Text

Core Operating Limits Report for Cycle 15
	ML15286A056
Person / Time
Site:	Nine Mile Point
Issue date:	10/07/2015
From:	Moore D; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NMP2L 2598
	Download: ML15286A056 (23)
	v • d • e

~Exeton Generation Technical Specification 5.6.5 NMP2L 2598 October 7, 2015 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 Enclosed is a copy of the Core Operating Limits Report, Cycle 15 for Nine Mile Point Unit 2 (NMP2).

The COLR has been revised as a result of MELLLA+ implementation and 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.

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

Enclosure:

Core Operating Limits Report for Nine Mile Point Unit 2 Cycle 15 cc:

NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector 4ocf

Enclosure Core Operating Limits Report For Nine Mile Point Unit 2 Cycle 15

J f

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 CORE OPERATING LIMIT REPORT FOR NINE MILE POINT UNIT 2 CYCLE 15 Prepared by:

Reviewed by:

Chadr Buttrn -NFPreparRveer Robert Potter - NF Peer Reviewer Reviewed by Reviewed by Reviewed by Reviewed by Approved by SQR by:__

Mike Holmes - Independent Reviewer David Knepper - ESA Independent Reviewer Date: 8/27/2015 Dt:8/28/2015 Date: 8/31/2015 Date: 8/31/2015 Date:_8/28/15 Date:_8/31//2015 Date:

9/1/2015 Date: 9/1/2015 John Darweesh - RE Reviewer Robert Close - Station Supplemental Reviewer J--J S/James Tusar - Senior BWR Design Manager Gerry Kahn - Station Qualified Reviewer Page 1 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Table of Contents Section Revision History List of Tables Terms and Definitions General Information MAPLHGR Limits MCPR Limits LHGR Limits Rod Block Monitor Setpoints Turbine Bypass Valve Parameters Modes of Operation Stability Protection Power/Flow Operating Map Methodology References Appendix A Appendix B Page Number 3

4 5

7 8

9 11 12 13 13 14 15 15 16 18 20 Page 2 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Revision History Revision Revision I Revision 0 Description Revised to reflect MELLLA+ Implementation New Issue for Cycle 15 Since this COLR will be the first Nine Mile Point Unit 2 (NMP2) COLR in the Exelon standard formatting and documentation style, it is listed as a new document in records management. This is revising the originally issued NMP2 Cycle 15 (015) COLR.

Page 3 of 21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 0 Core Operating Limits Report List of Tables Table #

Table Name Page Table 3-1 MAPLHGR Versus Average Planar Exposure 8

Table 3-2 MAPLHGR SLO Multiplier 8

Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 9 Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers (MCPRp) 10 Table 4-3 Flow Dependent MCPR Limits (MCPRF) for SLO & DLO 10 Table 5-1 LHGR Limits for UO 2 Fuel 11 Table 5-2 LHGR Limits for Gadolinia Rods 11 Table 5-3 Power Dependent LHGR Multiplier LHGRFACp 11 Table 5-4 Flow Dependent LHGR Multiplier LHGRFACF 12 Table 6-1 Rod Block Monitor Setpoints 12 Table 6-2 ARTS RWE Validated MCPR Values 12 Table 7-1 Turbine Bypass Valve Response Time 13 Table 8-1 Modes of Operation 13 Table 9-1 BSP Endpoints for Normal Feedwater Temperature 14 Table 9-2 Automatic BSP Setpoints 15 Page 4 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 1.0 Terms and Definitions ADSOOS APLHGR APRM ARTS BPV BSP DLO DSS-CD EGOS EIS EL LLA EGOC EOR FWHOOS GEH GNF GPM HFCL HTSP ICF INOP ITSP LCOG LHGR LHGRFACF LHGRFAOp 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 Detect and Suppress Solution - Confirmation Density Emergency Gore Cooling System Equipment In Service Extended Load Line Limit Analysis End of Cycle Equipment Out of Service End of Rated. The cycle exposure at which reactor power is equal to 3988 MWth with recirculation flow equal to 100% rated, all control blades fully withdrawn, and 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 Gore Flow Inoperable Intermediate Set Point (regarding RBM)

