NMP1L3134, Core Operating Limits Report

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Core Operating Limits Report
ML17087A271
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 03/21/2017
From: Moore D
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP1L3134
Download: ML17087A271 (64)
v • d • e


Text

~

~ Exelon Generation Technical Specification 6.6.5 NMP1L3134 March 21, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-001 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63

  • NRG Docket No. 50-220 '

Subject:

Core Operating Limits Report

References:

1) Letter from Exelon (W. Trafton) to NRG (Document Control Desk) dated April 7, 2015 (ML15111A210).
2) Letter from'Exelon (D. Moore) to NRG (Document Control Desk) dated September 9, 2016 (ML16257A454).

Enclosed are non-proprietary copies of the Core Operating Limits Report (COLR), Cycle 22, Revisions 0, 1 and 2 for Nine Mile Point Unit 1 (NMP1 ). These reports are being submitted pursuant to NMP1 Technical Specification 6.6.5.d. COLR, Revision 0, was previously submitted on April 7, 2015 (Reference 1), and COLR, Revision 1, was previously submitted on September 9, 2016 (Reference 2). The previously submitted Revision O and Revision 1 inadvertently contained GE Proprietary Information in Appendix A. Exelon requests the NRG to withdraw the previously submitted COLR Revision 0 and Revision 1 and replace them with the enclosed non-proprietary COLR Revision O and Revision 1. Exelon. requests the NRG destroy or return the COLRs submitted by References 1 and 2.

A non-proprietary COLR Revision 2 is enclosed to provide the latest version of the NMP1 COLR.

Should you have any questions regarding the information in this submittal, please contact me at (315) 349-5219.

Sincerely,

(/jl~~

Denni~ M. Moore Regulatory Assurance Manager, Nine Mile Point Nuclear Station Exelon Generation Company, LLC

.... .,_.i NMP1 Core Operating Limits Report March 21, 2017 Page2 DMM/KJ K/RJ R

Enclosures:

(1) Core Operating Limits Report for Nine Mile Point Unit 1 Cycle 22, Revision O (2) Core Operating Limits Report for Nine Mile Point Unit 1 Cycle 22, Revision 1 (3) Core Operating Limits Report for Nine Mile Point Unit 1 Cycle 22, Revision 2 cc: NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector

Enclosure 1 Core Operating Limits Report For Nine Mile Point Unit 1 Cycle 22 Revision O

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 CORE OPERATING LIMITS REPORT FOR NINE MILE POINT NUCLEAR STATION UNIT1RELOAD23CYCLE22 Prepared By: Date: 2/8/17 B. Lambert Reviewed By:

~

Independent Reviewer Date: 2/8/17 Reviewed By: Date: 2 / Df ft 1-J. Darweesh Reactor Engineering Reviewer Reviewed By: Date: 02/13/2017 D. S. Knepper Engineering Safety Analysis Reviewer Reviewed By: _ ____ ~ J_.__~--~-* R. Close

______ Date: 2/14/17 Station Supplemental Reviewer Approved By:

__~?}~_ Date: _0_2_12_0_12_0_1_7_

A. Johnson Manager - BWR Design Date: z / .:Zd /; 7 Page 1 of19

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table of Contents Page LO Terms and Definitions 4 2.0 General Information 5 3.0 MAPLHGR Limits 6 4.0 MCPRLimits ll 5.0 LHGRLimits 13 6.0 Limiting Power I Flow Line 14 7.0 Modes of Operation 15 8.0 Methodology 16 9.0 References 16 Appendix A 17 Page 2of19

lo I )_ l Exelon Nuclear-Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure -

Bundle: GEi l-P9DUB376-12GZ-100T-145-T6-2586 6 Table 3-2 MAPLHGR Versus Average Planar Exposure -

Bundle: GEI l-P9DUB381-14GZ-100T-145-T6-2946 7 Table 3-3 MAPLHGR Versus Average Planar Exposure'--

Bundle: GE l l-P9DUB380-13GZ-100T-l 45-T6-2948 7 Table 3-4 MAPLHGR Versus Average Planar Exposure-Bundle: GNF2-PIODG2B384-16GZ-IOOT2-145-T6-3351 8 Table 3-5 MAPLHGR Versus Average Planar Exposure-Bundle: GNF2-Pl ODG2B386-13GZ- l OOT2- l 45-T6-3352 8 Table 3-6 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-Pl ODG2B384-l 6GZ- I OOT2-145-T6-4133 9 Table 3-7 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-Pl ODG2B386-l 3GZ-l OOT2-l 45-T6-4 I 34 9 Table 3-8 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-PIODG2B371-16GZ-IOOT2-145-T6-4312 10 Table 3-9 MAPLHGR Versus Average Planar Exposure-Bundle: GNF2-PlODG2B375-l lG5.0-100T2-145-T6-4313 10 Table 3-10 MAPLHGR Multiplier for Four and Three Recirculation Loop Operation 10 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 11 Table 4-2 MCPR Adder for Three Recirculation Loop Operation 12 Table 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp 12 Table 4-4 Operating Limit MCPR Multiplier, Kf 12 Table 5-1 Linear Heat Generation Rate Limits - U0 2 Rods 13 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods 13 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) for PROOS 14 Table 7-1 Modes of Operation 15 List of Figures Figure 6-1 Limiting Power/Flow Line 14 Page 3of19

~ l J I Exelon Nuclear- Nuclear Fuels Doc ID: COLR N"me Mile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point l Cycle 22 1.0 Terms and De:fmitions ARTS APRM, Rod Block, and Technical Specification Improvement Program ELLLA Extended Load Line Limit Analysis EOOS Equipment Out of Service EOR End of Rated. The cycle exposure at which reactor power is equal to rated thermal power with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FWP Combination I Feedwater Pump Combination I as defined in Nl-OP-16, Le. TuriJine Driven Feedwater Pump (TDFWP) in service AND one Motor Driven Feedwater Pump (MDFWP) in service (bounds TDFWP in service OR one MDFWP in service OR two MDFWPs in service).

FWP Combination 2 Feedwater Pump Combination 2 as defined in Nl-OP-16, i.e. TDFWP in service AND two MDFWPs in service.

Kp Off-rated power dependent OLMCPR multiplier Kf Off-rated flow dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRFAC(F) Off-rated LHGR flow dependent thermal limit multipliers LHGRFAC(P) Off-rated LHGR power dependent thermal limit multipliers MAPFAC(F) Off-rated flow dependent MAPLHGR multiplier MAPFAC(P) Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) Off-rated flow dependent OLMCPR MCPR(P) Off-rated power dependent OLMCPR OLMCPR Operating Limit Minimum Critical Power Ratio OOS Out of Service PROOS Pressure Regulator Out of Service Page 4of19

  • l JI Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 C<ire Operating Limits Report for Nine Mile Point I Cycle 22 2.0 General Information This report provides the following cycle-specific parameter limits for Nine Mile Point Nuclear Station Unit I Cycle22:
  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
  • Operating Limit Minimum Critical Power Ratio (OLMCPR)
  • MCPR thermal limit adjustments and multipliers (MCPR(P) or MCPR(F))
  • Three recirculation loop operation MCPR adjustment
  • LHGR thermal limit multipliers (LHGRFAC(P))
  • MAPLHGR four and three recirculation loop operation multipliers
  • Linear Heat Generation Rate (LHGR)
  • Limiting Power I Flow Line This report is prepared in accordance with Technical Specification 6.6.5 of Reference 1. Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values. Nine Mile Point Unit I is a non-ARTs plant that utilizes ELLLA operating domain.

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

  • Extended Load Line Limit down to the minimum licensed core flow (i.e., 85.0% of rated) during full power operation,
  • Rated core flow is 67.5 Mlb/hr,
  • End-of-cycle coastdown to a minimum power level of 40% of rated power,
  • F eedwater temperature of no more than -10°F off nominal is licensed for this cycle.

Further information on the cycle-specific analyses for Nine Mile Point Unit I Cycle 22 and the associated operating domains discussed above is available in Reference 2.

Page 5of19

l ~ f I Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point l, Rev. 0 Core Operating Limits Report for Nine l\'lile Point l Cycle 22 3.0 MAPLHGR Limits 3.1 Technical Specification 3.1.7.a, 3.1.7.e 3.2 Description The MAPLHGR limits for each bundle type as a function of average planar exposure is given in Tables 3-1 through 3-9. For partial loop operation, a fuel-type-dependent multiplier is used, which is shown in Table 3-10. For operation with either four or three recirculation loops in service, multiply the most limiting values shown in Tables 3-1 through 3-3 by the GEi I value in Table 3-10 and multiply the most limiting values shown in Tables 3-4 through 3-9 by the GNF2 value in Table 3-10. The power and flow dependent multipliers for MAPLHGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F); therefore, MAPFAC(P) and MAPFAC(F) are equal to LO for all power and flow .conditions (Reference 2). LHGRFAC(P) and LHGRFAC(F) are addressed in Section 5.0.

Table3-l MAPLHGR Versus Average Planar Exposure-Bundle: GEll-P9DUB376-12GZ-lOOT-145-T6-2586 (Reference 2)

Average Planar Exposure MAPLHGR Limit 1 (GWD/ST) (kW/ft) 0.00 9.63 0.20 9.63 1.00 9.60 '

5.00 9.40 10.00 9.37 15.00 9.24 20.00 8.76 25.00 8.34 35.00 8.10 45.00 8.03 55.00 8.02 65.00 6.18 1

These MAPLHGRs are not lattice dependent.

