Text

Core Operating Limits Report
	ML16154A064
Person / Time
Site:	Nine Mile Point
Issue date:	05/16/2016
From:	Kreider R E; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NMP2L3088
	Download: ML16154A064 (26)
	v • d • e

)* __ , -;.:::: / Exelon Generation NMP2L 3088 May 16, 2016 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, Cycle 16 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 me at (315) 349-5219.

Robert E. Kreider, Jr. Plant Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC REK/KJK

Enclosure:

Core Operating Limits Report for Nine Mile Point Unit 2 Cycle 16 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 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document JD: COLR Nine Mile Point 2, Rev. 2 CORE OPERATING LIMITS REPORT FOR NINE MILE POINT UNIT 2 CYCLE 16 (This is a complete re-write; no revision bars are used.) Prepared by: ________

_______ Date: 41612016 Lizette Flint -Co-Preparer Prepared Date: 4/6/2016 Chad Burns -Co-Preparer 8..J-Reviewed

___ _ Brian Mmer -Independent Reviewer D t 4/7/2016 ae:. ____ __ Date: 04/01no16 Date: <1(?/1r, Date: 4/1112016 Date: 4/11/2016

SQR by:. ___ ---'--".....__

.......

-=* *=--------. Andrew Raft -S1allon Ql.lallfled Rsv!eww I Page 1 of23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Section Revision History List of Tables Terms and Definitions General Information MAPLHGR Limits MCPR Limits LHGR Limits Rod Block Monitor Setpoints Table of Contents Turbine Bypass Valve Parameters Modes of Operation Stability Protection Power Flow Operating Map Methodology References Appendix A Appendix B Page 2 of 23 Document ID: COLR Nine Mile Point 2, Rev. 2 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 2 Revision 1 Revision 0 Document ID: COLR Nine Mile Point 2, Rev. 2 Revision History Description New Issue for Cycle 16 Revised to reflect MELLLA+ Implementation New Issue for Cycle 15 Note that this issuance of the Nine Mile Point Unit 2 COLR is the second revision in both this actual document and the accompanying document identification number. This bypasses revision 1 of the document identification number. This was done to reduce confusion, to eliminate a possible error trap, and with the permission of the Records Management department.

Page 3 of23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 Table# Table 3-1 Table 3-2 Table 3-3 Table 4-1 Table 4-2 Table 4-3 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 SLO & DLO 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 13 13 14 14 15 15 16 17 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 1.0 Terms and Definitions AD SOOS APLHGR APRM ARTS BPV BSP DLO ECCS EIS ELL LA EOG EOC-RPT EOOS EOR FWHOOS GEH GNF GPM HFCL HTSP ICF INOP ITSP Kp LCO LHGR LHGRFACF LHGRFACp LOCA LTSP 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 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 Loss of Coolant Accident Low Trip Set Point (regarding RBM) Page 5 of 23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 MAPFACF MAPFACp MAPLHGR MCPR MCPRF MCPRp MELLLA M.ELLLA+ MSIVOOS NCL NRC OLMCPR OPRM PROOS RDF RPTOOS RTP RBM RWE SLM CPR SLO SRVOOS TBVOOS TS 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 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 Out of Service Turbine Bypass Valve Out of Service Technical Specification Page 6 of23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report 2.0 General Information Document ID: COLR Nine Mile Point 2, Rev. 2 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 Operating Limit APLHGR MCPR LHGR Requirement 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.

Page 7 of 23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 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 MW1h. 3.0 MAPLHGR Limits The Maximum Average Planar Linear Heat Generation Rate limits, in 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 tu.el 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 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 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. 2 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 (L), 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 interpolated based on core size and values provided in Reference 11 -Section 1.2, "SCRAM PARAMETERS".