GLMCPR 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 Low Trip Set Point (regarding RBM)

Page 5 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 MAPFACF MAPFACp MAPLHGR MCPR MCPRF MCPRp M ELLLA MELLLA+

MSIVOOS NCL NRC OLMCPR OPRM PROOS RDF RPTOOS RTP RBM RWE SLMCPR 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 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 of 21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2. Rev. 0 Core Operating Limits Report 2.0 General Information 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 15.

OPERATING LIMIT TECHNICAL SPECIFICATION REQUIREMENTS Operatinqi Limit Requirement APLHGR Technical Specification LCO 3.2.1 MCPR Technical Specification LCO 3.2.2 LHGR Technical Specification LCO 3.2.3 This report provides the following cycle-specific parameter limits for Nine Mile Point Unit 2 CYCLE 15 (RELOAD 14):

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 EOC Recirculation Pump Trip (EOC-RPT) Parameters Backup Stability Protection Parameters Per TS 5.6.5, these values have been determined using NRC-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 supports 2 SRVOOS and ICF for operational flexibility.

The data presented in this report is valid for all licensed operating domains on the operating map, including (Reference 2):

Page 7 of 21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 0 Core Operating Limits Report Maximum Extended Load Line Limit Analysis Plus to a minimum core flow of 85% of rated.

Increased Core Flow up to 105% rated.

Extended Power Uprate to 3988 MWth.

Note that no revision bars are used as this is a complete rewrite.

3.0 MAPLHGR Limits KW The Maximum Average Planar Linear Heat Generation Rate limits, in -*t obtained from the ECCS analysis are provided in Table 3-1. The limiting MAPLHGR value for the most limiting lattice of each fuel type as a function of exposure is given. Since NMP2 Cycle 15 employs solely GEl4 fuel, these values are applicable to all the bundles in the NMP2C15 core. For SLO, a multiplier is used as shown in Table 3-2.

Table 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types (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 SLO Multiplier All Fuel Types (Reference 2 - Table 16.3-2)

Fuel Type SLO Multiplier GE14C 0.78 Note that per TS LCO 3.4.1.d, 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.

Page 8 of 21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 0 Core Operating Limits Report 4.0 MCPR Limits The Operating Limit MCPRs listed in Table 4-1 cover all conditions listed in Section 8.0, Modes of Operation. ARTS provides for power and flow dependent thermal limits adjustments, which allow for a more reliable administration of the MCPR thermal limit.

Note that SLO and DLO OLMCPR values are identical. The OLMCPRs for PROOS, ADSOOS, MSIVOOS, and ADSOOS+MSIVOOS are the same as the BASE OLMCPRs.

Control rod scram time verification is required as per TS 3.1.4, "Control Rod Scram Times". Tau (T), a measure of scram time performance to notch position 39 throughout the cycle, is determined based on the cumulative scram time test results. 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). Tau is defined as:

Tare -- T TA -- TB Where:

TA = 0.866 seconds TB =0.672 + 1.65 N 1 0.016 seconds Tae =

NiT* seconds n is the number of surveillance tests performed in the cycle; N1 is the number of active control rods measured in surveillance test i; N1 is the total number of active rods measured; T1 is the average scram time to notch 39 for rods in surveillance test i.