Page 6of19

t I r I Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine l\'Iile Point 1 Cycle 22 Table3-2 MAPLHGRVersusAveragePlanarExposure-Bundle:GE11-P9DUB381-14GZ-JOOT-145-T6-2946 (Reference 2)

MAPLHGR Limit1 Average Planar (kW/ft)

Exposure (GWD/ST) Lattice Lattice Lattice Lattice Lattice Lattice 7433 7439 7440 7441 7442 7443 0.00 I0.24 10.24 10.19 10.19 10.19 10.19 020 1024 1024 10.19 I0.19 I0.19 10.19 LOO 10.20 10.20 I0.19 10.19 10.19 10.19 5.00 9.91 9.91 9.85 9.85 9.85 9.85 10.00 9.42 9.42 9.34 9.34 9.34 9.34 15.00 922 9.22 9.19 9.19 9.19 9.19 20.00 9.18 9.18. 9.19 9.19 9.19 9.19 25.00 8.64 8.64 8.63 8.63 8.63 8.63 35.00 8.08 8.08 8.08 8.08 8.08 8.08 45.00 8.02 8.02 7.99 7.99 7.99 7.99 55.00 8.00 8.00 7.99 7.99 7.99 7.99 65.00 7.97 7.97 7.96 7.96 7.96 7.96 Table3-3 MAPLHGR Versus Average Planar Exposure- Bundle: GE11-P9DUB380-13GZ-100T-145-T6-2948 (Reference 2)

MAPLHGR Limit' Average Planar (kW/ft)

Exposure (GWD/ST) Lattice Lattice Lattice Lattice Lattice Lattice 7433 7449 7450 7451 7447 7448 0.00 9.71 9.71 9.69 9.69 9.69 9.69 0.20 9.71 9.71 9.69 9.69 9.69 9.69 1.00 9.68 9.68 9.67 9.67 9.67 9.67 5.00 9.56 9.56 9.50 9.50 9.50 9.50 10.00 9.38 9.38 9.32 9.32 9.32 9.32 15.00 9.23 9.23 9.24 9.24 9.24 9.24 20.00 9.28 9.28 9.31 9.31 9.31 9.31 25.00 8.43 8.43 8.45 8.45 8.45 8.45 35.00 8.09 8.09 8.09 8.09 8.09 8.09 45.00 7.98 7.98 8.02 8.02 8.02 8.02 55.00 7.97 7.97 7.98 7.98 7.98 7.98 65.00 7.91 7.91 7.93 7.93 7.93 7.93 1

These MAPLHGRs are lattice dependent.

Page 7of19

  • ' r ~

Exelon Nuclear-Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine .Mile Point I Cycle 22 Table3-4 MAPLHGR Versus Average Planar Exposure- Bundle: GNF2-P10DG2B384-16GZ-100T2-145-T6-3351 (Reference 2)

Average Planar Exposure MAPLHGR Limit1 (GWD/ST) (kW/ft) 0.00 7.91 0.20 7.91 LOO 7.88 5.00 7.81 10.00 7.70 15.00 7.58 20.00 7.03 25.00 6.68 35.00 6.51 45.00* 6.27 55.00 6.14 65.00 6.05 Table3-5 MAPLHGR Versus Average Planar Exposure-Bundle: GNF2-PIODG2B386-13GZ-100T2-145-T6-3352 (Reference 2)

Average Planar Exposure MAPLHGR Limit' (GWD/ST) (kW/ft) 0.00 7.81 0.20 7.81 1.00 7.92 5.00 7.83 10.00 7.71 15.00 7.73 20.00 7.09 25.00 6.68 35.00 6.52 45.00 6.26 55.00 6.15 65.00 6.05 1

These MAPLHGRs are not lattice dependent.

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, I ,- I Exelon Nuclear-Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table3-6 MAPLHGR Versus Average Planar Exposure- BundJe: GNF2-PlODG2B384-16GZ-HlOT2-145-T6-4133 (Reference 2)

Average Planar Exposure MAPLHGR Limit1 (GWD/ST) (kW/ft) 0 . 00 7.90 0.20 7.90 LOO 7 . 85 5 . 00 7.79 10.00 7.73 15 . 00 7.74 20 . 00 7.06 25 . 00 6 . 68 35 . 00 6..51 45 . 00 6 . 28 55 . 00 6.15 65.00 6.05 Table3-7 MAPLHGR Versus Average Planar Exposure - Bundle: GNF2-P10DG2B386-13GZ-IOOTI-145-T6-4134 (Reference 2)

Average Pli;mar Exposure MAPLHGR Limit1 (GWD/ST) (kW/ft) 0 . 00 7.78 0 . 20 7.78 LOO 7.84 5 . 00 7 . 83 10 . 00 7 . 71 15 . 00 7 . 73 20 . 00 7 . 09 25 . 00 6 . 67 35 . 00 6.52 45.00 6.26 55.00 6 . 15 65.00 6.05 1

These MAPLHGRs are not lattice dependent.

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t l I 1 Exelon Nuclear- Nuclear Fuels Doc ID: COLR 1\lne Mile Point l, Rev. 0 Core Operating Limits Report for Nine :Mile Point l Cycle 22 Table3-8 MAPLHGR Versus Average Planar Exposure- Bundle: GNF2-PIODG2B37i-16GZ-100TI-145-T6-4312 (Reference 2)

Average Planar Exposure MAPUIGR Limit1 (GWD/ST) (kW/ft) 0.00 7.96 0.20 7.96 LOO 7.96 5.00 7.88 10.00 7.76 15.00 7.63 20.00 7.16 25.00 6.68 35.00 6.50 45.00 6.29 55.00 6.18 65.00 6.09 Table3-9 MAPLHGR Versus Average Planar Exposure- Bundle: GNF2-PlODG2B375-UG5.0-lOOT2-145-T6-4313 (Reference 2)

Average Planar Exposure MAPLHGR Limit' (GWD/ST) (kW/ft) 0.00 7.90 0.20 7.90 1.00 7.91 5.00 7.85 10.00 7.76 15.00 7.65 20.00 7.25 25.00 6.69 35.00 6.45 45.00 6.28 55.00 6.17 65.00 6.08 Table3-10 MAPLHGR Multiplier for Four and Three Recirculation Loop Operation (Reference 2)

Fuel Type Four and Three Loop Operation Multiplier2 GEll 0.98 GNF2 0.99 1

These MAPLHGRs are not lattice dependent.

2 The 4-loop MAPLHGR multiplier is applicable up to 90.5% rated thermal power if the Out-of-Service (OOS) loop is isolated from the reactor and is applicable up to 100% rated thermal power if the OOS loop is un-isolated. The 3-loop MAPLHGR Multiplier is applicable to 90% rated power and 75% rated core flow regardless of whether the OOS recirculation loops are isolated or un-isolated.

Page 10of19

I I I\

E:xeJon Nuc1ear- Nuclear Fuels Doc ID~ COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 4.0 MCPR Limits 4.1 Technical Specification 3.1.7.c, 3.1.7.e 4.2 Description The OLMCPR is determined for a given power and flow condition by evaluating the power dependent MCPR and the flow dependent MCPR and selecting the greater of the two. Tables 4-1and4-2 are derived from Reference 2 and are valid for all Cycle 22 operating domains. Nine Mile Point Unit I Cycle 22 has a mid-cycle MCPR breakpoint, as defined in Table 4-1. An adder, presented in Table 4-2, is required to be applied to all limits in Table 4-l and MCPR(P) in Table 4-3 in the event of three recirculation loop operation. Table 4-1 and 4-2 limits are bounding for both GEI 1 and GNF2 fuel types.

The power dependent MCPR limits are presented in Table 4-3 and are valid for both GEI 1 and GNF2 fuel types (Reference 2). When core thermal power is greater than or equal to 45% of rated, the applicable Kp multiplier from Table 4-3 is applied to the applicable rated condition OLMCPR value in Table 4-1 or adjusted OLMCPR value determined by using Table 4-2. Below 45% rated thermal power, the MCPR(P) limits in Table 4-3 are applied directly. The appropriate MCPR(P) or Kp value may be determined by linear interpolation.

The flow adjusted OLMCPR is determined by multiplying the applicable rated condition OLMCPR provided by either Table 4- l or 4-2 by the applicable Kf multiplier given in Table 4-

4. The Kf multipliers are valid for both GEi I and GNF2 fuel types and are documented in Reference 2. The appropriateKf value may be determined by linear interpolation.

Table4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)

(All Fuel Types, Four/Five Recirculation Loop Operation)

(Reference 2)

Cvcle Exposure Feed water Pump SCRAM Time

<EOR-3609  ;:::EOR-3609 Combination 1 Option 2 MWd/ST MWd/ST B 1.47 1.54 FWP Combination 1 A 1.57 1.64 B 1.52 1.59 FWP Combination 2 A 1.62 1.69 1

0LMCPR values are independent of pressure regulator in-service or out-of service conditions.

2 For tau(*)= 0, use SCRAM Time Option B limits. For (i) = 1, use SCRAM Time Option A limits. When tau does not equal 0 or I, use linear interpolation. Tau is defined as:

't =('rave- tn) I (TA - <n) where TA= 0.868 seconds, control rod average scram insertion time limit to notch 39 tn = 0.672 + 1.65 * [ N1 I Lf=i Ni ]

  • 0.016 112

'rave= Lf=l Ni'ti I Lf=l Ni where n =number of surveillance tests performed in cycle; N, = number of active control rods measured in the l" surveillance test; t; =average scram time to notch 39 of all rods measures in the i'h surveillance test; and N 1 =total number of active rods measured.

Page 11of19

a I It Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine l\'lile Point I Cycle 22 Table4-2 MCPR Adder for Three Recirculation Loop Operation (All Fuel Types)

(Reference 2)

Three Recirculation Loop Operation 0.03 Adder 1 Table4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp (All Fuel Types)

(Reference 2)

Core Core Thermal Power (% of Rated)

EOOS Flow 0 25 <45 ~45 65 85 >85 100 Combination (%of Operating Limit MCPR, Operating Limit MCPR Multiplier, Kp rated) MCPR(P)

FWP ~60 3.28 3.28 2.36 1.349 1.216 1.133 1.133 1.000 Combination I >60 3.40 3.40 2.86 FWP ~60 3.28 3.28 2.36 1.349 1.216 1.133 1.133 1.000 Combination 2 >60 3.40 3.40 2.86

~60 3.28 3.28 2.36 PROOS 2 1.553 1.336 1.198 1.133 1.000

>60 3.40 3.40 . 2.86 Table4-4 Operating Limit MCPR Multiplier, Kf (All Fuel Types)

(Reference 2)

Flow MCPR

(%rated) Multiplier, Kf 0.0 1.500 45.0 1.500

>45.0 1.132 75.0 1.000 100.0 1.000 1

Increase the values in Table 4-1 and the MCPR(P) values in Table 4-3 by 0.03 in the event ofThree Recirculation Loop Operation.