Tau (L) is determined based on the cumulative plant scram time test results. LA 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 actual plant SCRAM speeds that are faster than the LA SCRAM insertion time limit. The lower Option B limits may be used provided that the actual plant average scram speed (LAVE) is faster or equal to the Option B SCRAM time speed limit (L 8). This is determined by ensuring that L :::; 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 of23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Where: Tave -TB T=---TA = 0.866 seconds Document ID: COLR Nine Mile Point 2, Rev. 2 (Reference 1, Section 3.1.4) T 8 = Q.672 + 1.65

j._.nN 1 .

0.016 seconds "'i=1Ni n is the number of surveillance tests performed in the cycle; Ni is the number of active control rods measured in surveillance test i; N 1 is the total number of active rods measured; Ti is the average scram time to notch 39 for rods in surveillance test i; 0.672 is the mean distribution for average scram insertion time to position 39 drop-out; 0.016 is the standard deviation of the distribution for average scram insertion time to position 39 out at NMP2 (Reference 3 -Table 6-2, Reference 8 -Item 2, Reference 11 -Section 1.2). 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 MWD/ST BASE A 1.73 1.75 B 1.55 1.57 BASE SLO A 1.75 1.77 B 1.57 1.59 rBvoos A 1.75 1.75 B 1.57 1.57 TBVOOS SLO A 1.77 1.77 B 1.59 1.59 RPTOOS A 1.78 1.78 B 1.55 1.57 RPTOOS SLO A 1.80 1.80 B 1.57 1.59 PRO OS 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. 2 Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers (MCPRp) All Fuel Types (Reference 2 -Appendix D, Reference 16 -Section 7) Core Thermal Power [% of rated] Core Flow 0 23 <26 55 60 85 100 EOOS Combination

[%of rated] Operating Limit Operating Limit MCPR Multiplier MCPR (Kp) BASE >75 1.190 1.167 1.150 1.056 2.65 2.65 2.57 BASE SLO >75 1.190 1.167 1.150 1.056 2.67 2.67 2.59 TBVOOS >75 1.190 1.167 1.150 1.081 3.51 3.51 3.22 TBVOOS SLO >75 1.190 1.167 1.150 1.081 3.53 3.53 3.24 RPTOOS >75 1.190 1.167 1.150 1.068 2.65 2.65 2.57 RPTOOS SLO >75 1.190 1.167 1.150 1.068 2.67 2.67 2.59

>75 PROOS 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 SLO & DLO All Fuel Types (Reference 2 -Appendix D, Reference 16 -Table 7-20) 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 Generat ion -Nuclear Fuels Core Operati n g Limits Report 5.0 LHGR Limits Doc u ment ID: COLR N in e M il e Point 2 , Rev. 2 The LHGR limit is the product of the exposure depen.dent 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 B-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 GNF2 See Reference 13 -Table B-2 Page 12 of 23 E xel on Gene rati on -Nuclear Fu el s Co re Ope ratin g Lim it s Report Document ID: COLR N in e Mile Po i nt 2 , Rev. 2 EOOS Combination BASE BASE SLO TBVOOS TBVOOS SLO RPTOOS RPTOOS SLO PROOS EOOS Condition DLO SLO Table 5-3 Power Dependent LHGR Multiplier LHGRFACp All Fuels Types (Reference 2 -Appendix D, Reference 16 -Section 7) Core Flow Core Thermal Power [% of rated] [%of rated] 0 23 <26 2:26 55 >75 0.613 0.720 ::;75 0.540 0.540 0.545 >75 0.613 0.720 ::;75 0.540 0.540 0.545 >75 0.613 0.720 ::;75 0.495 0.495 0.545 . >75 *: 0.613 0.720 ::;75 0.495 0.495 0.545 >75 ... ::;75 0.540 0.540 0.545 0.613 0.720 >75 . .. *. 0.613 0.720 ::;75 0.540 0.540 0.545 >75 0.613 0.720 ::;75 0.540 0.540 0.545 Table 5-4 Flow Dependent LHGR Multiplier LHGRFACF All Fuel Types and Modes of Operation 60 85 0.791 0.922 0.791 0.922 0.791 0.922 0.791 0.922 0.791 0.922 0.791 0.922 0.740 0.831 Reference 2 -Appendix D, Reference 16 -Section 7) Core Flow [% of rated] 0 30 I 52.7 I 85 I 112 LHGRFACF Multiplier 0.420 0.625 I I 1.000 I 1.000 0.420 0.625 I 0.780 I 0.780 I 0.780 Page 13 of 23 100 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. 2 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 given in Table 6-1 are unfiltered; these unfiltered values are applicable as the time filter constant is set to zero. (Reference 9 -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 SLM CPR and cladding 1 % plastic strain criteria will not be exceeded in the event of a Rod Withdraw Error. Table 6-1 Rod Block Monitor Setpoints 1 (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 still less than the minimum cycle OLMCPR. Table 6-2 ARTS RWE Validated MCPR Values (Reference 2 -Section 10) Power Level [% Rated] MCPR <90%