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

All Fuel Types (Reference 2 - Section 11 )

EQOS Combination SCRAM Time Cycle Exposure Option

<EOR-2816 MWD/ST

>EOR-2816 MWD/ST BASE A

1.65 1.66 B

1.41 1.42 BASE SLO A

1.65 1.66 B

1.41 1.42 TBVOOS A

1.66 1.66 B

1.44 1.44 TBVOOS SLO A

1.66 1.66 B

1.44 1.44 RPTOOS A

1.75 1.81 B

1.42 1.48 RPTOOS SLO A

1.75 1.81 B

1.42 1.48 Page 9 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers (MCPRp)

All Fuel Types (Reference 2 - Appendix 0, Reference 3 - Section 4.3)

EOOS Cornbi nation Core Flow [%

of rated]

0 23 J<26 [_>26

<5SI>.5 I5 60I 85 1<901_>90 100 Core Thermal Power [% of ratedi Operating Limit MCPR Operating Limit MCPR Multiplier (Kp)

BASE

>75 1*

1511 1.336 1.193 1.150 1.056

<75 2.52 2.52 2.43 BASESLO

>75 1.511 1.336 1.193 1.150 1.056

<75 2.52 2.52 2.43 RPTOOS

>7 1*

1511 1.336 1.193 1.150 1.062

75 2.52 2.52 2.43___

RPTOOS

>7 1.511 1.336 1.193 1.150 1.062 SLO

<75 2.52 2.52 2.43 TBVOOS

>7 1.511 1.336 1.193 1.150 1.056

<75 3.33 3.33 3.06 1.000 1.000 1.000 1.000 1.000 1.000 1.000 TBVOOS SLO

>75 1.511 1.336 1.193 1.150 1.056

<75 3.33 3.33 3.06 PROOS

>75

.1 PROOS

<75 2.52 2.52 2.43 PROOS SLO

>71.1

<75 2.52 2.52 2.43 1.122 1.038 1.122 1.038 1.000 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). The Kp/MCPRp and LHGRFACp thermal limits applicable to the Equipment In-Service, TBVOOS and RPTOOS conditions are documented in Reference 3. The Kp/MCPRn and LHGRFACp thermal limits applicable to the PROOS condition are documented in References 3 and 4.

Table 4-3 Flow Dependent MCPR Limits (MCPRF) for SLO & DLO All Fuel Types (Reference 2 - Appendix D)

Flow [% rated]

MCPRF Limit 0.0 1.91 30.0 1.69 87.3 1.27 112.0 1.27 Page 10 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2. Rev. 0 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.

Table 5-1 LHGR Limits for UO2 Fuel (Reference 5, Reference 6 - Table D2)

Fuel Type LHGR Limit [KW/ft]

GE14C See Reference 6 - Table D2 Table 5-2 LHGR Limits for Gadolinia Rods (Reference 5, Reference 6 - Table D4)

Fuel Type LHGR Limit [KW/ft]

GE14C I

See Reference 6 -Table D4 Table 5-3 Power Dependent LHGR Multiplier LHGRFACp All Fuels Types eference 2 -Appendix D, Reference 4 -Section 4, Core Thermal Power [% of ratei Page 11 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Table 5-4 Flow Dependent LHGR Multiplier LHGRFACF All Fuel Types and Modes of Operation Reference 2 - Appendix D)

EOOS____Core Flow [% of rated]

EQS0 30 52.8 85 112 Condition LHGRFACF Multiplier DLO 0.420 0.625

[;;Ž<

1.000 1.000 SLO 0.420 0.625 0.780 0.780 0.780 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 Setpoints' (Reference 2 - Section 10, Reference 7 - Section 5.1.3, Reference 8 - Section 4, 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 15. The RWE MCPR values have been analyzed at discrete setpoint values and unblocked (continuous withdraw) conditions. The most limiting RBM OLMCPR of 1.38 is still less than minimum cycle OLMCPRs.

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

Power Level [% Rated]

MCPR

<90%

>1.70

>90%

->1.40

' Values given are unfiltered; for filtered values see Reference 10.

Page 12 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2. Rev. 0 7.0 Turbine Bypass Valve Parameters Per Technical Specification LCO 3.7.5, whenever the reactor power is at or above 23%

the main turbine bypass system shall be operable or the plant must operate with the TBVOOS penalties previously stated. The definition of operable is given in Table 7-1 be low.