2 Limits apply to PROOS coincident with FWP Combination I or 2.

3 Values are applicable up to a Maximum Runout Flow of 102.5% of rated. Values apply to operation in either FWP Combination I or 2 with or without Pressure Regulator in-service.

Page 12of19

  • I , I Exelon Nuclear - Nuclear Fuels Doc ID: COLR N'me 1\-tile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point l Cycle 22 5.0 LHGR Limits
5. l Technical Specification 3.1.7.b 5.2 Description The Linear Heat Generation Rate (LHGR) for all fuel bundles shall not exceed either 1 LO kW/ft1 or the LHGR limits presented in Tables 5-l and 5-2. Linear interpolation should be used for points not listed in Appendix A or Appendix B of Reference 4. Power adjusted LHGR limits are required for operation with PROOS at greater than or equal to 45% RTP. Below 45% RTP, no additional limits are required. These power dependent LHGR multipliers (LHGRFAC(P)) are provided in Table 5-3 for Option Band Option A scram times and are applicable to both GEl 1 and GNF2 fuel types (Reference 2). The power adjusted LHGR is determined by multiplying the applicable Appendix A LHGR limit by the LHGR multiplier, LHGRFAC(P). The LHGRFAC(P) curves are independent of recirculation loop operability. The appropriate LHGRFAC(P) values may be determined by linear interpolation. Flow dependent LHGR multipliers (LHGRFAC(F))

are not required (Reference 2).

Table5-1 Linear Heat Generation Rate Limits - UOi Rods (References 3 and 4)

Fuel Tvoe LHGR GEil See Aooendix A GNF2 1 See Appendix B of Reference 4 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (References 3 and 4)

Fuel Type LHGR GEil See Appendix A GNF2 1 See Appendix B of Reference 4 1

GNF2 LHGR limit has been set down to a maximum value of 11 kW/ft to address Emergency Procedure Guidelines (EPG) requirements (Reference 6).

Page 13of19

  • I ~ 1 Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point l Cycle 22 Table5-3 Power Dependent LHGR Multiplier LHGRFAC(P) for PROOS (All Fuel Types)

(Reference 2)

Core Thermal Power(% of rated)

Scram Time Option 0 <45 2':45 65 85 100 Option A {i.e. -c>O) l.000 1.000 0.518 0.518 0.636 1.000 OptionB 1.000 1.000 0.737 0.867 0.987 1.000 6.0 Limiting Power/Flow Line 6.1 Technical Specification 3.1.7.d, 3.l.7.e 6.2 Description The Nine Mile Point Unit l power/flow relationship is shown in the figure below.

Figure6-1 Limiting Power/Flow Line (References 5, 7, and 8) 120 85.0. 100.0) (I 00.0, I 00.0) 100 .......

0-

~

~

~

~

.....0 80

~

~

Q

~ 60 0

c.. Power = 0.55* W+53

=.,..

8

-= 40 E--

0 u.

20 0

0 20 40 60 80 100 120 Core Flow (% of Rated)

Page 14of19

I I t I Exelon Nuclear-Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 7.0 Modes of Operation 7.1 Description The allowable modes of operation are found in Table 7- L Operation with PROOS is supported in all modes of operation, provided the restrictions identified in the applicable station procedures are met. All EOOS options allow for three recirculation loop operation. Operation up to 67.:5 Mlbfhr core flow is licensed for this cycle (Reference 2). Each mode supports operation with up to l0°F reduction in feedwater temperature and each mode may be coincident with coastdown operation.

The minimum coastdown power level is 40% per GESTAR II (Methodology Document 1).

Table7-1 Modes of Operation (Reference 2)

Options Allowed Operatin2 Re2ion Four/Five-loop Operation, FWP Combination 1, Option A or B Yes 1 Four/Five-loop Operation, FWP Combination 2, Option A or B Yes 1 PROOS, Four/Five-loop Operation, FWP Combination 1 or 2, OptionAorB Yes 1 Three-loop Operation, FWP Combination 1, Option A or B Yes 2 Three-loop Operation, FWP Combination 2, Option A or B Yesz PROOS, Three-loop Operation, FWP Combination I or 2, Option A orB Yes2 1

In 4-loop operation, power is limited to 90.5% ofrated power/100% ofrated core flow if the Out-of-Service (OOS) loop is isolated from the reactor as described in Section 3. If the OOS loop is un-isolated there are no rated power restrictions (Reference 2).

2 In 3-loop operation, power is limited to 90% of rated power/75% ofrated core flow regardless of whether the OOS recirculation loops are isolated or un-isolated as described in Section 3 (Reference 2).

Page 15of19

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1. Rev. 0 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 8.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

1. "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-20, December 2013 and U.S.

Supplement NEDE-24011-P-A-20-US, December 2013.

9.0 References

l. "Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License", Docket No. 50-220, License No. DPR-63, Appendix A- Radiological Technical Specifications.
2. "Supplemental Reload Licensing Report for Nine Mile Point I Reload 23 Cycle 22", Global Nuclear Fuel Document No. 002N2884-SRLR, Revision 0, November 2014.
3. "Fuel Bundle Information Report for Nine Mile Point l Reload 23 Cycle 22", Global Nuclear Fuel Document No. 002N2885-FBIR, Revision 0, November2014.
4. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II), Global Nuclear Fuel Document No. NEDC-33270P, Revision 5, May 2013.
5. "Limiting Relationship Between Core Power and Core Flow Rate (TAC 63532)," NRC Letter, Nine Mile Point 1 Technical Specification Amendment 92 to Facility Operating License No. DPR-63, March 24, 1987.
6. "Nine Mile Point Nuclear Station Unit 1 GNF2 ECCS-LOCA Evaluation," GE Hitachi Nuclear Energy Document No. 0000-0098-3457-R2, March2013.
7. "General Electric Boiling Water Reactor Extended Load Line Limit Analysis for Nine Mile Point 1 Cycle 9," General Electric Document No. NEDC-31126, February 1986.
8. "Nine Mile Point 1 Cycle 24 Limiting Load Line Analysis," Global Nuclear Fuel Letter, Document No.

002N5662-RO, March 18, 2015.

Page 16 of19 L _ _ _ _ _ __

I I t I Exe]on Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point l, Rev. 0 Core Operating Limits Report for Nine Mile Point l Cycle 22 Appendix A U02/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEi 1-P9DUB381-14GZ-100T-145-T6-2946 (GEi l)

Bundle Number: 2946 Peak Pellet Exposure 002 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 11.00 20.00 (18.14) ILOO 30.00 (27.22) 9.88 70.00 (63.50) 6.38 Peak Pellet Exposure Most Limiting Gadolinia LHGRLimit 1 GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 9.90 16.92 (15.35) 9.90 26.54 (24.08) 8.89 65.03 (59.00) 5.74 1

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 5.0% Gd).

Page 17 of19

  • ' JI 1 Exelon Nuclear- Nuclear Fuels Doc ID: COLRNine Mile Point I, Rev. 0 Core Operating Limits Report for Nine Mile Point I Cycle 22 U02/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEi l-P9DUB380-13GZ-IOOT-145-T6-2948(GEi1)

Bundle Number: 2948 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 11.00 20.00 (18.14) 11.00 30.00 (27.22) 9.88 70.00 (63.50) 6.38 Peak Pellet Exposure Most Limiting Gadolinia LHGRLimit 2 GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 9.43 16.52 (14.99) 9.43 25.95 (23.54) 8.47 63.65 (57.74) 5.47 2

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 7.0% Gd).

Page 18of19

" '

  • 1 Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 0 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 U02/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEi 1-P9DUB376-12GZ-IOOT-145-T6-2586 (GEI l)

Bundle Number: 2586 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 11.00 20.00 (18.14) 11.00 30.00 (27.22) 9.88 70.00 (63.50) 6.38 Peak Pellet Exposure Most Limiting Gadolinia LHGRLimit 3 GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 9.70 16.79 (15.23) 9.70 26.35 (23.90) 8.71 64.58 (58.59) 5.62 3

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 6.0% Gd).

Page 19of19

, l

  • 1 Enclosure 2 Core Operating Limits Report For Nine Mile Point Unit 1 Cycle 22 Revision 1

Ir l .t I Exelon Nuclear - Nuclear Fuels Doe ID: COLR Nine Mile Point 1, Rev. 1 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 CORE OPERATING LIMITS REPORT FOR NINE MILE POINT NUCLEAR STATION UNIT1RELOAD23CYCLE22 2/8/17 Prepared By: Date: _ _ _ __

B. Lambert Reviewed IBy: Date: _2/8/17 Independent Reviewer Reviewed By:

J. Darweesh Reactor Engineering Reviewer Reviewed By: Date: 02/13/2017 Engineering Safety Analysis Reviewer

~~.c~

Reviewed By: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _2_1_14_1_1_7_

R. Close Station Supplemental Reviewer kio8°4;J Date: __ 02_1_20_1_20_1_1_

Approved By:

. A. Johnson Manager - BWR Design Station Qualified Review By: Date:

Page 1 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table of Contents Page 1.0 Terms and Definitions 5 2.0 General lnfonnation 6 3.0 MAPLHGR Limits 7 4.0 MCPRLimits 12 5.0 LHGRLimits 14 6.0 Limiting Power I Flow Line 15 7.0 Modes of Operation 16 8.0 Methodology 17 9.0 References 17 Appendix A 18 Page 2 of20

  • I a. I Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 J Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Record of COLR Nine Mile Point 1 Cycle 22 Revisions Revision Description Rev. Number - 1 Revise Reference 2 and Reference 6 and revise footnotes for Table 3-10 and Table 7-1.