1 Values given are unfiltered; for filtered values see Reference

10. Page 14 of 23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report 7 .0 Turbine Bypass Valve Parameters Document ID: COLR Nine Mile Point 2, Rev. 2 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 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) 8.0 Modes of Operation Table 8-1 Modes of Operation (Reference 2, Reference 12 -Table 15.0-6, Reference

16) Options" 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 (Reference 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. 2 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 (Reference 15). Operation with EOC 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 Temperature 3 (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 Boundarv, NCL A2 64.5 50.0 Controlled Entry Region Boundary, HFCL B2 27.5 28.9 Controlled Entry Region Boundary, NCL A3 96.0 79.7 BSP Bqundary 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. 2 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 Setpoints 4 (Reference 2-Table 15-3) Symbol mTRIP 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 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 (GEST AR II)",

A-21, May 2015 2. "General Electric Standard Application for Reactor Fuel (GEST AR 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. 2 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+)", March 2016, Global Nuclear Fuels Document No. 001 N4653, Revision 1. 3. "TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analyses", GEH Document NEDE-32906P-A, Rev. 3, September 2006. 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 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 1st, 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 23rd, 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 21, October 2014, 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.TODI NF151201, "Nine Mile Point Unit 2 Cycle 16 Customer Approved FRED Form", Revision 0, May 21st, 2015. Page 18 of 23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 15. "Power Flow Operating Map 1 Recirculation Loop in Operation", Engineering Change Notice No. ECP-12-000448-CN-043 EM-9508-17.01, Revision 0000.00, August 16 1 h, 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. Page 19 of23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Appendix A Page 20 of 23 Document ID: COLR Nine Mile Point 2, Rev. 2 Exelon Generation

-Nuclear Fuels Core Operating Lim it s Report NINE MILE POINT UNIT2 Reload 15 0 J.I llO } l HO ---E:&lmsillll of"MELLLA+ Upper t-&aadary l 1 00 --Plq>c-'Mamal BSPScnm Regio>Bm.mmy 90 80 . --Fropo5Bi Maaml BSPCczbd !--RrgjDn Bom11l11 y l --BSP.Boundary iO .. .. ii< " t I l I I t I l , , i I I I i ' i I I I .i\.l , _, '! /. 60

E .. 50 l I t (:: 40 30 20 1 0 0 I / I I D1 ' /I,/ B l< .,. I t j ! I I I t / I I / / __..-" I t I ! I l I I / 4/ Y I ' < I i I ! j y ' ./ I j t ' I l Document ID: COLR Nine Mile Po int 2 , Rev. 2 1 09 119 I v / v I / / 001 4653 Revision l 47ll6 4387 3988 3589 3190 IT<;ll .. .. ii< 2393 c "-* 1994 "f:. 1595 1196 798 399 0 0 10 20 30 40 :50 60 Core.Flow[%] 70 80 90 100 110 uo Figure 19 Manual BSP Regions and BSP Boundary for Normal Feedwater Temperature Operation Page 21of23 Page 48 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Appendix 8 Page 22 of 23 Document ID: COLR Nine Mile Point 2, Rev. 2 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 ;;;;-0 IO 20 NED0-33576 REVISION 0 NON-PROPRIETARY INFORMATION

