Text

Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2
	ML23076A291
Person / Time
Site:	Monticello
Issue date:	03/17/2023
From:	Hafen S; Northern States Power Company, Minnesota, Xcel Energy
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
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ML23076A290	List: L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2;
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	L-MT-23-012 NAD-MN-050NP, Rev 2
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2807 West County Road 75 Monticello, MN 55362 ENCLOSURE 3 CONTAINS PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.390(b)(4)

March 17, 2023 L-MT-23-012 TS 5.6.3.d ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2

References:

1) Monticello Nuclear Generating Plant, Submittal of Revision 1 of the Core Operating Limits Report for Cycle 31 (ADAMS Accession No. ML22011A219), dated January 11, 2022.

Pursuant to the requirements of Technical Specification 5.6.3.d, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter NSPM),

hereby submits Revision 2 of COLR for the Monticello Cycle 31.

Revision 1 of the Cycle 31 COLR was submitted per the above reference. The COLR for Cycle 31, Revision 2 is required to accommodate operating with 3 of 4 main steam lines in service. provides a revised non-proprietary version of the MNGP COLR for Cycle 31, (NAD-MN-050NP, Revision 2). The proprietary version of the COLR contains information of the type that Global Nuclear Fuels (GNF) maintains in confidence and withholds from public disclosure. Enclosure 2 provides an executed affidavit from GNF. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in 10 CFR 2.390, Public inspections, exemptions, requests for withholding, and 10 CFR 9.17, Agency records exempt from public disclosure. Enclosure 3 provides the revised proprietary version of the COLR for Cycle 31 (NAD-MN-050P, Revision 2).

If you have any questions about this submittal, please contact Nate Fedora, Senior Regulatory Engineer, at nathan.a.fedora@xcelenergy.com.

Document Control Desk Page 2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.

Digitally signed by Sean Sean Dornseif for Dornseif for Date: 2023.03.17 18:53:06 -05'00' Shawn C. Hafen Plant Manager, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (3) cc: Administrator, Region III, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC State of Minnesota

ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT CYCLE 31 NON-PROPRIETARY CORE OPERATING LIMITS REPORT REVISION 2 NAD-MN-050NP (40 pages follow)

Non-Proprietary NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Monticello Nuclear Generating Plant Cycle 31 Non-Proprietary Core Operating Limits Report Revision 2 NAD-MN-050NP Prepared By: Prepared per LDC 604000000913 Steven Winston Senior Engineer, Nuclear Analysis and Design Verif ied By: Verif ied per LDC 604000000913 Jody Helland Reactor Engineering Reviewed By: Reviewed per LDC 604000000913 Kevin Austin Reactor Engineering - Monticello Approved By: Approved per LDC 604000000913 Darius Ahrar Manager, Nuclear Analysis and Design Proprietary Information Notice This is a non-proprietary version of the Monticello Nuclear Generating Plant Cycle 31 COLR, NAD-MN-050, Revision 2, which has proprietary inf ormation removed. Portions of the document that have been removed are indicated by white space inside open and closed brackets as shown here (( )).

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 1 of 40

Table of Contents Section/Description Page #

1.0 CORE OPERATING LIMITS REPORT (COLR) ........................................................................4 2.0 REFERE NCES .......................................................................................................................4 3.0 ROD BLOCK MONITOR OPERABILITY REQUIREME NTS ......................................................6 4.0 ROD BLOCK MONITOR UPSCALE TRIP SETPOINT ..............................................................6 5.0 MINIMUM CRITICAL POWER RATIO (MCP R) ........................................................................7 5.1 TECH. SPEC. SCRAM SPEED (TSSS) ...........................................................................................7 5.1.1 TSSS OLMCPR for Two Recirculation Loop Operation ...........................................................................................7 5.2 NOMINAL SCRAM SPEED (NSS) ..................................................................................................7 5.2.1 NSS OLMCPR for Two Recirculation Loop Operation .............................................................................................7 5.3 TECHNICAL SPECIFICATION SCRAM TIME D EPENDENCE ..................................................................7 5.4 PRESSURE REGULATOR OUT OF SERVICE (PROOS) OPERATION ....................................................8 5.4.1 OLMCPR for Two Recirculation Loop Operation, WITHOUT A BACKUP PRESSURE REGULATOR....................9 5.5 OLMCPR FOR SINGLE RECIRCULATION LOOP OPERATION .............................................................9 6.0 POWER-FLOW MAP ..............................................................................................................9 7.0 APPROVE D ANALYTICAL METHODS ................................................................................. 10 8.0 FUEL ROD HEAT GE NERATION RATE ............................................................................... 11 8.1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) AS A FUNCTION OF EXPOSURE ..................................................................................................................................... 11 8.1.1 Single and Two-Recirculation Loop Operation (MAPLHGR)..................................................................................11 8.2 LINEAR HEAT GENERATION RATE (LHGR) .................................................................................. 12 8.2.1 Single and Two-Recirculation Loop Operation (LHGR) .........................................................................................12 8.3 PRESSURE REGULATOR OUT OF SERVICE (PROOS) OPERATION .................................................. 13 8.4 MAIN STEAM ISOLATION VALVE OUT OF SERVICE (MSIVOOS) OPERATION ..................................... 14 9.0 CORE STABILITY REQUI REMENTS .................................................................................... 18 9.1 STABILITY EO-III SOLUTION...................................................................................................... 18 9.2 ENHANCED OPTION III OP RM SETPOINTS .................................................................................. 18 9.3 EXTENDED FLOW WINDOW STABILITY - HIGH SCRAM................................................................... 18 9.4 BACKUP STABILITY PROTECTION REGIONS ................................................................................. 19 9.5 ACTIONS FOR ENTRY INTO SCRAM REGION ................................................................................ 19 9.6 ACTIONS FOR ENTRY INTO CONTROLLED ENTRY REGION.............................................................. 19 10.0 TURBINE BYPASS SYSTEM RESPONSE TIME ................................................................... 20 11.0 APRM SIMULATE D THE RMAL POWE R - HIGH, DELTA W ALLOWABLE VALUE ............... 20 NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 2 of 40