The COLR Nine Mile Point I, Rev. 0 FCMS version has an illegible Appendix A (see IR 2626201 ). Appendix A has been verified to be legible in Revision I.

Rev. Number-0 New Issuance for Cycle 22 Page 3 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure -

Bundle: GEi l-P9DUB376-12GZ-100T-145-T6-2586 7 Table 3-2 MAPLHGR Versus Average Planar Exposure -

Bundle: GEl l-P9DUB381-14GZ-100T-145-T6-2946 8 Table 3-3 MAPLHGR Versus Average Planar Exposure -

Bundle: GE1 l-P9DUB380-13GZ-100T-145-T6-2948 8 Table 3-4 MAPLHGR Versus Average Planar Exposure-Bundle: GNF2-PlODG2B384-16GZ-lOOT2-145-T6-335 l 9 Table 3-5 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-PlODG2B386-13GZ-lOOT2-145-T6-3352 9 Table 3-6 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-PlODG2B384-16GZ-lOOT2-145-T6-4133 10 Table 3-7 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-PlODG2B386-13GZ-lOOT2-145-T6-4134 10 Table 3-8 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-PlODG2B37 l-16GZ-100T2-145-T6-4312 11 Table 3-9 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-PlODG2B375-l lG5.0-lOOT2-145-T6-4313 11 Table 3-10 MAPLHGR Multiplier for Four and Three Recirculation Loop Operation 11 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 12 Table 4-2 MCPR Adder for Three Recirculation Loop Operation 13 Table 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp 13 Table 4-4 Operating Limit MCPR Multiplier, Kf 13 Table 5-1 Linear Heat Generation Rate Limits - U02 Rods 14 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods 14 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) for PROOS 15 Table 7-1 Modes of Operation 16 List of Figures Figure 6-1 Limiting Power/Flow Line 15 Page 4 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 1.0 Terms and Definitions ARTS APRM, Rod Block, and Technical Specification Improvement Program ELLLA Extended Load Line Limit Analysis EOOS Equipment Out of Service EOR End of Rated. The cycle exposure at which reactor power is equal to rated thermal power with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FWP Combination 1 Feedwater Pump Combination 1 as defined in Nl-OP-16, i.e. Turbine Driven Feedwater Pump (TDFWP) in service AND one Motor Driven Feedwater Pump (MDFWP) in service (bounds TDFWP in service OR one MDFWP in service OR two MDFWPs in service).

FWP Combination 2 Feedwater Pump Combination 2 as defined in Nl-OP-16, i.e. TDFWP in service AND two MDFWPs in service.

Kp Off-rated power dependent OLMCPR multiplier Kf Off-rated flow dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRFAC(F) Off-rated LHGR flow dependent thermal limit multipliers LHGRF AC(P) Off-rated LHGR power dependent thermal limit multipliers MAPFAC(F) Off-rated flow dependent MAPLHGR multiplier MAPF AC(P) Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) Off-rated flow dependent OLMCPR MCPR(P) Off-rated power dependent OLMCPR OLMCPR Operating Limit Minimum Critical Power Ratio OOS Out of Service PROOS Pressure Regulator Out of Service Page 5 of20

~ I , I Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 2.0 General Information This report provides the following cycle-specific parameter limits for Nine Mile Point Nuclear Station Unit I Cycle 22:

  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
  • Operating Limit Minimum Critical Power Ratio (OLMCPR)
  • MCPR thermal limit adjustments and multipliers (MCPR(P) or MCPR(F))
  • Three recirculation loop operation MCPR adjustment
  • LHGR thermal limit multipliers (LHGRFAC(P))
  • MAPLHGR four and three recirculation loop operation multipliers
  • Linear Heat Generation Rate (LHGR)
  • Limiting Power I Flow Line This report is prepared in accordance with Technical Specification 6.6.5 of Reference 1. Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values. Nine Mile Point Unit I is a non-ARTs plant that utilizes ELLLA operating domain.

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

  • Extended Load Line Limit down to the minimum licensed core flow (i.e., 85.0% of rated) during full power operation,
  • Rated core flow is 67.5 Mlb/hr,
  • End-of-cycle coastdown to a minimum power level of 40% of rated power,
  • Feedwater temperature of no more than -l0°F off nominal is licensed for this cycle.

Further information on the cycle-specific analyses for Nine Mile Point Unit 1 Cycle 22 and the associated operating domains discussed above is available in Reference 2.

Page 6 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 3.0 MAPLHGR Limits 3.1 Technical Specification 3.1.7.a, 3.1.7.e 3.2 Description The MAPLHGR limits for each bundle type as a function of average planar exposure is given in Tables 3-1 through 3-9. For partial loop operation, a fuel-type-dependent multiplier is used, which is shown in Table 3-10. For operation with.either four or three recirculation loops in service, multiply the most limiting values shown in Tables 3-1 through 3-3 by the GE! 1 value in Table 3-10 and multiply the most limiting values shown in Tables 3-4 through 3-9 by the GNF2 value in Table 3-10. The power and flow dependent multipliers for MAPLHGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F); therefore, MAPFAC(P) and MAPFAC(F) are equal to 1.0 for all power and flow conditions (Reference 2). LHGRF AC(P) and LHGRF AC(F) are addressed in Section 5.0.

Table 3-1 MAPLHGR Versus Average Planar Exposure-Bundle: GE11-P9DUB376-12GZ-100T-145-T6-2586 (Reference 2)

Average Planar Exposure MAPLHGR Limit1 (GWD/ST) (kW/ft) 0.00 9.63 0.20 9.63 1.00 9.60 5.00 9.40 10.00 9.37 15.00 9.24 20.00 8.76 25.00 8.34 35.00 8.10 45.00 8.03 55.00 8.02 65.00 6.18 1

These MAPLHGRs are not lattice dependent.

Page 7 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 3-2 MAPLHGR Versus Average Planar Exposure-Bundle: GE11-P9DUB381-14GZ-100T-145-T6-2946 (Reference 2)

MAPLHGR Limit1 Average Planar (kW/ft)

Exposure (GWD/ST) Lattice Lattice Lattice Lattice Lattice Lattice 7433 7439 7440 7441 7442 7443 0.00 10.24 10.24 10.19 10.19 10.19 10.19 0.20 10.24 10.24 10.19 10.19 10.19 10.19 1.00 10.20 10.20 10.19 10.19 10.19 10.19 5.00 9.91 9.91 9.85 9.85 9.85 9.85 10.00 9.42 9.42 9.34 9.34 9.34 9.34 15.00 9.22 9.22 9.19 9.19 9.19 9.19 20.00 9.18 9.18 9.19 9.19 9.19 9.19 25.00 8.64 8.64 8.63 8.63 8.63 8.63 35.00 8.08 8.08 8.08 8.08 8.08 8.08 45.00 8.02 8.02 7.99 7.99 7.99 7.99 55.00 8.00 8.00 7.99 7.99 7.99 7.99 65.00 7.97 7.97 7.96 7.96 7.96 7.96 Table 3-3 MAPLHGR Versus Average Planar Exposure- Bundle: GE11-P9DUB380-13GZ-IOOT-145-T6-2948 (Reference 2)

MAPLHGR Limit 1 Average Planar (kW/ft)

Exposure (GWD/ST) Lattice Lattice Lattice Lattice Lattice Lattice 7433 7449 7450 7451 7447 7448 0.00 9.71 9.71 9.69 9.69 9.69 9.69 0.20 9.71 9.71 9.69 9.69 9.69 9.69 1.00 9.68 9.68 9.67 9.67 9.67 9.67 5.00 9.56 9.56 9.50 9.50 9.50 9.50 10.00 9.38 9.38 9.32 9.32 9.32 9.32 15.00 9.23 9.23 9.24 9.24 9.24 9.24 20.00 9.28 9.28 9.31 9.31 9.31 9.31 25.00 8.43 8.43 8.45 8.45 8.45 8.45 35.00 8.09 8.09 8.09 8.09 8.09 8.09 45.00 7.98 7.98 8.02 8.02 8.02 8.02 55.00 7.97 7.97 7.98 7.98 7.98 7.98 65.00 7.91 7.91 7.93 7.93 7.93 7.93 1

These MAPLHGRs are lattice dependent.

Page 8 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 3-4 MAPLHGR Versus Average Planar Exposure- Bundle: GNF2-P10DG2B384-16GZ-100T2-145-T6-3351 (Reference 2)

Average Planar Exposure MAPLHGR Limit1 (GWD/ST) (kW/ft) 0.00 7.91 0.20 7.91 1.00 7.88 5.00 7.81 10.00 7.70 15.00 7.58 20.00 7.03 25.00 6.68 35.00 6.51 45.00 6.27 55.00 6.14 65.00 6.05 Table3-5 MAPLHGR Versus Average Planar Exposure - Bundle: GNF2-P10DG2B386-13GZ-100T2-145-T6-3352 (Reference 2)

Average Planar Exposure MAPLHGR Limit1 (GWD/ST) (kW/ft) 0.00 7.81 0.20 7.81 1.00 7.92 5.00 7.83 10.00 7.71 15.00 7.73 20.00 7.09 25.00 6.68 35.00 6.52 45.00 6.26 55.00 6.15 65.00 6.05 1

These MAPLHGRs are not lattice dependent.

Page 9 of20

Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 3-6 MAPLHGR Versus Average Planar Exposure- Bundle: GNF2-P10DG2B384-16GZ-100T2-145-T6-4133 (Reference 2)

Average Planar Exposure MAPLHGR Limit1 (GWD/ST) (kW/ft) 0.00 7.90 0.20 7.90 l.00 7.85 5.00 7.79 10.00 7.73 15.00 7.74 20.00 7.06 25.00 6.68 35.00 6.51 45.00 6.28 55.00 6.15 65.00 6.05 Table 3-7 MAPLHGR Versus Average Planar Exposure-Bundle: GNF2-P10DG2B386-13GZ-100T2-145-T6-4134 (Reference 2)

Average Planar Exposure MAPLHGR Limit 1 (GWD/ST) (kW/ft) 0.00 7.78 0.20 7.78 1.00 7.84 5.00 7.83 10.00 7.71 15.00 7.73 20.00 7.09 25.00 6.67 35.00 6.52 45.00 6.26 55.00 6.15 65.00 6.05 1

These MAPLHGRs are not lattice dependent.