Table 7-1 Turbine Bypass Valve Response Time (Reference 11 - Section 2.6)

Event Response Time [sec]

Total Response Time Of BPV (80% of 03 ratedBPV flow)

__________3 Maximum Bypass Valve Delay From Event Initiation To Start Of BPV Opening 01 8.0 Modes of Operation Table 8-1 Modes of Operation (Reference 2, Reference 12 - Table 15.0-6)

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 ADSOOS Yes ADSOOS SLO Yes MSIVOOS + ADSOOS Yes MSIVOOS + ADSOOS SLO Yes For Main Steam Isolation Valve (MSIV) Out of Service, only one MSIV may be inoperable and, per Reference 14 - Section 15.22.0, reactor power must be maintained

< 75% rated power.

SThe EOOS Options listed are for Option A or Option B Page 13 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Note that there are no thermal limit penalties or differences for operating with up to two Safety Relief Valves Out of Service (SRVOOS) and all conditions also support 2 SRVOOS.

There are no thermal limit penalties or differences for operating with up to two ADS valves out of service and all conditions also support 2 ADSOOS.

Maximum power in SLO operation 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%

(original ELLLA boundary). These restrictions are also described in the SLO Loop Power-to-Flow Maps (Reference 16). Where these two parameters intersect on the Power-to-Flow Maps restricts SLO maximum power.

Operation with EOC RPTOOS was justified for Nine Mile Point Unit 2 in Reference 13.

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 Per References 15 and 2 the OPRM Upscale Setpoint requirement has been replaced by the DSS-CD solution. The Amplitude Discriminator Setpoint 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 Table 9-1, and Table 9-2. A graphical representation of these values can be found in Appendix A Table 9-1 BSP Endpoints for Normal Feedwater Temperature (Reference 2 -Table 15-2)

Endpoint Power [% of rated]

.Flow

[% of rated]

Definition Al 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 Boundary, NCL A3 89.9 71.4 BSP Boundary Intercept, HFCL B3 74.0 55.0 BSP Boundary Intercept, MELLLA+ Boundary Minimum

___Flow Page 14 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Table 9-2 Automatic BSP Setpoints 3

~Reference 2 -Table 15-3)

Parameter Sym bol Value Slope of Automatic BSP APRM flow-biased trip linear segment mBSP-TRIP 1.26 Automatic BSP APRM flow-biased trip setpoint powerPB-TI intercept. Constant Power Line BPRP39.7%

RTP for Trip from zero Drive Flow to Flow Breakpoint value.

Automatic BSP APRM flow-biased trip setpoint drive flowWBPTI369RD intercept. Constant Flow Line forWBRRP369RD Trip.__

Flow Breakpoint value WBSPBREAK 16.4% RDF 10.0 Power/Flow Operating Map See Appendix B for a Power/Flow Map.

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-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 SBounding for both DLO and SLO.

Page 15 of21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 0 Core Operating Limits Report 12.0 References

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 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Plus (MELLLA+)", August 2015, Global Nuclear Fuels Document No. 000N0123-SRLR, Revision 3.

3. "Nine Mile Point Nuclear Power Plant, Unit 2, TRACG Implementation for Reload Licensing Transient Analysis (Ti1309)", GEH Document No. 0000-0157-9895-Ri, Rev.

i, October 2013.

4. "Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900: Transient Analysis", GE Energy Document No. GE-NE-0000-0055-2373-R0, Revision 0, February 2007.

5. "Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15", GNF Document No. 000N0123-FIBR-P Revision 0, December 2013.

6. Letter from B. R. Moore (GNF) to Document Control Desk (NRC),

Subject:

"GEl4 Compliance with Amendment 22 of NEDE-24011i-P-A (GESTAR II), NEDC-32868P, Revision 5, May 2013," GNF Document No. MFN13-028, 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. "Nine Mile Point Nuclear Station Unit 2 APRM/RBM/Technical Specifications/Maximum Extended Load Line Limit Analysis (ARTS/MELLLA)", GE Energy Document No.