List of Tables Table/Description Page #

Table 1 NSS Scram Insertion Time to CRD Notch Position ....................................................................8 Table 2 MAPLHGR Limits, ATRIUM 10XM ......................................................................................... 15 Table 3 MAPLHGR Limits, GE14C EDB-4332 .................................................................................... 16 Table 4 ATRIUM 10XM Steady-State LHGR Limits ............................................................................. 17 Table 5 GE14 UO2/ Gd Thermal Mechanical LHGR Limits ................................................................... 17 Table 6 Licensed OPRM Amplitude Setpoint ...................................................................................... 18 Table 7 EFWS Nominal Setpoints f or the Scram Region...................................................................... 18 Table 8 BSP Endpoints for Normal Feedwater Temperature ................................................................ 19 List of Figures Figure/Description Page #

Figure 1 Power Dependent LHGR Multipliers ..................................................................................... 21 Figure 2 Flow Dependent LHGR Multipliers ....................................................................................... 22 Figure 3 Power Dependent MCPR(P) Limits for TSSS Insertion Rates ................................................ 23 Figure 4 Power Dependent MCPR(P) Limits for NSS - BOC to 11.9 GWd/MTU................................... 24 Figure 5 Power Dependent MCPR(P) Limits for NSS - BOC to Coastdown ......................................... 25 Figure 6 Flow Dependent MCPR(F) Limits......................................................................................... 26 Figure 7 Power/Flow Map ................................................................................................................. 27 Figure 8 Power Dependent MCPR(P) Limits for Pressure Regulator Out of Service (PROOS) .............. 28 Figure 9 Pressure Regulator Out Of Service Interim MFLCP R Limit ..................................................... 29 Figure 10 Power Dependent LHGR Multipliers f or Pressure Regulator Out of Service (PROOS ) .......... 30 Figure 11 Pressure Regulator Out of Service (PROOS ) Interim MFLPD Limit ...................................... 31 Figure 12 Power Dependent MCP R(P) Limits f or SLO with NSS/TSSS Ins ertion Rates ........................ 32 Figure 13 Power Dependent MAPLHGR Multipliers ............................................................................ 33 Figure 14 Flow Dependent MAPLHGR Multipliers .............................................................................. 34 Figure 15 Pressure Regulator Out Of Service (PROOS ) Power Dependent MAPLHGR Multipliers ........ 35 Figure 16 Pressure Regulator Out of Service (PROOS ) Interim MAPRA T Limits .................................. 36 Figure 17 MSIV Out-of -Service - Flow Dependent LHGR Multipliers ................................................... 36 Figure 18 MSIV Out-of -Service - Flow Dependent MCPR(F) Limits .................................................... 36 Figure 19 MSIV Out-of -Service (MSIVOOS) - Interim MFLPD Multipliers ............................................ 39 Figure 20 MSIV Out-of -Service (MSIVOOS) Interim MFLCP R Limits ................................................... 40 NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 3 of 40

1.0 Core Operating Limits Report (COLR)

This Core Operating Limits Report f or Monticello Nuclear Generating Plant (MNGP) Cycle 31 is prepared in accordance with the requirements of Technical Specif ication 5.6.3. The core operating limits are developed using NRC-approved methodology as listed in Section 7 of this COLR and are established such that all applicable thermal limits of the plant saf ety analysis are met.

Note that AREVA has changed its name to Framatome.

A 0.03 penalty has been applied to the SLMCPR when the ratio of core power to core f low is 42 MWt / Mlbm/hr in the EFW region. This penalty has been incorporated into the OLMCPR. The 0.03 penalty is not applied when MNGP is operating in the Maximum Extended Load Line Limit (MELLLA) region or operating in the EFW region where the ratio of core power to core f low is <

42 MWt / Mlbm/hr. The OLMCPRs in Section 5 of this COLR were selected to ensure that the MCPR SLs of Tech Spec SL 2.1 are not violated. Note that Single Loop Operation is not permitted in the EFW region.

This report includes the Enhanced Option III (EO-III) long term stability solution, which is required to operate in the Extended Flow Window (EFW) (aka, MELLLA+) region of the Power-f low map.