Page 10 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table3-8 MAPLHGR Versus Average Planar Exposure - Bundle: GNF2-P10DG2B371-16GZ-100T2-145-T6-4312 (Reference 2)

Average Planar Exposure MAPLHGR Limit 1 (GWD/ST) (kW/ft) 0.00 7.96 0.20 7.96 1.00 7.96 5.00 7.88 10.00 7.76 15.00 7.63 20.00 7.16 25.00 6.68 35.00 6.50 45.00 6.29 55.00 6.18 65.00 6.09 Table 3-9 MAPLHGR Versus Average Planar Expdsure - Bundle: GNF2-Pl ODG2B375-l 1GS.0-1 OOT2-145-T6-4313 (Reference 2)

Average Planar Exposure MAPLHGR Limit 1 (GWD/ST) (kW/ft) 0.00 7.90 0.20 7.90 1.00 7.91 5.00 7.85 10.00 7.76 15.00 7.65 20.00 7.25 25.00 6.69 35.00 6.45 45.00 6.28 55.00 6.17 65.00 6.08 Table 3-10 MAPLHGR Multiplier for Four and Three Recirculation Loop Operation (Reference 2)

Fuel Type Four and Three Loop Operation Multiplier2 GEi 1 0.98 GNF2 0.99 1

These MAPLHGRs are not lattice dependent.

2 The 4-loop MAPLHGR multiplier is applicable up to 100% of rated power and 100% of rated core flow if the Out-of-Service (OOS) loop is isolated or un-isolated from the reactor. The 3-loop MAPLHGR Multiplier is applicable to 90% rated power and 75% rated core flow regardless of whether the OOS recirculation loops are isolated or un-isolated.

Page 11 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point I, Rev. I I Core Operating Limits Report for Nine Mile Point I Cycle 22 4.0 MCPR Limits 4.1 Technical Specification 3.1.7.c, 3.1.7.e 4.2 Description The OLMCPR is determined for a given power and flow condition by evaluating the power dependent MCPR and the flow dependent MCPR and selecting the greater of the two. Tables 4-1 and 4-2 are derived from Reference 2 and are valid for all Cycle 22 operating domains. Nine Mile Point Unit I Cycle 22 has a mid-cycle MCPR breakpoint, as defined in Table 4-1. An adder, presented in Table 4-2, is required to be applied to all limits in Table 4-1 and MCPR(P) in Table 4-3 in the event of three recirculation loop operation. Table 4-1 and 4-2 limits are bounding for both GEi I and GNF2 fuel types.

The power dependent MCPR limits are presented in Table 4-3 and are valid for both GEl l and GNF2 fuel types (Reference 2). When core thermal power is greater than or equal to 45% of rated, the applicable Kp multiplier from Table 4-3 is applied to the applicable rated condition OLMCPR value in Table 4-1 or adjusted OLMCPR value determined by using Table 4-2. Below 45% rated thermal power, the MCPR(P) limits in Table 4-3 are applied directly. The appropriate MCPR(P) or Kp value may be determined by linear interpolation.

The flow adjusted OLMCPR is determined by multiplying the applicable rated condition OLM CPR provided by either Table 4-1 or 4-2 by the applicable Kf multiplier given in Table 4-

4. The Kf multipliers are valid for both GEl 1 and GNF2 fuel types and are documented in Reference 2. The appropriate Kfvalue may be determined by linear interpolation.

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

(All Fuel Types, Four/Five Recirculation Loop Operation)

(Reference 2)

Cycle Exposure Feedwater Pump SCRAM Time 2 < EOR-3609 2: EOR-3609 Combination 1 Option MWd/ST MWd/ST B 1.47 1.54 FWP Combination 1 A 1.57 1.64 B 1.52 1.59 FWP Combination 2 A 1.62 1.69 1

0LMCPR values are independent of pressure regulator in-service or out-of service conditions.

2 For tau (T) = 0, use SCRAM Time Option B limits. For ('r) = 1, use SCRAM Time Option A limits. When tau does not equal 0 or I, use linear interpolation. Tau is defined as:

't =(<ave - <n) I (<A - TB) where

'A= 0.868 seconds, control rod average scram insertion time limit to notch 39

<s = 0.672 + 1.65 * [ N1 !"f,{= 1 Ni ] 112

  • 0.016

<ave= L'i=1 Niri I L'i=1 Ni where n =number of surveillance tests performed in cycle; N; = number of active control rods measured in the i"' surveillance test; 't; = average scram time to notch 39 of all rods measures in the i"' surveillance test; and N 1 = total number of active rods measured.

Page 12 of20

'° I .°I

  • Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 4-2 MCPR Adder for Three Recirculation Loop Operation (All Fuel Types)

(Reference 2)

Three Recirculation Loop Operation 0.03 Adder 1 Table 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp (All Fuel Types)

(Reference 2)

Core Core Thermal Power(% of Rated)

EOOS Flow 0 25 <45 ~45 65 85 >85 100 Combination (%of Operating Limit MCPR, Operating Limit MCPR Multiplier, Kp rated) MCPR(P FWP :s; 60 3.28 3.28 2.36 1.349 1.216 1.133 1.133 1.000 Combination I > 60 3.40 3.40 2.86 FWP :s; 60 3.28 3.28 2.36 1.349 1.216 1.133 1.133 1.000 Combination 2 > 60 3.40 3.40 2.86

s; 60 3.28 3.28 2.36 PROOS 2 1.553 1.336 1.198 1.133 1.000

> 60 3.40 3.40 2.86 Table 4-4 Operating Limit MCPR Multiplier, Kf (All Fuel Types)

(Reference 2)

Flow MCPR

(%rated) Multiplier, Kf 0.0 1.500 45.0 1.500

>45.0 1.132 75.0 1.000 100.0 1.000 1

Increase the values in Table 4-1 and the MCPR(P) values in Table 4-3 by 0.03 in the event of Three Recirculation Loop Operation.

2 Limits apply to PROOS coincident with FWP Combination 1 or 2.

3 Values are applicable up to a Maximum Runout Flow of 102.5% of rated. Values apply to operation in either FWP Combination I or 2 with or without Pressure Regulator in-service.

Page 13 of20

t I ~

  • Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 5.0 LHGR Limits 5.1 Technical Specification 3.1.7.b 5.2 Description The Linear Heat Generation Rate (LHGR) for all fuel bundles shall not exceed either 11.0 kW/ft 1 or the LHGR limits presented in Tables 5-1 and 5-2. Linear interpolation should be used for points not listed in Appendix A or Appendix B of Reference 4. Power adjusted LHGR limits are required for operation with PROOS at greater than or equal to 45% RTP. Below 45% RTP, no additional limits are required. These power dependent LHGR multipliers (LHGRFAC(P)) are provided in Table 5-3 for Option Band Option A scram times and are applicable to both GEI 1 and GNF2 fuel types (Reference 2). The power adjusted LHGR is determined by multiplying the applicable Appendix A LHGR limit by the LHGR multiplier, LHGRFAC(P). The LHGRFAC(P) curves are independent of recirculation loop operability. The appropriate LHGRFAC(P) values may be determined by linear interpolation. Flow dependent LHGR multipliers (LHGRFAC(F))

are not required (Reference 2).

Table 5-1 Linear Heat Generation Rate Limits - U02 Rods (References 3 and 4)

Fuel Type LHGR GEi 1 See Appendix A GNF2 1 See Aooendix B of Reference 4 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (References 3 and 4)

Fuel Type LHGR GEI 1 See Appendix A GNF2 1 See Appendix B of Reference 4 1

GNF2 LHGR limit has been set down to a maximum value of 11 kW/ft to address Emergency Procedure Guidelines (EPG) requirements (Reference 6).

Page 14 of20

  • l ) ,

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) for PROOS (All Fuel Types)

(Reference 2)

Core Thermal Power (% of rated)

Scram Time Option 0 <45 2:45 65 85 100 Option A (i.e. t > O) 1.000 1.000 0.518 0.518 0.636 1.000 Option B 1.000 1.000 0.737 0.867 0.987 1.000 6.0 Limiting Power/Flow Line 6.1 Technical Specification 3.1.7.d, 3.1.7.e 6.2 Description The Nine Mile Point Unit 1 power/flow relationship is shown in the figure below.

Figure 6-1 Limiting Power/Flow Line (References 5, 7, and 8) 120 85.0. I 00.0) ( 00.0, I 00.0) 100 ~

.. ~

0:

~

.....Q 80 ~

V"'

~

t;:

Q 60

~

~ Power= 0.55* W+53 e:..

~ 40 Q

u 20 0

0 20 40 60 80 100 120 Core Flow (% of Rated)

Page 15 of20

l Exelon Nuclear - Nuclear Fuels Doc ID
COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 7.0 Modes of Operation 7.1 Description The allowable modes of operation are found in Table 7-1. Operation with PROOS is supported in all modes of operation, provided the restrictions identified in the applicable station procedures are met. All EOOS options allow for three recirculation loop operation. Operation up to 67.5 Mlb/hr core flow is licensed for this cycle (Reference 2). Each mode supports operation with up to 10°F reduction in feedwater temperature and each mode may be coincident with coastdown operation.

The minimum coastdown power level is 40% per GESTAR II (Methodology Document 1).

Table 7-1 Modes of Operation (Reference 2)

Options Allowed Operating Region Four/Five-loop Operation, FWP Combination 1, Option A or B Yes Four/Five-loop Operation, FWP Combination 2, Option A or B Yes PROOS, Four/Five-loop Operation, FWP Combination 1 or 2, Option A or B Yes Three-loop Operation, FWP Combination 1, Option A or B Yes 1 Three-loop Operation, FWP Combination 2, Option A or B Yes 1 PROOS, Three-loop Operation, FWP Combination I or 2, Option A orB Yes 1 1

In 3-loop operation, power is limited to 90% of rated power/75% ofrated core flow regardless of whether the OOS recirculation loops are isolated or un-isolated as described in Section 3 (Reference 2).