NEDC-33286P Revision 0, March 2007.

9. "Revise 22A2843AM", Engineering Change Notice for NSSS161405000 "Design Spec Data Sheet, Neutron Monitoring System", Exelon Document Number 007242, Rev. 1, April 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-i1006 NMP2 A-M-T506-RBM-Calc-2006 Revision 1, March 2008.

11."OPL 3 - Fuel Analysis Parameters", Nine Mile Point Nuclear Station Calculation No.

A10.1-AE-001 Revision 02, October 2003.

12."Nine Mile Point Nuclear Station Unit 2 Updated Safety Analysis Report", U.S. Nuclear Regulatory Commission Docket 50-410 License NPF-69, Revision 20, October 2012, Exelon Document.

13. "Project Task Report, Constellation Energy Nuclear Group, Nine Mile Point Nuclear Station Unit 2 MELLLA+, Task T0900: Transient Analysis", GEH Document No. 0000-0130-0603-R3, Revision 3, July 2013.

14."FRED Nine Mile Point Unit 2 Reload 14 Cycle 15 MELLLA+", Technical Information Letter between Nine Mile Point Nuclear Station and GNF, Revision 4, August 2013.

Page 16 of 21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 0 Core Operating Limits Report

15. "License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus", Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 Docket No. 50-410, November 2013.

16. "Power Flow Operating Map 1 Recirculation Loop in Operation", Engineering Change Notice No. ECP-12-000448-CN-043 EM-950B-1 7.01, Revision 0000.00, August 2015, Exelon Document.

Page 17 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Appendix A Page 18 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report NINE MILE POINT 2 Reload 14 Document ID: COLR Nine Mile Point 2, Rev. 0 000N01I23-SRLR Revision 3 123 -

-i

!M anual 9$* 5cr~m *eglen Z 73]

60 J'

63-Al 1

13 3,

13 20 32 43 513 62 70 93 93 133 113 133 Core Flowv {%)

Figure 22 Manual BSP Regions and BSP Boundary for Normal Feedwater Temperature Operation Page 46 Page 19 of 2l

e

,I Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Appendix B Page 20 of 21

L Exelon Nuclear - Nuclear Fuels Core Operating Limits Report NE[X)-33576 REVISION 0 NON-PROPRIETARY INFORMATION -CLASS I (PUBiL[C) 0 10 20 30 40

51) 00 70 00 930 I 1(1 Document lD: COLR Nine Mile Point 2. Rev. 0 I10 120 130 I-120 11(1 911 80 70) 40 30 20 10 4500 41(*0, 3500 23(01~

2500 1 500 5(11) 60 Core Flow. F/%

Figure I-I Power/Flow Operating Map for MELLLA+

1-14 Page 21 of 21

~Exeton Generation Technical Specification 5.6.5 NMP2L 2598 October 7, 2015 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 Enclosed is a copy of the Core Operating Limits Report, Cycle 15 for Nine Mile Point Unit 2 (NMP2).

The COLR has been revised as a result of MELLLA+ implementation and 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.

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

Enclosure:

Core Operating Limits Report for Nine Mile Point Unit 2 Cycle 15 cc:

NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector 4ocf

Enclosure Core Operating Limits Report For Nine Mile Point Unit 2 Cycle 15

J f

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 CORE OPERATING LIMIT REPORT FOR NINE MILE POINT UNIT 2 CYCLE 15 Prepared by:

Reviewed by:

Chadr Buttrn -NFPreparRveer Robert Potter - NF Peer Reviewer Reviewed by Reviewed by Reviewed by Reviewed by Approved by SQR by:__