This report includes using COTRANSA2 (Ref erence 6.0), XCOBRA (Ref erence 7.0), XCOBRA-T (Ref erence 8.0) and CASMO-4/MICROBURN-B2 (Ref erence 9.0) as described in the AREVA THERMEX methodology report (Ref erence 7.0) and neutronics methodology report (Ref erence 10.0).

Revision 2 is being issued to account f or site conditions with 1 MSIV Out of Service with power levels < 75% of rated (Ref erence 15).

2.0 References 1.0 ANP-3912P, Revision 1, Monticello Reload Saf ety Analysis Report f or Cycle 31, March 2021.

2.0 NEDC-32868P, Revision 5, GE14 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR II), MFN 13-028, May 2013.

3.0 ANP-10262PA, Revision 0, Enhanced Option Ill Long Term Stability Solution, May 2008.

4.0 Calculation CA-08-051, Rev 0, Instrument Setpoint Calculation - Rod Block Monitor (RBM)

PRNM Setpoints f or CLTP and EPU Operation.

5.0 Letter f rom D. Musolf (NSP) to Director, Of f ice of Nuclear Reactor Regulation, NRC Revision 1 to License Amendment Request Dated September 7, 1976, Single Loop Operation dated July 2, 1982.

6.0 ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program f or Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.

7.0 XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology f or Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 4 of 40

8.0 XN-NF-84-105(P )(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code f or BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.

9.0 EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology f or Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.

10.0 XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology f or Boiling Water Reactors - Neutronic Methods f or Design and Analysis, Exxon Nuclear Company, March 1983.

11.0 GHNE-0000-0073-4167-R2, Reactor Long-Term Stability Solution Option III: Licensing Basis Hot Channel Oscillation Magnitude f or Monticello Nuclear Generating Plant, December 2007.

12.0 Calculation 14-049, Revision 2, Instrument Setpoint Calculation, Average Power Range Monitor NUMAC PRNM Setpoints - Extended Flow Window Stability, (EC 601000000063),

September 21, 2018.

13.0 ANP-3295P, Revision 3, Monticello Licensing Analysis For EFW (EPU/MELLLA+),

February 2016.

14.0 002N3952-R1, Revision 1, Supplemental Reload Licensing Report f or Monticello Reload 27 Cycle 28, April 2015.

15.0 FS1-0066804 Revision 1, Support f or Monticello Cycle 31 Operation with 1 MSIVOOS, March 2023 NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 5 of 40

3.0 Rod Block Monitor Operability Requirements The Rod Withdrawal Error (RWE) analysis (Ref erence 1.0) validated that the f ollowing MCPR values provide the required margin f or f ull withdrawal of any control rod during Monticello Cycle 31:

Note that the RBM is not credited below 30% power as identif ied below in Section 4.0.

For Power 30% and < 90%: MCPR 1.86 (f or TLO)

For Power 30% and < 90%: MCPR 1.91 (f or SLO)

For Power 90%: MCPR 1.57 (f or TLO)

When the core power is greater than or equal to 30% and less than 90% of rated in two -loop operation and the MCPR is less than 1.86, then a limiting control rod pattern exists and the Rod Block Monitor is required to be operable.

When the core power is greater than or equal to 30% and less than 90% of rated in single loop operation and the MCPR is less than 1.91, then a limiting control rod pattern exists and the Rod Block Monitor is required to be operable.

When the core power is greater than or equal to 90% and the MCPR is less than 1.57, then a limiting control rod pattern exists and the Rod Block Monitor is required to be operable.

Ref erence: Technical Specif ication Table 3.3.2.1-1 Function 1.

4.0 Rod Block Monitor Upscale Trip Setpoint Technical Specification Trip Setpoints and Allowable Values Function Trip Setpoint Allowable Values Low Power Range - Upscale (a) 121.2/125 of f ull scale 121.6/125 of f ull scale Intermediate Power Range - Upscale (b) 116.2/125 of f ull scale 116.6/125 of f ull scale High Power Range - Upscale (c), (d) 111.2/125 of f ull scale 111.6/125 of f ull scale Applicable Thermal Power (a) Thermal Power 30% and < 65% RTP and MCPR is below the limit specif ied in Section 3.0.

(b) Thermal Power 65% and < 85% RTP and MCPR is below the limit specif ied in Section 3.0.

(c) Thermal Power 85% and < 90% RTP and MCPR is below the limit specif ied in Section 3.0.

(d) Thermal Power 90% RTP and MCPR is below the limit specif ied in Section 3.0.

Ref erence: Technical Specif ication Table 3.3.2.1-1 Functions 1.a, 1.b, and 1.c.

The Ref erence f or the Trip Setpoints and Allowable Values is Ref erence 4.0.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 6 of 40

5.0 Minimum Critical Power Ratio (MCPR)

The cycle specif ic MCPR limits protect the MCPR95%/95% limit of 1.05 which is a generic value based on the ATRIUM 10XM f uel type and the ACE MCPR correlation.

The cycle specif ic MCPR limits presented in Figures 3-6, 8, 9 and 12 are based on TLO and SLO MCPR99.9% values of 1.08 and 1.13 which meets the requirement in Technical Specif ication.

2.1.1.3 5.1 Tech. Spec. Scram Speed (TSSS)

The Operating Limit Minimum Critical Power Ratio (OLMCPR) f or TSSS does not account f or scram speeds that are f aster than those required by Technical Specif ications.