Page 16 of20

) }

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 8.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

I. "General Electric Standard Application for Reactor Fuel," NEDE-240 l l-P-A-20, December 2013 and U.S.

Supplement NEDE-2401 l-P-A-20-US, December 2013.

9.0 References I. "Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License, Docket No. 50-220, License No. DPR-63, Appendix A - Radiological Technical Specifications.

2. "Supplemental Reload Licensing Report for Nine Mile Point 1 Reload 23 Cycle 22", Global Nuclear Fuel Document No. 002N2884-SRLR, Revision 2, January 2016.
3. "Fuel Bundle Information Report for Nine Mile Point 1 Reload 23 Cycle 22", Global Nuclear Fuel Document No. 002N2885-FBIR, Revision 0, November 2014.
4. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC-33270P, Revision 5, May 2013.
5. "Limiting Relationship Between Core Power and Core Flow Rate (TAC 63532)," NRC Letter, Nine Mile Point I Technical Specification Amendment 92 to Facility Operating License No. DPR-63, March 24, 1987.
6. "Nine Mile Point Nuclear Station Unit 1 GNF2 ECCS-LOCA Evaluation," GE Hitachi Nuclear Energy Document No. 0000-0098-3457-R2/000N 1093-RO, January 2014.
7. "General Electric Boiling Water Reactor Extended Load Line Limit Analysis for Nine Mile Point 1 Cycle 9," General Electric Document No. NEDC-31126, February 1986.
8. "Nine Mile Point 1 Cycle 24 Limiting Load Line Analysis," Global Nuclear Fuel Letter, Document No.

002N5662-RO, March 18, 2015.

Page 17 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine lUile Point l, Rev. l I Core Operating Limits Report for Nine Mile Point l Cycle 22 Appendix A U02 /Gd Thermal-Mechanical LHGR Limits Bundle Type: GEi 1-P9DUB381-14GZ-100T-145-T6-2946(GEi1)

Bundle Number: 2946 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 11.00 20.00 (18.14) 1 l.00 30.00 (27.22) 9.88 70.00 (63.50) 6.38 Peak Pellet Exposure Most Limiting Gadolinia LHGRLimit 1 GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 9.90 16.92 (15.35) 9.90 26.54 (24.08) 8.89 65.03 (59.00) 5.74 1

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 5.0% Gd).

Page 18 of20

Exelon Nuclear- Nuclear Fuels Doc ID; COLR Nine Mile Point 1, Rev. 1 I Core Operating Limits Report for Nine Mile Point I Cycle 22 U02/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEi I-P9DUB380-13GZ-IOOT-145-T6-2948 (GEl l)

Bundle Number: 2948 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 11.00 20.00 (18.14) 11.00 30.00 (27.22) 9.88 70.00 (63.50) 6.38 Peak Pellet Exposure Most Limiting Gadolinia LHGRLimit 2 GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 9.43 16.52 (14.99) 9.43 25.95 (23.54) 8.47 63.65 (57.74) 5.47 2

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 7.0% Gd).

Page 19 of20

Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine l\'l:ile Point 1, Rev. I I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 U02/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEi l-P9DUB376-12GZ-IOOT-145-T6-2586 (GEi I)

Bundle Number: 2586 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 11.00 20.00 (18.14) 11.00 30.00 (27.22) 9.88 70.00 (63.50) 6.38 Peak Pellet Exposure Most Limiting Gadolinia LHGRLimit 3 GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 9.70 16.79 (15.23) 9.70 26.35 (23.90) 8.71 64.58 (58.59) 5.62 3

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 6.0% Gd).

Page 20 of20

Enclosure 3 Core Operating Limits Report For Nine Mile Point Unit 1 Cycle 22 Revision 2

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point I, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 CORE OPERATING Lll\.flTS REPORT FOR NINE MlLE POINT NUCLEAR STATION UNIT 1 RELOAD 23 CYCLE 22 Prepared By: Date: 2/8/17 B. Lambert 2/8/17 Reviewed By: Date: _ _ _ __

Independent Reviewer Reviewed By:~~~ Date: J I ff I r1-J. Darweesh Reactor Engineering Reviewer Reviewed By: Date: 02/13/2017 Engineering Safety Analysis Reviewer AJ l. /) 1).

Reviewed By: _ _ _---_  !<__~---~=--------Date: 2/14/17 R. Close Station Supplemental Reviewer Approved By: --~?14;) A. Johnson Date: _ 02/20/2017 Manager - BWR Design StaHonQua\ifiod Review By:

L~ ( a-- Date: c:24f; 7.

. e Page I of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 J Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table of Contents Page 1.0 Terms and Definitions 5 2.0 General Information 6 3.0 MAPLHGR Limits 7 4.0 MCPRLimits 12 5.0 LHGRLimits 14 6.0 Limiting Power I Flow Line 15 7.0 Modes of Operation 16 8.0 Methodology 17 9.0 References 17 Appendix A 18 Page 2 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point I, Rev. 2 I Core Operating Limits Report for Nine Mile Point I Cycle 22 Record ofCOLR Nine Mile Point 1Cycle22 Revisions Revision Description Rev. Number - 2 Removed GNF proprietary FBIR (Appendix A). Appendix A now contains non-proprietary Linear Heat Generation Rate Limits for GE 11 fuel.

Rev. Number - 1 Revise Reference 2 and Reference 6 and revise footnotes for Table 3~ 10 and Table 7-1.

The COLR Nine Mile Point 1, Rev. 0 FCMS version has an illegible Appendix A (see IR 2626201). Appendix A has been verified to be legible in Revision 1.

Rev. Number - 0 New Issuance for Cycle 22 Page 3 of20

t I 'J I Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure -

Bundle: GEl l-P9DUB376-12GZ-100T-145-T6-2586 7 Table 3-2 MAPLHGR Versus Average Planar Exposure -

Bundle: GEl l-P9DUB381-14GZ-100T-145-T6-2946 8 Table 3-3 MAPLHGR Versus Average Planar Exposure -

Bundle: GEi l-P9DUB380-13GZ-100T-145-T6-2948 8 Table 3-4 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-P 1ODG2B384- l 6GZ-100T2- l 45-T6-335 l 9 Table 3-5 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-PlODG2B386-13GZ-lOOT2-145-T6-3352 9 Table 3-6 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-PlODG2B384-16GZ-lOOT2-145-T6-4133 10 Table 3-7 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-P IODG2B3 86-13GZ-100T2- l 45-T6-4 l 34 10 Table 3-8 MAPLHGR Versus Average Planar Exposure-Bundle: GNF2-PlODG2B371-16GZ-lOOT2-145-T6-4312 11 Table 3-9 MAPLHGR Versus Average Planar Exposure -

Bundle: GNF2-P I ODG2B375- I l 05.0-1OOT2-l45-T6-4313 11 Table 3-10 MAPLHGR Multiplier for Four and Three Recirculation Loop Operation 11 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 12 Table 4-2 MCPR Adder for Three Recirculation Loop Operation 13 Table 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp 13 Table 4-4 Operating Limit MCPR Multiplier, Kf 13 Table 5-1 Linear Heat Generation Rate Limits - U02 Rods 14 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods 14 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) for PROOS 15 Table 7-1 Modes of Operation 16 List of Figures Figure 6-1 Limiting Power/Flow Line 15 Page 4 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 1.0 Terms and Definitions ARTS APRM, Rod Block, and Technical Specification Improvement Program ELLLA Extended Load Line Limit Analysis EOOS Equipment Out of Service EOR End of Rated. The cycle exposure at which reactor power is equal to rated thermal power with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.

FWP Combination 1 Feedwater Pump Combination 1 as defined in N l -OP-16, i.e. Turbine Driven Feedwater Pump (TDFWP) in service AND one Motor Driven Feedwater Pump (MDFWP) in service (bounds TDFWP in service OR one MDFWP in service OR two MDFWPs in service).

FWP Combination 2 Feedwater Pump Combination 2 as defined in Nl-OP-16, i.e. TDFWP in service AND two MDFWPs in service.

Kp Off-rated power dependent OLMCPR multiplier Kf Off-rated flow dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRFAC(F) Off-rated LHGR flow dependent thermal limit multipliers LHGRFAC(P) Off-rated LHGR power dependent thermal limit multipliers MAPFAC(F) Off-rated flow dependent MAPLHGR multiplier MAPFAC(P)

  • Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) Off-rated flow dependent OLMCPR MCPR(P) Off-rated power dependent OLMCPR OLMCPR Operating Limit Minimum Critical Power Ratio OOS Out of Service PROOS Pressure Regulator Out of Service Page 5 of20

. ' ) '

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1Cycle22 2.0 General Information This report provides the following cycle-specific parameter limits for Nine Mile Point Nuclear Station Unit 1 Cycle 22:

  • Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
  • Operating Limit Minimum Critical Power Ratio (OLMCPR)
  • MCPR thermal limit adjustments and multipliers (MCPR(P) or MCPR(F))
  • . Three recirculation loop operation MCPR adjustment
  • LHGR thermal limit multipliers (LHGRFAC(P))
  • MAPLHGR four and three recirculation loop operation multipliers
  • Linear Heat Generation Rate (LHGR)
  • Limiting Power I Flow Line This report is prepared in accordance with Technical Specification 6.6.5 of Reference I. Power and flow dependent limits are listed for various power and flow levels. Linear intei:polation is to be used to find intermediate values. Nine Mile Point Unit I is a non-ARTS plant that utilizes ELLLA operating domain.

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

  • Extended Load Line Limit down to the minimum licensed core flow (i.e., 85.0% of rated) during full power operation,
  • Rated core flow is 67.5 Mlb/hr,
  • End-of-cycle coastdown to a minimum power level of 40% ofrated power,
  • Feedwater temperature of no more than -10°F off nominal is licensed for this cycle.

