLR Nine Mile Point 2, Rev. 3 1. "Nine Mile Point Nuclear Station Unit 2 Renewed Facility Operating License", Docket No. 50-410, Renewed License.No. NPF-69, Exelon Document. 2. "Supplemental Reload Licensing Report for Nine Mile Point Unit 2 Reload 15 Cycle 16 Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis Plus (MELLLA+)", December 2017, Global Nuclear Fuel Document No. 001 N4653, Revision 2. 3. [REMOVED] 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. "Fuel Bundle Information Report for Nine Mile Point Unit 2 Reload 15 Cycle 16 Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis Plus (MELLLA+)", GNF Document No. 001 N4654, Revision 0, February 2016. 6. "GE14 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR II), NEDC-32868P, Revision 5, May 2013," GNF Document No. MFN 13-028, May 24, 2013. 7. "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. 8. "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," NED0-24154 and NEDE-24154P, Volumes I, II, and Ill, October 1978. 9. "Revise 22A2843AM", Engineering Change Notice for NSSS161405000 "Design Spec Data Sheet, Neutron Monitoring System", Exelon Document Number 007242, Rev. 1,April 1~2008. 10. "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. 11. "Final resolved OPL-3 parameters for NMP2 C16", Exelon ENSAF ID Number ES1500019 Revision 0, June 23rct, 2015. 12. "Nine Mile Point Nuclear Station Unit 2 Updated Safety Analysis Report", U.S. Nuclear Regulatory Commission Docket 50-410 License NPF-69, Revision 22, October 2016, Exelon Document. 13. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)", NEDC-33270P, Revision 5, May 2013, GNF Document No. MFN 13-029, May 24, 2013 14. "Power Flow Operating Map 1 Recirc Loop in Operation (OPRM System Operable)", Nine Mile Point Drawing No. EM-950B-001, Revision 18.00, September 91h, 2015, Exelon Document. Page 18 of23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 3 15. "Power Flow Operating Map 1 Recirc Loop in Operation (OPRM System Inoperable)", Nine Mile Point Drawing No. EM-950B-002, Revision 00.00, September 91h, 2015, Exelon Document. 16. "GNF2 Fuel Design Cycle-Independent Analyses for Exelon Nine Mile Point Nuclear Station Unit 2", GEH Document No. 003N2003 Revision 1, February 2016. 17. "Nine Mile Point Unit 2 Option B' Scram Speed Implementation", GEH Document No. 004N0521-RO, September 2017. Page 19 of 23 Exelon Generation -Nuclear Fuels Core Operating Limits Report Appendix A Page 20 of23 Document ID: COLR Nine Mile Point 2, Rev. 3 Exelon Generation -Nuclear Fuels Core Operating Limits Report NlNE MILE POINT UN1T 2 Reload 15 0 11 22 33 120 110 f-----ExtensionofMELLLA+Upper Bounduy --Proposed Manual BSP Sa-am 100 f--Regioo Boondary --Proposed Manual BSP Cootrol 90 Entry Region Boundary --BSPBoundary 80 f--70 " 43 I i I i I I I Al , , Core Flow [l\flbm/br] S4 65 76 87 V Document ID: COLR Nine Mile Point 2, Rev. 3 001N4653 Revision 2 98 109 119 4786 4387 3988 v / A3 ./ 3589 V 4 / y 3190 ,;:;' 2792 [ ii! 0 60 ll,. I,, < 'I ,,,' i /, " ii! 2393 0 ,; E " 50 (: 40 30 /'J'V I / ./ "'/ I / V n, .// ./ V B2< ..... I / J ./ p.. ,; E 1994 1595 1196 20 to 0 I I J I / V ____.,,, / 798 399 0 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow[%] Figure 19 Manual BSP Regions and BSP Boundary for Normal Feedwater Temperature Operation Page 21 of 23 Page 58 l Exelon Generation -Nuclear Fuels Core Operating Limits Report Appendix B Page 22 of 23 Document ID: COLR Nine Mile Point 2, Rev. 3 Exelon Generation -Nuclear Fuels Core Operating Limits Report 110 '""' 70 ...i u :::: !:..., .. 60 ... Q .. = 50 .. ... -= '""' 40 30 20 10 0 0 IO 20 NED0-33576 REVISION 0 NON-PROPRIETARY INFORMATION -CLASS I (PUBLIC) Core Flow (Mihm/hr) 30 40 50 60 70 80 90 100 110 Document ID: COLR Nine Mile Point 2, Rev. 3 120 130 4500 4000 3500 3000 2500 ::; .. 2000 E 1500 1000 500 ... -= '""' +-,>-+-+-+=lc..+-+-+-+-+-+-,>-+4--+-+-+--+-+-+-+-+->-+-+-+-<-+--+-+-+-+--+-+-+-+-+->-+-+-+-<>-+-+-+-,-+--+-+-+-+--+-+-+-+-+-+-+-+- 0 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow(%) Figure 1-1 Power/Flow Operating Map for MELLLA+ in Dual Loop Operation Note: Operation in the MELLLA+ and MELLLA regions is not analyzed for single loop operation. Refer to Section 8.0 Modes of Operation, Tech Spec 3.4.1 (Reference 1), and Reference 14 and 15 (SLO Power-to-Flow Map) for Single Loop Operation restrictions. 1-14 Page 23 of 23