-CLASS I (PUBLIC) Core Flow (Mlbm/hr) 30 40 50 60 70 80 90 JOO J JO J20 130 J20 -if-+--H'--h-Hf-+-+-l-+-+-+-+-+-+--tf-+--H'-+--+-f-+-f-t-+-+-i-+-+--+-+f-+-+-t--+-+-+-+-H--+r-Hf-+-+-t-+-f-+-+-+---!rl--+--H--+-ri-'f-+-+-1-i 100% CLTP 3988 MWt i I JO _ 86.9% CLTP (Pre-EPU)

= 3467 MWt , , 4 , _j. _ _ __ l ---_ -----JOO * :u!

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_ i i i I i : I i i 20 -Kj-------

I I I I I I I I I I I 10

t--*

I 1 i I I I I I I I I 4500 4000 3500 3000 2500 l:l l: 0 io.. ... 2000 ., .c ""' J500 JOOO 500 0 0 0 JO 20 30 40 50 60 70 80 90 JOO I JO J20 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 15 (SLO Power-to-Flow Map) for Single Loop Operation restrictions.

1-14 Page 23 of 23

7 Exelon Generation NMP1L 3091 May 16, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk -Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Units 1 and 2 1 O CFR 72.44(d)(3)

Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRG Docket Nos. 50-220 and 50-410 Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket No. 72-1036

Subject:

2015 ISFSI Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2

Reference:

1. Letter from Peter Orphanos (Exelon) to the U.S. Nuclear Regulatory Commission, "2015 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2", dated May 2, 2016. This letter is to provide clarification that the report submitted via Reference 1 satisfies the annual effluent reporting requirements for the ISFSI required by 1 O CFR 72.44(d)(3).

There were no radioactive effluents released from the station ISFSI during the monitoring period, January 1, 2015 through December 31, 2015. Should you have questions regarding the information in this submittal, please contact Jeffrey W. Gerber, Site Chemistry Environmental

& Radwaste Manager, at (315) 349-4264.

Sincerely, Robert E. Kreider, Jr. Plant Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC REK/KJK Cc: NRG Regional Administrator, Region 1 NRG Project Manager NRG Resident Inspector C. Graves, NRG

)* __ , -;.:::: / Exelon Generation NMP2L 3088 May 16, 2016 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, Cycle 16 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 me at (315) 349-5219.

Robert E. Kreider, Jr. Plant Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC REK/KJK

Enclosure:

Core Operating Limits Report for Nine Mile Point Unit 2 Cycle 16 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 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document JD: COLR Nine Mile Point 2, Rev. 2 CORE OPERATING LIMITS REPORT FOR NINE MILE POINT UNIT 2 CYCLE 16 (This is a complete re-write; no revision bars are used.) Prepared by: ________

_______ Date: 41612016 Lizette Flint -Co-Preparer Prepared Date: 4/6/2016 Chad Burns -Co-Preparer 8..J-Reviewed

___ _ Brian Mmer -Independent Reviewer D t 4/7/2016 ae:. ____ __ Date: 04/01no16 Date: <1(?/1r, Date: 4/1112016 Date: 4/11/2016

SQR by:. ___ ---'--".....__

.......