Further information on the cycle-specific analyses for Nine Mile Point Unit I Cycle 22 and the associated operating domains discussed above is available in Reference 2.

Page 6 of20

J I ) "'

Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point I Cycle 22 3.0 MAPLHGR Limits 3.1 Technical Specification 3.1.7.a, 3.1.7.e 3.2 Description The MAPLHGR limits for each bundle type as a function of average planar exposure is given in Tables 3-1 through 3-9. For partial loop operation, a fuel-type-dependent multiplier is used, which is shown in Table 3-10. For operation with either four or three recirculation loops in service, multiply the most limiting values shown in Tables 3-1 through 3-3 by the GEl 1 value in Table 3-10 and multiply the most limiting values shown in Tables 3-4 through 3-9 by the GNF2 value in Table 3-10. The power and flow dependent multipliers for MAPLHGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F); therefore, MAPFAC(P) and MAPFAC(F) are equal to 1.0 for all power and flow conditions (Reference 2). LHGRF AC(P) and LHGRFAC(F) are addressed in Section 5.0.

Table3-1 MAPLHGR Versus Average Planar Exposure-Bundle: GE11-P9DUB376-12GZ-100T-145-T6-2586 (Reference 2)

Average Planar Exposure MAPLHGR Limit1 (GWD/ST) (kW/ft) 0.00 9.63 0.20 9.63 1.00 9.60 5.00 9.40 10.00 9.37 15.00 9.24 20.00 8.76 25.00 8.34 35.00 8.10 45.00 8.03 55.00 8.02 65.00 6.18 1

These MAPLHGRs are not lattice dependent.

Page 7 of20

Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 3-2 MAPLHGR Versus Average Planar Exposure- Bundle: GE11-P9DUB381-14GZ-100T-145-T6-2946 (Reference 2)

MAPLHGR Limit1 Average Planar (kW/ft)

Exposure (GWD/ST) Lattice Lattice Lattice Lattice Lattice Lattice 7433 7439 7440 7441 7442 7443 0.00 10.24 10.24 10.19 10.19 10.19 10.19 0.20 10.24 10.24 10.19 10.19 10.19 10.19 1.00 10.20 10.20 10.19 10.19 10.19 10.19 5.00 9.91 9.91 9.85 9.85 9.85 9.85 10.00 9.42 9.42 9.34 9.34 9.34 9.34 15.00 9.22 9.22 9.19 9.19 9.19 9.19 20.00 9.18 9.18 9.19 9.19 9.19 9.19 25.00 8.64 8.64 8.63 8.63 8.63 8.63 35.00 8.08 8.08 8.08 8.08 8.08 8.08 45.00 8.02 8.02 7.99 7.99 7.99 7.99 55.00 8.00 8.00 7.99 7.99 7.99 7.99 65.00 7.97 7.97 7.96 7.96 7.96 7.96 Table3-3 MAPLHGR Versus Average Planar Exposure - Bundle: GE11-P9DUB380-13GZ-100T-145-T6-2948 (Reference 2)

MAPLHGR Limit 1 Average Planar (kW/ft)

Exposure (GWD/ST) Lattice Lattice Lattice Lattice Lattice Lattice 7433 7449 7450 7451 7447 7448 0.00 9.71 9.71 9.69 9.69 9.69 9.69 0.20 9.71 9.71 9.69 9.69 9.69 9.69 1.00 9.68 9.68 9.67 9.67 9.67 9.67 5.00 9.56 9.56 9.50 9.50 9.50 9.50 10.00 9.38 9.38 9.32 9.32 9.32 9.32 15.00 9.23 9.23 9.24 9.24 9.24 9.24 20.00 9.28 9.28 9.31 9.31 9.31 9.31 25.00 8.43 8.43 8.45 8.45 8.45 8.45 35.00 8.09 8.09 8.09 8.09 8.09 8.09 45.00 7.98 7.98 8.02 8.02 8.02 8.02 55.00 7.97 7.97 7.98 7.98 7.98 7.98 65.00 7.91 7.91 7.93 7.93 7.93 7.93 1

These MAPLHGRs are lattice dependent.

Page 8 of20

Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 3-4 MAPLHGR Versus Average Planar Exposure - Bundle: GNF2-P10DG2B384-16GZ-100T2-145-T6-3351 (Reference 2)

Average Planar Exposure MAPLHGR Limit1 (GWD/ST) (kW/ft) 0.00 7.91 0.20 7.91 1.00 7.88 5.00 7.81 10.00 7.70 15.00 7.58 20.00 7.03 25.00 6.68 35.00 6.51 45.00 6.27 55.00 6.14 65.00 6.05 Table 3-5 MAPLHGR Versus Average Planar Exposure- Bundle: GNF2-P10DG2B386-13GZ-100T2-145-T6-3352 (Reference 2)

Average Planar Exposure MAPLHGR Limit 1 (GWD/ST) (kW/ft) 0.00 7.81 0.20 7.81 1.00 7.92 5.00 7.83 10.00 7.71 15.00 7.73 20.00 7.09 25.00 6.68 35.00 6.52 45.00 6.26 55.00 6.15 65.00 6.05 1

These MAPLHGRs are not lattice dependent.

Page 9 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table3-6 MAPLHGR Versus Average Planar Exposure- Bundle: GNF2-P10DG2B384-16GZ-100T2-145-T6-4133 (Reference 2)

Average Planar Exposure MAPLHGR Limit' (GWD/ST) (kW/ft) 0.00 7.90 0.20 7.90 1.00 7.85 5.00 7.79 10.00 7.73 15.00 7.74 20.00 7.06 25.00 6.68 35.00 6.51 45.00 6.28 55.00 6.15 65.00 6.05 Table3-7 MAPLHGR Versus Average Planar Exposure-Bundle: GNF2-PlODG2B386-13GZ-lOOT2-145-T6-4134 (Reference 2)

Average Planar Exposure MAPLHGR Limit 1 (GWD/ST) (kW/ft) 0.00 7.78 0.20 7.78 1.00 7.84 5.00 7.83 10.00 7.71 15.00 7.73 20.00 7.09 25.00 6.67 35.00 6.52 45.00 6.26 55.00 6.15 65.00 6.05 1

These MAPLHGRs are not lattice dependent.

Page 10 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 3-8 MAPLHG R Versus Average Planar Exposure - Bundle: GNF2-Pl ODG2B371-16GZ-1 OOT2-145-T6-4312 (Reference 2)

Average Planar Exposure MAPLHGR Lirnit1 (GWD/ST) (kW/ft) 0.00 7.96 0.20 7.96 1.00 7.96 5.00 7.88 10.00 7.76 15.00 7.63 20.00 7.16 25.00 6.68 35.00 6.50 45.00 6.29 55.00 6.18 65.00 6.09 Table3-9 MAPLHGR Versus Average Planar Exposure-Bundle: GNF2-PlODG2B375-11G5.0-lOOT2-145-T6-4313 (Reference 2)

Average Planar Exposure MAPLHGR Lirnit 1 (GWD/ST) (kW/ft) 0.00 7.90 0.20 7.90 1.00 7.91 5.00 7.85 10.00 7.76 15.00 7.65 20.00 7.25 25.00 6.69 35.00 6.45 45.00 6.28 55.00 6.17 65.00 6.08 Table3-10 MAPLHGR Multiplier for Four and Three Recirculation Loop Operation (Reference 2)

Fuel Type Four and Three Loop Operation Multiplier GEI I 0.98 GNF2 0.99 1

These MAPLHGRs are not lattice dependent.

2 The 4-loop MAPLHGR multiplier is applicable up to 100% of rated power and 100% of rated core flow if the Out-of-Service (OOS) loop is isolated or un-isolated from the reactor. The 3-loop MAPLHGR Multiplier is applicable to 90% rated power and 75% rated core flow regardless of whether the OOS recirculation loops are isolated or un-isolated.

Page 11 of20 L_

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 J Core Operating Limits Report for Nine Mile Point 1 Cycle 22 4.0 MCPR Limits 4.1 Technical Specification 3.1.7.c, 3.1.7.e 4.2 Description The OLMCPR is determined for a given power and flow condition by evaluating the power dependent MCPR and the flow dependent MCPR and selecting the greater of the two. Tables 4-1 and 4-2 are derived from Reference 2 and are valid for all Cycle 22 operating domains. Nine Mile Point Unit 1 Cycle 22 has a mid-cycle MCPR breakpoint, as defined in Table 4-1. An adder, presented in Table 4-2, is required to be applied to all limits in Table 4-1 and MCPR(P) in Table 4-3 in the event of three recirculation loop operation. Table 4-1and4-2 limits are bounding for both GE 11 and GNF2 fuel types.

The power dependent MCPR limits are presented in Table 4-3 and are valid for both GEl 1 and GNF2 fuel types (Reference 2). When core thermal power is greater than or equal to 45% of rated, the applicable Kp multiplier from Table 4-3 is applied to the applicable rated condition OLMCPR value in Table 4-1 or adjusted OLMCPR value determined by using Table 4-2. Below 45% rated thermal power, the MCPR(P) limits in Table 4-3 are applied directly. The appropriate MCPR(P) or Kp value may be determined by linear interpolation.

The flow adjusted OLMCPR is determined by multiplying the applicable rated condition OLM CPR provided by either Table 4-1 or 4-2 by the applicable Kf multiplier given in Table 4-

4. The Kf multipliers are valid for both GEl 1 and GNF2 fuel types and are documented in Reference 2. The appropriate Kfvalue may be determined by linear interpolation.

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

(All Fuel Types,_ Four/Five Recirculation Loop Operation)

(Reference 2)

Cvcle Exoosure Feedwater Pump SCRAM Time 2 < EOR-3609 ~EOR-3609 Com bin ati on 1 Option MWd/ST MWd/ST B 1.47 1.54 FWP Combination 1 A 1.57 1.64 B 1.52 1.59 FWP Combination 2 A 1.62 1.69 1

0LMCPR values are independent of pressure regulator in-service or out-of service conditions.