5.1.1 TSSS OLMCPR for Two Recirculation Loop Operation The TSSS OLMCPR shall be determined f o r two recirculation loop operation (TLO) as f ollows, where core thermal power is denoted by (P):

For 25% (P) 100%:

1. the TSSS OLMCPR is the greater of {MCPR(P) f rom Figure 3} or {MCPR(F) f rom Figure 6}

Ref erence: Technical Specif ication Section 3.2.2.

5.2 Nominal Scram Speed (NSS)

The OLMCPR f or NSS does take into account the measured scram speeds that are f aster than the Technical Specif ication requirements, thus reducing the potential consequences of a limiting transient.

5.2.1 NSS OLMCPR for Two Recirculation Loop Operation The NSS OLMCPR shall be determined f or two recirculation loop operation as f ollows:

For 25% (P) 100%:

1. If cycle exposure 11900 MWd/MTU, the NSS OLMCPR is the greater of {MCPR(P) f rom Figure 4} or {MCPR(F) f rom Figure 6}

2. If cycle exposure > 11900 MWd/MTU, the NSS OLMCPR is the greater of {MCPR(P) f rom Figure 5} or {MCPR(F) f rom Figure 6}

Ref erence: Technical Specif ication Section 3.2.2.

5.3 Technical Specification Scram Time Dependence Technical Specif ication 3.1.4 and Table 3.1.4-1 provide the scram insertion time versus po sition requirements f or continued operations. Technical Specif ication Surveillance Requirements SR 3.1.4.1 - SR 3.1.4.4 provide the surveillance requirements f or the CRDs. Data f rom testing of the CRDs, or f rom an unplanned scram, is summarized in Surveillance Test 0081.

Using this cycle specif ic inf ormation, values of Pave can be calculated in accordance with the equation below f or each notch position (P = 46, 36, 26, and 06).

The Equation (1) used to calculate the average of the current scram times f or the cycle is:

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 7 of 40

N P

i P

ave = i =1 (1)

N where:

P i = the scram time to notch position P f or control rod i f rom its most recent surveillance test; N= The number of operable control rods (N < 121).

P= The notch position (P = 46, 36, 26, and 06)

N sum of the most recent scram times f or all operable control rods (N) i =1 P

i= measured to notch position P to comply with the Technical Specif ication surveillance requirements SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, SR 3.1.4.4.

The average scram time f or notch position (P), Pave is tested against the Nominal Scram Speed f or that notch position (NSS P) using the f ollowing equation:

P ave NSS P (2) where:

NSS P is the Nominal Scram Speed f or the specif ied CRD Notch Position (P) f rom Table 1 NSS Scram Insertion Time to CRD Notch Position Table 1 NSS Scram Insertion Time to CRD Notch Position Notch Position (P) NSS P (sec) 46 0.304 36 0.820 26 1.355 06 2.477 If the average scram time satisf ies the Equation 2 criteria f or each notch position, continued plant operation under the NSS operating limit minimum critical power ratio (OLMCPR) f or pressurizat ion events is permitted. If the average scram time f ails the Equation 2 criteria f or any notch position, the TSSS OLMCPR must be used f or pressurization events .

No interpolation between NSS and TSSS operating limits is allowed.

5.4 Pressure Regulator Out of Service (PROOS) Operation This section provides power dependent MCPR limits when a backup pressure regulator is not operational (also called PROOS).

A Pressure Regulator Failure Down-Scale (PRFDS) event without backup pressure regulator was evaluated f or Monticello (Ref erence 1.0). This event resulted in a more restrictive Power NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 8 of 40

Dependent MCPR limit than required f or normal reduced power operation with both pressure regulators operational. The of f -rated power dependent limits have been generated f or Cycle 31 (Ref erence 1.0). Figure 8 provides the required more restrictive power dependent MCPR limits.

The Pressure Regulator Out of Service limits are applicable f or Cycle 31 (Ref erence 1.0).

Figure 8 shows the more restrictive limits determined in Ref erence 1.0 f or PROOS operation.

Figure 8 should only be used f or operation without a backup pressure regulator. Figure 8 is valid f or both TSSS and NSS OLMCPR limits f rom BOC through Coastdown.

An interim MFLCPR Limit is provided in Figure 9. This limit should only be used if the Gardel thermal limit input has not been modif ied as described in Section 5.4.1 to account f or pressure regulator out of service operation. That is, only Figure 8 or Figure 9 should be used to provide the appropriate PROOS limit. These f igures should not be utilized in combination.

5.4.1 OLMCPR for Two Recirculation Loop Operation, WITHOUT A BACKUP PRESSURE REGULATOR.

The PROOS TSSS OLMCPR and NSS OLMCPR shall be determined f or two recirculation loop operation as f ollows:

For 25% (P) 100%:

1. the OLMCPR is the greater of {MCPR(P) f rom Figure 8} or {MCPR(F) f rom Figure 6}

5.5 OLMCPR for Single Recirculation Loop Operation For single recirculation loop operation, there are not separate TSSS, NSS and PROOS OLMCPRs. The OLMCPR is bounded in all three conditions by the same limit. It shall be determined as f ollows:

1. the OLMCPR is the greater of {MCPR(P) f rom Figure 12} or {MCPR(F) f rom Figure 6}

Ref erence: Technical Specif ication Section 3.2.2.