-=* *=--------. Andrew Raft -S1allon Ql.lallfled Rsv!eww I Page 1 of23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Section Revision History List of Tables Terms and Definitions General Information MAPLHGR Limits MCPR Limits LHGR Limits Rod Block Monitor Setpoints Table of Contents Turbine Bypass Valve Parameters Modes of Operation Stability Protection Power Flow Operating Map Methodology References Appendix A Appendix B Page 2 of 23 Document ID: COLR Nine Mile Point 2, Rev. 2 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 2 Revision 1 Revision 0 Document ID: COLR Nine Mile Point 2, Rev. 2 Revision History Description New Issue for Cycle 16 Revised to reflect MELLLA+ Implementation New Issue for Cycle 15 Note that this issuance of the Nine Mile Point Unit 2 COLR is the second revision in both this actual document and the accompanying document identification number. This bypasses revision 1 of the document identification number. This was done to reduce confusion, to eliminate a possible error trap, and with the permission of the Records Management department.

Page 3 of23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 Table# Table 3-1 Table 3-2 Table 3-3 Table 4-1 Table 4-2 Table 4-3 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 SLO & DLO 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 13 13 14 14 15 15 16 17 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 1.0 Terms and Definitions AD SOOS APLHGR APRM ARTS BPV BSP DLO ECCS EIS ELL LA EOG EOC-RPT EOOS EOR FWHOOS GEH GNF GPM HFCL HTSP ICF INOP ITSP Kp LCO LHGR LHGRFACF LHGRFACp LOCA LTSP 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 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 Loss of Coolant Accident Low Trip Set Point (regarding RBM) Page 5 of 23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 MAPFACF MAPFACp MAPLHGR MCPR MCPRF MCPRp MELLLA M.ELLLA+ MSIVOOS NCL NRC OLMCPR OPRM PROOS RDF RPTOOS RTP RBM RWE SLM CPR SLO SRVOOS TBVOOS TS 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 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 Out of Service Turbine Bypass Valve Out of Service Technical Specification Page 6 of23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report 2.0 General Information Document ID: COLR Nine Mile Point 2, Rev. 2 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 Operating Limit APLHGR MCPR LHGR Requirement 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.

Page 7 of 23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 2 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 MW1h. 3.0 MAPLHGR Limits The Maximum Average Planar Linear Heat Generation Rate limits, in 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 tu.el 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 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 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. 2 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 (L), 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 interpolated based on core size and values provided in Reference 11 -Section 1.2, "SCRAM PARAMETERS".

Tau (L) is determined based on the cumulative plant scram time test results. LA 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 actual plant SCRAM speeds that are faster than the LA SCRAM insertion time limit. The lower Option B limits may be used provided that the actual plant average scram speed (LAVE) is faster or equal to the Option B SCRAM time speed limit (L 8). This is determined by ensuring that L :::; 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 of23 Exelon Generation

-Nuclear Fuels Core Operating Limits Report Where: Tave -TB T=---TA = 0.866 seconds Document ID: COLR Nine Mile Point 2, Rev. 2 (Reference 1, Section 3.1.4) T 8 = Q.672 + 1.65

j._.nN 1 .

0.016 seconds "'i=1Ni n is the number of surveillance tests performed in the cycle; Ni is the number of active control rods measured in surveillance test i; N 1 is the total number of active rods measured; Ti is the average scram time to notch 39 for rods in surveillance test i; 0.672 is the mean distribution for average scram insertion time to position 39 drop-out; 0.016 is the standard deviation of the distribution for average scram insertion time to position 39 out at NMP2 (Reference 3 -Table 6-2, Reference 8 -Item 2, Reference 11 -Section 1.2). 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 MWD/ST BASE A 1.73 1.75 B 1.55 1.57 BASE SLO A 1.75 1.77 B 1.57 1.59 rBvoos A 1.75 1.75 B 1.57 1.57 TBVOOS SLO A 1.77 1.77 B 1.59 1.59 RPTOOS A 1.78 1.78 B 1.55 1.57 RPTOOS SLO A 1.80 1.80 B 1.57 1.59 PRO OS A 1.73 1.75 B 1.55 1.57 Page 10 of 23 Exelon Generation