2 For tau (t) = 0, use SCRAM Time Option B limits. For (t) = 1, use SCRAM Time Option A limits. When tau does not equal 0 or 1, use linear interpolation. Tau is defined as:

T =(Tave - Ts) I (TA - <s) where TA= 0.868 seconds, control rod average scram insertion time limit to notch 39 2

  • s = 0.672 + 1.65 * [ N1 I 'L'i=i Ni ] 11
  • 0.016
  • ave= L'i=1 Niri I Li=1 Ni where n =number of surveillance tests performed in cycle; N; =number of active control rods measured in the/' surveillance test; T; =average scram time to notch 39 of all rods measures in the i"' surveillance test; and N 1 =total number of active rods measured.
  • Page 12 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 4-2 MCPR Adder for Three Recirculation Loop Operation (All Fuel Types)

(Reference 2)

Three Recirculation Loop Operation 0.03 Adder 1 Table 4-3 Power Dependent MCPR Limits and Multipliers MCPR(P) and Kp (All Fuel Types)

(Reference 2)

Core Core Thermal Power (% of Rated)

EOOS Flow 0 25 <45 ~45 65 85 >85 100 Combination (%of Operating Limit MCPR, Operating Limit MCPR Multiplier, Kp rated) MCPR(P1 FWP  ::;; 60 3.28 3.28 2.36 1.349 1.216 1.133 1.133 1.000 Combination 1 > 60 3.40 3.40 2.86 FWP  ::;; 60 3.28 3.28 2.36 1.349 1.216 1.133 1.133 1.000 Combination 2 > 60 3.40 3.40 2.86 2  ::;; 60 3.28 3.28 2.36 PROOS 1.553 1.336 1.198 1.133 1.000

> 60 3.40 3.40 2.86 Table 4-4 Operating Limit MCPR Multiplier, Kf (All Fuel Types)

(Reference 2)

Flow MCPR

(%rated) Multiplier, Kf 0.0 1.500 45.0 1.500

>45.0 1.132 75.0 1.000 100.0 1.000 1

Increase the values in Table 4-1 and the MCPR(P) values in Table 4-3 by 0.03 in the event of Three Recirculation Loop Operation.

2 Limits apply to PROOS coincident with FWP Combination 1 or 2.

3 Values are applicable up to a Maximum Runout Flow of 102.5% of rated. Values apply to operation in either FWP Combination 1 or 2 with or without Pressure Regulator in-service.

Page 13 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 5.0 LHGR Limits 5.1 Technical Specification 3.1.7.b 5.2 Description The Linear Heat Generation Rate (LHGR) for all fuel bundles shall not exceed either 11.0 kW/ft 1 or the LHGR limits presented in Tables 5-1 and 5-2. Linear interpolation should be used for points not listed in Appendix A or Appendix B of Reference 4. Power adjusted LHGR limits are required for operation with PROOS at greater than or equal to 45% RTP. Below 45% RTP, no additional limits are required. These power dependent LHGR multipliers (LHGRF AC(P)) are provided in Table 5-3 for Option Band Option A scram times and are applicable to both GEl 1 and GNF2 fuel types (Reference 2). The power adjusted LHGR is determined by multiplying the applicable Appendix A LHGR limit by the LHGR multiplier, LHGRF AC(P). The LHGRFAC(P) curves are independent of recirculation loop operability. The appropriate LHGRFAC(P) values may be determined by linear interpolation. Flow dependent LHGR multipliers (LHGRF AC(F))

are not required (Reference 2).

Table 5-1 Linear Heat Generation Rate Limits - U02 Rods (References 3 and 4)

Fuel Type LHGR GEi 1 See Appendix A GNF2 1 See Annendix B of Reference 4 Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (References 3 and 4)

Fuel Tvoe LHGR GEl 1 See Appendix A GNF2 1 See Annendix B of Reference 4 1

GNF2 LHGR limit has been set down to a maximum value of 11 kW/ft to address Emergency Procedure Guidelines (EPG) requirements (Reference 6).

Page 14 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 J Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) for PROOS (All Fuel Types)

(Reference 2)

Core Thermal Power (% of rated)

Scram Time Option 0 <45 2:45 65 85 100 Option A (i.e. t > O) 1.000 1.000 0.518 0.518 0.636 1.000 Option B 1.000 1.000 0.737 0.867 0.987 1.000 6.0 Limiting Power/Flow Line 6.1 Technical Specification 3.1.7.d, 3.1.7.e 6.2 Description The Nine Mile Point Unit 1 power/flow relationship is shown ih the figure below.

Figure 6-1 Limiting Power/Flow Line (References 5, 7, and 8) 120 (85.0. I 00.0) ( 00.0, 100.0) 100 ~

0-

~

c:z::

80

__,,,. ~

0

~

~

-:::e.

e_,

""~ 60 0

Q.c Power= 0.55* W+53

...e

.c:

E-<

40

""...0 u

20 0

0 20 40 60 80 100 120 Core Flow (% of Rated)

Page 15 of20

Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 Core Operating Limits Report for Nine Mile Point 1 Cycle 22 7.0 Modes of Operation 7.1 Description The allowable modes ofoperation are found in Table 7-1. Operation with PROOS is supported in all modes of operation, provided the restrictions identified in the applicable station procedures are met. All EOOS options allow for three recirculation loop operation. Operation up to 67.5 Mlb/hr core flow is licensed for this cycle (Reference 2). Each mode supports operation with up to 10°F reduction in feedwater temperature and each mode may be coincident with coastdown operation.

The minimum coastdown power level is 40% per GESTAR II (Methodology Document I).

Table 7-1 Modes of Operation (Reference 2)

Options Allowed Operating Region Four/Five-loop Operation, FWP Combination I, Option A or B Yes Four/Five-loop Operation, FWP Combination 2, Option A or B Yes PROOS, Four/Five-loop Operation, FWP Combination I or 2, Option A or B Yes Three-loop Operation, FWP Combination I, Option A or B Yes 1 Three-loop Operation, FWP Combination 2, Option A or B Yes 1 PROOS, Three-loop Operation, FWP Combination 1 or 2, Option A orB Yes 1 1

In 3-loop operation, power is limited to 90% of rated power/75% ofrated core flow regardless of whether the OOS recirculation loops are isolated or un-isolated as described in Section 3 (Reference 2).

Page 16 of20

Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 8.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

1. "General Electric Standard Application for Reactor Fuel," NEDE-240 l l-P-A-20, December 2013 and U.S.

Supplement NEDE-240 l l-P-A-20-US, December 2013.

9.0 References

1. "Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License", Docket No. 50-220, License No. DPR-63, Appendix A - Radiological Technical Specifications.
2. "Supplemental Reload Licensing Report for Nine Mile Point 1 Reload 23 Cycle 22, Global Nuclear Fuel Document No. 002N2884-SRLR, Revision 2, January 2016.
3. "Fuel Bundle Information Report for Nine Mile Point 1 Reload 23 Cycle 22", Global Nuclear Fuel Document No. 002N2885-FBIR, Revision 0, November2014.
4. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC-33270P, Revision 6, March 2016.
5. "Limiting Relationship Between Core Power and Core Flow Rate (TAC 63532)," NRC Letter, Nine Mile Point l Technical Specification Amendment 92 to Facility Operating License No. DPR-63, March 24, 1987.
6. "Nine Mile Point Nuclear Station Unit l GNF2 ECCS-LOCA Evaluation," GE Hitachi Nuclear Energy Document No. 0000-0098-3457-R2/000N1093-RO, January 2014.
7. "General Electric Boiling Water Reactor Extended Load Line Limit Analysis for Nine Mile Point 1 Cycle 9," General Electric Document No. NEDC-31126, February 1986.
8. "Nine Mile Point 1 Cycle 24 Limiting Load Line Analysis," Global Nuclear Fuel Letter, Document No.

002N5662-RO, March 18, 2015.

Page 17 of20

  • Exelon Nuclear - Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point 1 Cycle 22 Appendix A U02/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEi l-P9DUB381-14GZ-100T-l45-T6-2946 (GEl I)

Bundle Number: 2946 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 11.00 20.00 (18.14) l l.00 30.00 (27.22) 9.88 70.00 (63.50) 6.38 Peak Pellet Exposure Most Limiting Gadolinia LHGRLimit 1 GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 9.90 16.92 (15.35) 9.90 26.54 (24.08) 8.89 65.03 (59.00) 5.74 1

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 5.0% Gd).

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Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point 1, Rev. 2 I Core Operating Limits Report for Nine Mile Point I Cycle 22 U02/Gd Thermal-Mechanical LHGR limits Bundle Type: GEi l-P9DUB380-13GZ-IOOT-145-T6-2948 (GEi I)

Bundle Number: 2948 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 11.00 20.00 (18.14) 11.00 30.00 (2722) 9.88 70.00 (63.50) 6.38 Peak Pellet Exposure Most Limiting Gadolinia LHGRLimit 2 GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 9.43 16.52 (14.99) 9.43 25.95 (23.54) 8.47 63.65 (57.74) 5.47 2

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 7.0% Gd).

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Exelon Nuclear- Nuclear Fuels Doc ID: COLR Nine Mile Point I, Rev. 2 I Core Operafmg Limits Report for Nine Mile Point I Cycle 22 U02 /Gd Thermal-Mechanical LHGR Limits Bundle Type: GEl l-P9DUB376-12GZ-100T-145-T6-2586(GEi1)

Bundle Number: 2586 Peak Pellet Exposure U02 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 11.00 20.00 (18.14) 11.00 30.00 (27.22) 9.88 70.00 (63.50) 6.38 Peak Pellet Exposure Most Limiting Gadolinia LHGRLimit 3 GWd/MT (GWd/ST) kW/ft 0.00 ( 0.00) 9.70 16.79 (15.23) 9.70 26.35 (23.90) 8.71 64.58 (58.59) 5.62 3

Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ( 6.0% Gd).

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