Mike Holmes - Independent Reviewer David Knepper - ESA Independent Reviewer Date: 8/27/2015 Dt:8/28/2015 Date: 8/31/2015 Date: 8/31/2015 Date:_8/28/15 Date:_8/31//2015 Date:

9/1/2015 Date: 9/1/2015 John Darweesh - RE Reviewer Robert Close - Station Supplemental Reviewer J--J S/James Tusar - Senior BWR Design Manager Gerry Kahn - Station Qualified Reviewer Page 1 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Table of Contents Section Revision History List of Tables Terms and Definitions General Information MAPLHGR Limits MCPR Limits LHGR Limits Rod Block Monitor Setpoints Turbine Bypass Valve Parameters Modes of Operation Stability Protection Power/Flow Operating Map Methodology References Appendix A Appendix B Page Number 3

4 5

7 8

9 11 12 13 13 14 15 15 16 18 20 Page 2 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Revision History Revision Revision I Revision 0 Description Revised to reflect MELLLA+ Implementation New Issue for Cycle 15 Since this COLR will be the first Nine Mile Point Unit 2 (NMP2) COLR in the Exelon standard formatting and documentation style, it is listed as a new document in records management. This is revising the originally issued NMP2 Cycle 15 (015) COLR.

Page 3 of 21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 0 Core Operating Limits Report List of Tables Table #

Table Name Page Table 3-1 MAPLHGR Versus Average Planar Exposure 8

Table 3-2 MAPLHGR SLO Multiplier 8

Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 9 Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers (MCPRp) 10 Table 4-3 Flow Dependent MCPR Limits (MCPRF) for SLO & DLO 10 Table 5-1 LHGR Limits for UO 2 Fuel 11 Table 5-2 LHGR Limits for Gadolinia Rods 11 Table 5-3 Power Dependent LHGR Multiplier LHGRFACp 11 Table 5-4 Flow Dependent LHGR Multiplier LHGRFACF 12 Table 6-1 Rod Block Monitor Setpoints 12 Table 6-2 ARTS RWE Validated MCPR Values 12 Table 7-1 Turbine Bypass Valve Response Time 13 Table 8-1 Modes of Operation 13 Table 9-1 BSP Endpoints for Normal Feedwater Temperature 14 Table 9-2 Automatic BSP Setpoints 15 Page 4 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 1.0 Terms and Definitions ADSOOS APLHGR APRM ARTS BPV BSP DLO DSS-CD EGOS EIS EL LLA EGOC EOR FWHOOS GEH GNF GPM HFCL HTSP ICF INOP ITSP LCOG LHGR LHGRFACF LHGRFAOp 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 Detect and Suppress Solution - Confirmation Density Emergency Gore Cooling System Equipment In Service Extended Load Line Limit Analysis End of Cycle Equipment Out of Service End of Rated. The cycle exposure at which reactor power is equal to 3988 MWth with recirculation flow equal to 100% rated, all control blades fully withdrawn, and 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 Gore Flow Inoperable Intermediate Set Point (regarding RBM)

GLMCPR 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 Low Trip Set Point (regarding RBM)

Page 5 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 MAPFACF MAPFACp MAPLHGR MCPR MCPRF MCPRp M ELLLA MELLLA+

MSIVOOS NCL NRC OLMCPR OPRM PROOS RDF RPTOOS RTP RBM RWE SLMCPR 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 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 of 21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2. Rev. 0 Core Operating Limits Report 2.0 General Information 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 15.

OPERATING LIMIT TECHNICAL SPECIFICATION REQUIREMENTS Operatinqi Limit Requirement APLHGR Technical Specification LCO 3.2.1 MCPR Technical Specification LCO 3.2.2 LHGR Technical Specification LCO 3.2.3 This report provides the following cycle-specific parameter limits for Nine Mile Point Unit 2 CYCLE 15 (RELOAD 14):

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 EOC Recirculation Pump Trip (EOC-RPT) Parameters Backup Stability Protection Parameters Per TS 5.6.5, these values have been determined using NRC-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 supports 2 SRVOOS and ICF for operational flexibility.