6.0 Power-Flow Map The Power-Flow Operating Map based on analysis to support Cycle 31 is shown in Figure 7. The Power-Flow Operating Map is consistent with a rated power of 2004 MWt as described in Ref erence 13.0. The Backup Stability Protection (BSP) lines are described in Section 9.0 of this report.

Region I in Figure 7 is the Scram Region and Region II is the Controlled Entry Region. These two regions are applicable when the OPRM Upscale Trip is INOPERABLE NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 9 of 40

7.0 Approved Analytical Methods NEDE-24011-P-A Rev. 20 General Electric Standard Application f or Reactor Fuel (GESTAR)

NEDE-24011-P-A-US Rev. 20 General Electric Standard Application f or Reactor Fuel (GESTAR) - Supplement f or the United States.

NEDO-31960-A, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology, with Supplement 1, dated November 1995 NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications, August 1996 Engineering Evaluation EC 25987, Calculation Framework f or the Extended Flow Window Stability (EFWS) Setpoints, as docketed in Xcel Energy letter to NRC L-MT-15-065, dated September 29, 2015 XN-NF-81-58(P)(A) Rev. 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, March 1984 EMF-85-74(P) Rev. 0 Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR)

Fuel Rod Thermal-Mechanical Evaluation Model, February 1998 ANF-89-98(P)(A) Rev. 1 and Supplement 1, Generic Mechanical Design Criteria f or BWR Fuel Designs, May 1995 XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology f or Boiling Water Reactors - Neutronic Methods f or Design and Analysis, March 1983 XN-NF-80-19(P)(A) Volume 4 Rev. 1, Exxon Nuclear Methodology for Boiling Water Reactors:

Application of the ENC Methodology to BWR Reloads, June 1986 EMF-2158(P)(A) Rev. 0 Siemens Power Corporation Methodology f or Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, October 1999.

XN-NF-80-19(P)(A) Volume 3 Rev. 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, January 1987 XN-NF-84-105(P )(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code f or BWR Transient Thermal-Hydraulic Core Analysis, February 1987 ANF-913(P)(A) Volume 1 Rev. 1 and Volume 1 Supplements 2, 3, and 4, COTRANSA2: A Computer Program f or Boiling Water Reactor Transient Analyses, August 1990 EMF-2209(P)(A) Rev. 3 SPCB Critical Power Correlation, September 2009 EMF-2245(P)(A) Rev. 0 Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, August 2000 EMF-2361(P)(A) Rev. 0 EXEM BWR-2000 ECCS Evaluation Model, May 2001 EMF-2292(P)(A) Rev. 0 ATRIUM'-10: Appendix K Spray Heat Transf er Coef f icients, September 2000 EMF-CC-074(P)(A) Volume 4 Rev. 0, BWR Stability Analysis: Assessment of STAIF with Input f rom MICROBURN-B2, August 2000 BAW-10247PA Rev. 0 Realistic Thermal-Mechanical Fuel Rod Methodology f or Boiling Water Reactors, February 2008 ANP-10298PA Rev. 1 ACE/ATRIUM 10XM Critical Power Correlation, March 2014 ANP-10307PA Rev. 0 AREVA MCPR Saf ety Limit Methodology f or Boiling Water Reactors, June 2011 BAW-10255PA Rev. 2 Cycle-Specif ic DIVOM Methodology Using the RAMONA5-FA Code, May 2008 ANP-10262PA Rev. 0 Enhanced Option III Long Term Stability Solution, May 2008 NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 10 of 40

8.0 Fuel Rod Heat Generation Rate 8.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) as a Function of Exposure The MAPLHGR limits in Table 2 through Table 3 are conservative values bounding all f uel lattice types (all GE14 natural uranium lattices are excluded) in a given f uel bundle design and are intended only f or use to determine bounding thermal limits as described below to establish MAPLHGR limits f or Technical Specif ication 3.2.1. No channel bow ef f ects are included in the bounding MAPLHGR values in these tables as there are no reused channels.

MAPLHGR limits f or the ATRIUM 10XM f uel and f or each individual GE14 f uel lattice f or a given bundle design as a f unction of axial location and average planar exposure are determined based on the approved methodology ref erenced in Monticello Technical Specif ication 5.6.3.b and are loaded into the process computer f or use in core monitoring calculations.

To determine bounding MAPLHGR limits:

8.1.1 Single and Two-Recirculation Loop Operation (MAPLHGR)

At rated core thermal power and core f low conditions, the MAPLHGR value f or each f uel bundle design as a f unction of average planar exposure shall not exceed the bounding limits provided in Table 2 through Table 3.

The MAPLHGR limit f or single (SLO) and two recirculation loop (TLO) operation are determined as f ollows:

1. For ATRIUM 10XM:

a. For TLO, the MAPLHGR limits are listed in Table 2.

b. For SLO, multiply the MAPLHGR limit in Table 2 by 0.70.

2. For GE14C:

a. For TLO, the MAPLHGR limits are listed in Table 3. To calculate MAPLHGR ,

calculate the minimum of :

i. MAPLHGR(P) = MAPFAC(P)

MAPLHGR limit where MAPFAC(P) is taken f rom Figure 13 ii. MAPLHGR(F) = MAPFAC(F)

MAPLHGR limit where MAPFAC(F) is taken f rom Figure 14

b. For SLO calculate the minimum of :

i. The calculation above in Section 8.1.1. 2(a)

OR ii. The result when multiplying the MAPLHGR limit in Table 3 by 0.83.

Straight line interpolation between nearest data points is permitted only within each individual Table f rom Table 2 through Table 3.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 11 of 40

8.2 Linear Heat Generation Rate (LHGR)

For ATRIUM 10XM f uel, the LHGR limits provided in Table 4 are applicable to all ATRIUM 10XM f uel in Cycle 31. The LHGR limits are provided as a f unction of f uel rod peak pellet exposure.

The LHGR limits are f uel rod nodal limits and are to be applied at every node of the f uel rod including the natural uranium lattices. There are no separate single loop operation specif ic multipliers applicable to LHGR, as such TLO and SLO limits are the same.

For GE14 f uel, the uranium dioxide (UO 2) and gadolinia LHGR limits provided in Table 5 are applicable to all GE14 f uel lattice types in Cycle 31. The uranium dioxide (UO2) and gadolinia LHGR limits are provided as a f unction of f uel rod peak pellet exposure. The gadolinia LHGR limits in Table 5 are conservative values which bound the gadolinia LHGR limits f or all the gadolinia concentrations occurring in each of the bundle types used in Cycle 31. The LHGR limits are f uel rod nodal limits and are to be applied at every node of the f uel rod including the natural uranium lattices.

The individual LHGR limits f or the uranium dioxide and gadolinia f uel rods in each f uel bundle type used in Cycle 31, as a f unction of axial location and pellet exposure are determined based on the approved methodology ref erenced in Monticello Technical Specif ication 5.6.3.b and are loaded into the process computer f or use in core monitoring calculations.

The LHGR limits are presented in this report f or use to determine bounding thermal limits to demonstrate compliance with Technical Specif ication 3.2.3.

To determine bounding LHGR limits:

8.2.1 Single and Two-Recirculation Loop Operation (LHGR)

At rated core thermal power and core f low conditions, the LHGR limit f or each f uel bundle design as a f unction of peak pellet exposure and f uel pin type shall not exceed the bounding limits provided in Table 4 and Table 5.

LHGR limits are adjusted f or of f-rated core thermal power and core f low conditions as f ollows:

1. For ATRIUM 10XM calculate the minimum of :

a. LHGR(P) = LHGRFAC(P)

LHGR limit f rom Table 4 where LHGRFAC(P) comes f rom Figure 1.

OR

b. LHGR(F) = LHGRFAC(F)

LHGR limit f rom Table 4 where LHGRFAC(F) comes f rom Figure 2.

2. For GE14C calculate the minimum of :

a. LHGR(P) = LHGRFAC(P)

LHGR limit f rom Table 5 where LHGRFAC(P) comes f rom Figure 1.

OR

b. LHGR(F) = LHGRFAC(F)

LHGR limit f rom Table 5 where LHGRFAC(F) comes f rom Figure 2.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 12 of 40

8.3 Pressure Regulator Out of Service (PROOS) Operation This section provides power dependent MAPLHGR and LHGR limits when a backup pressure regulator is not operational (also called PROOS).

The Pressure Regulator Failure Down-Scale (PRFDS) event without backup pressure regulator evaluated f or Monticello in Ref erence 1.0 resulted in more restrictive power dependent LHGR limits than required f or normal reduced power operation with both pressure regulators operational. When this event was evaluated f or Cycle 31 (Ref erence 1.0), the results showed f or ATRIUM 10XM, the MAPLHGR limits are unchanged f rom Section 8.1 and the LHGR limits are unchanged f rom Section 8.2. The MAPLHGR and LHGR limits with PROOS are more limiting than the base case f or GE14C.

The MAPLHGR and LHGR limits f or GE14C are adjusted f or of f-rated core thermal power and core f low conditions by determining the f ollowing:

1. For GE14C:

a. MAPLHGR limit is calculated as the minimum of :

i. MAPLHGR(P) = MAPFAC(P)

MAPLHGR limit f rom Table 3 where MAPFAC(P) comes f rom Figure 15.

OR ii. MAPLHGR(F) = MAPFAC(F)

MAPLHGR limit f rom Table 3 where MAPFAC(F) comes f rom Figure 14.

b. LHGR limit is calculated as the minimum o f :

i. LHGR(P) = LHGRFAC(P)

LHGR limit f rom Table 5 where LHGRFAC(P) comes f rom Figure 10.

OR ii. LHGR(F) = LHGRFAC(F)

LHGR limit f rom Table 5 where LHGRFAC(F) comes f rom Figure 2.

Figure 10 shows the more restrictive limits determined in Ref erence 1.0 f or PROOS operation.

Figure 10 should only be used f or operation without a backup pressure regulator.