The data presented in this report is valid for all licensed operating domains on the operating map, including (Reference 2):

Page 7 of 21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 0 Core Operating Limits Report Maximum Extended Load Line Limit Analysis Plus to a minimum core flow of 85% of rated.

Increased Core Flow up to 105% rated.

Extended Power Uprate to 3988 MWth.

Note that no revision bars are used as this is a complete rewrite.

3.0 MAPLHGR Limits KW The Maximum Average Planar Linear Heat Generation Rate limits, in -*t obtained from the ECCS analysis are provided in Table 3-1. The limiting MAPLHGR value for the most limiting lattice of each fuel type as a function of exposure is given. Since NMP2 Cycle 15 employs solely GEl4 fuel, these values are applicable to all the bundles in the NMP2C15 core. For SLO, a multiplier is used as shown in Table 3-2.

Table 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types (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 SLO Multiplier All Fuel Types (Reference 2 - Table 16.3-2)

Fuel Type SLO Multiplier GE14C 0.78 Note that per TS LCO 3.4.1.d, 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.

Page 8 of 21

Exelon Nuclear - Nuclear Fuels Document ID: COLR Nine Mile Point 2, Rev. 0 Core Operating Limits Report 4.0 MCPR Limits The Operating Limit MCPRs listed in Table 4-1 cover all conditions listed in Section 8.0, Modes of Operation. ARTS provides for power and flow dependent thermal limits adjustments, which allow for a more reliable administration of the MCPR thermal limit.

Note that SLO and DLO OLMCPR values are identical. The OLMCPRs for PROOS, ADSOOS, MSIVOOS, and ADSOOS+MSIVOOS are the same as the BASE OLMCPRs.

Control rod scram time verification is required as per TS 3.1.4, "Control Rod Scram Times". Tau (T), a measure of scram time performance to notch position 39 throughout the cycle, is determined based on the cumulative scram time test results. 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). Tau is defined as:

Tare -- T TA -- TB Where:

TA = 0.866 seconds TB =0.672 + 1.65 N 1 0.016 seconds Tae =

NiT* seconds n is the number of surveillance tests performed in the cycle; N1 is the number of active control rods measured in surveillance test i; N1 is the total number of active rods measured; T1 is the average scram time to notch 39 for rods in surveillance test i.

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

All Fuel Types (Reference 2 - Section 11 )

EQOS Combination SCRAM Time Cycle Exposure Option

<EOR-2816 MWD/ST

>EOR-2816 MWD/ST BASE A

1.65 1.66 B

1.41 1.42 BASE SLO A

1.65 1.66 B

1.41 1.42 TBVOOS A

1.66 1.66 B

1.44 1.44 TBVOOS SLO A

1.66 1.66 B

1.44 1.44 RPTOOS A

1.75 1.81 B

1.42 1.48 RPTOOS SLO A

1.75 1.81 B

1.42 1.48 Page 9 of 21

Exelon Nuclear - Nuclear Fuels Core Operating Limits Report Document ID: COLR Nine Mile Point 2, Rev. 0 Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers (MCPRp)

All Fuel Types (Reference 2 - Appendix 0, Reference 3 - Section 4.3)

EOOS Cornbi nation Core Flow [%

of rated]

0 23 J<26 [_>26

<5SI>.5 I5 60I 85 1<901_>90 100 Core Thermal Power [% of ratedi Operating Limit MCPR Operating Limit MCPR Multiplier (Kp)

BASE

>75 1*

1511 1.336 1.193 1.150 1.056

<75 2.52 2.52 2.43 BASESLO

>75 1.511 1.336 1.193 1.150 1.056

<75 2.52 2.52 2.43 RPTOOS

>7 1*

1511 1.336 1.193 1.150 1.062

75 2.52 2.52 2.43___