Interim MFLPD Limits are provided in Figure 11 to address the more restrictive LHGR Limits identif ied in the Ref erence 1.0 analysis. These limits should only be used if the Gardel thermal limit input has not been modif ied to account f or PROOS operation. That is, only Figure 10 or Figure 11 should be used to provide the appropriate PROOS LHGR limit. Figure 10 should not be utilized in combination with Figure 11.

Interim MAPRAT Limits are provided in Figure 16 to address the more restrictive MAPLHGR Limits identif ied in the Ref erence 14.0 analysis. These limits should only be used if the Gardel thermal limit input has not been modif ied to account f or PROOS operation. That is, only Figure 15 or Figure 16 should be used to provide the appropriate PROOS MAPLHGR limit. Figure 15 should not be utilized in combination with Figure 16.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 13 of 40

8.4 Main Steam Isolation Valve Out of Service (MSIVOOS) Operation This section provides f low dependent MCPR and LHGR limits when a main steam isolation valve is Out of Service ( MSIVOOS), and is ONLY applicable at power levels equal to or below 75%

power.

The Main Steam Isolation Valve event was evaluated f or Monticello Cycle 31 in Ref erence 15.0.

When this event was evaluated, the results showed that the power dependent MCPR limits are unchanged f rom Section 5, the power dependent LHGR limits are unchanged f rom Section 8.2, and the MAPLHGR limits are unchanged f rom Section 8.1. The MCPR and LHGR f low dependent limits with MSIVOOS are more limiting than the base case.

The MCPR and LHGR limits are adjusted f or of f-rated core thermal power and core f low conditions by determining the f ollowing:

1. For GE14C:

1. The OLMCPR is the greater of {MCPR(P) f rom Figure 3 or Figure 5 as applicable to scram speed} or {MCPR(F) f rom Figure 18}

2. The LHGR limit is calculated as the minimum of :

i. LHGR(P) = Limits remain unchanged f rom normal operation.

OR ii. LHGR(F) = LHGRFAC(F)

LHGR limit f rom Table 5 where LHGRFAC(F) comes f rom Figure 17

2. For ATRIUM 10XM:

1. The OLMCPR is the greater of {MCPR(P) f rom Figure 3 or Figure 5 as applicable to scram speed} or {MCPR(F) f rom Figure 18}.

2. The LHGR limit is calculated as the minimum of :

i. LHGR(P) = Limits remain unchanged f rom normal operation.

OR ii. LHGR(F) = LHGRFAC(F)

LHGR limit f rom Table 4 where LHGRFAC(F) comes f rom Figure 17 Interim MFLPD Limits are provided in Figure 19 to address the more restrictive LHGRFACf multipliers identif ied in the Ref erence 15.0 analysis. These limits should only be used if the Gardel thermal limit input has not been modif ied to account f or MSIVOOS operation. Only Figure 17 or Figure 19 should be used to provide the appropriate MSIVOOS LHGR limit. Figure 17 should not be utilized in combination with Figure 19.

Interim MFLCPR Limits are provided in Figure 20 to address the more restrictive MCPRf Limits identif ied in the Ref erence 15.0 analysis. These limits should only be used if the Gardel thermal limit input has not been modif ied to account f or MSIVOOS operation. Only Figure 18 or Figure 20 should be used to provide the appropriate MSIVOOS OLMCPR limit. Figure 18 should not be utilized in combination with Figure 20.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 14 of 40

Table 2 MAPLHGR Limits, ATRIUM 10XM Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft)(1)(2) 0.00 ( 0.00) 12.5 20.00 (18.14) 12.5 67.00 (60.78) 7.6 Notes:

(1) Applicable multipliers per Section 8.1 will be applied to the data in this table f or two recirculation loop and single recirculation loop operations.

(2) MAPLHGR Data, Ref erence 1.0.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 15 of 40

Table 3 MAPLHGR Limits, GE14C EDB-4332 (2)

GE14-P10DNAB374-16GZ-100T-145-T6-4332 Average Planar Exposure MAPLHGR Limit GWD/MTU (GWD/STU) (kW/ft)(1)(3) 0.00 (0.00) 8.19 0.22 (0.20) 8.23 1.10 (1.00) 8.31 2.20 (2.00) 8.42 3.31 (3.00) 8.54 4.41 (4.00) 8.66 5.51 (5.00) 8.79 6.61 (6.00) 8.92 7.72 (7.00) 9.06 8.82 (8.00) 9.21 9.92 (9.00) 9.35 11.02 (10.00) 9.50 12.13 (11.00) 9.59 13.23 (12.00) 9.37 14.33 (13.00) 9.26 15.43 (14.00) 9.28 16.53 (15.00) 9.28 17.64 (16.00) 9.28 18.74 (17.00) 9.26 19.84 (18.00) 9.23 20.94 (19.00) 9.19 22.05 (20.00) 9.15 23.15 (21.00) 9.11 24.25 (22.00) 9.07 26.46 (24.00) 9.00 27.56 (25.00) 8.96 33.07 (30.00) 8.81 38.58 (35.00) 8.57 38.85 (35.24) 8.55 44.09 (40.00) 8.11 49.60 (45.00) 7.57 55.12 (50.00) 6.58 55.50 (50.35) 6.47 60.63 (55.00) 5.03 61.91 (56.16) 4.64 62.57 (56.76) 4.64 63.37 (57.49) 4.64 63.50 (57.60) 4.64 Notes:

(1) Applicable multipliers per Section 8.1 will be applied to the data in this table f or two recirculation loop and single recirculation loop operations.

(2) Engineering Data Bank (EDB) number, Ref erence 14.0.

(3) MAPLHGR Data, Ref erence 14.0.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 16 of 40

Table 4 ATRIUM 10XM Steady-State LHGR Limits Peak Pellet Exposure LHGR Limit (a)(b)(c)

GWD/MTU (GWD/STU) (kW/ft) 0.0 (0.0) 14.1 18.9 (17.15) 14.1 74.4 (67.49) 7.4 Notes:

(a) Applicable multipliers per Section 8.2 will be applied to the data in this table f or two recirculation loop and single recirculation loop operations.

(b) LHGR Data is f rom Ref erence 1.0.

(c) Extrapolation beyond the exposure in this table is allowed as long as the peak pin exposure does not exceed the licensing limit of 62.0 GWD/MTU.

Table 5 GE14 UO2/Gd Thermal Mechanical LHGR Limits Most Limiting Gadolinia Peak Pellet Exposure UO2 LHGR Limit (a)(b)(c) Peak Pellet Exposure LHGR Limit (a)(b)(c)

GWD/MTU (GWD/STU) (kW/ft) GWD/MTU (GWD/STU) (kW/ft)

((

))

Notes:

(a) Applicable multipliers per Section 8.2 will be applied to the data in this table f or two recirculation loop and single recirculation loop operations.

(b) These bounding Thermal Mechanical LHGR Limits may be used with all GE14 f uel loaded in Cycle 31.

(c) Tables D-2 and D-4 in Ref erence 2.0.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 17 of 40

9.0 Core Stability Requirements 9.1 Stability EO-III Solution Monticello has implemented the AREVA Enhanced Option III (EO-III) Long Term Stability solution using the Oscillation Power Range Monitor (OPRM) as described in Ref erence 3.0. Plant-specific Hot Channel Oscillation Magnitude (HCOM) (Ref erence 11.0) and other cycle specif ic stability parameters are used in the Cycle 31 EO-III Stability Evaluation, which is documented in Ref erence 1.0. A Backup Stability Protection (BSP) evaluation is also documented in Ref erence 1.0.

Ref erence: Technical Specif ication 3.3.1.1 9.2 Enhanced Option III OPRM Setpoints A reload Enhanced Option Ill evaluation has been perf ormed in accordance with the licensing methodology described in Ref erence 3.0.

The OPRM setpoints f or Two Loo p Operation (TLO) are conservative relative to Single Loop Operation (SLO) and are, theref ore, bounding. The OPRM Period Based Detection Algorithm (PBDA) instrumentation setpoints f or use in Technical Specif ication LCO 3.3.1.1 Table 3.3.1.1-1 Function 2f shall not exceed the f ollowing:

Table 6 Licensed OPRM Amplitude Setpoint Confirmation Count OPRM Amplitude Setpoint Setpoint 13 1.10 Ref erence: Technical Specif ication 3.3.1.1 9.3 Extended Flow Window Stability - High Scram Ref erence 3.0 describes the single channel instability exclusion and backup stability protection provided by the Extended Flow Window Stability (EFWS) scram. The EFWS APRM setpoints f rom Ref erence 12.0 are conf irmed f or Cycle 31 and def ined in Table 7.

Table 7 EFWS Nominal Setpoints for the Scram Region Parameter Allowable Value NTSP Slope of EFWS APRM f low-2.49 2.49 biased trip linear segment.

Constant Power Line f or Trip f rom zero Drive Flow to Flow 40.6 % RTP* 38.6 % RTP*

Breakpoint value.

Constant Flow Line f or Trip. 48.7 % RDF** 49.7 % RDF**

Flow Breakpoint value 30.3 % RDF** 31.3 % RDF**

Notes:

RTP - Rated Thermal Power

- RDF - Recirculation Drive Flow Ref erence: Technical Specif ication 3.3.1.1 NAD-MN-050NP, Monticello Cycle 31 COLR, Revision Page 18 of 40 2

9.4 Backup Stability Protection Regions The Backup Stability Protection (BSP) regions are shown in Figure 7. The BSP regions are an integral part of the Tech Spec-required alternative method to detect and suppress thermal hydraulic instability oscillations in that they identif y areas of the power/f low map where there is an increased probability that the reactor core could experience a thermal hydraulic instability.

Regions are identif ied that are either excluded f rom planned entry and continued operation (Scram Region), or where planned entry is not permitted unless specif ic operating restrictions are met and specif ic actions are required to be taken to immediately leave the region f ollowing inadvertent or f orced entry (Controlled Entry Region). The boundaries of these regions are established on a cycle-specif ic basis based upon core decay ratio calculations perf ormed using NRC-approved methodology (Ref erence 1.0).

The BSP regions are only applicable when the Upscale Trip f unction of the OPRM is inoperable.

However, immediate action is required to leave Region I even if the OPRMs are operable. The BSP region boundaries were calculated f or Monticello Cycle 31 f or nominal f eedwater temperature conditions. The endpoints of the regions are def ined in Table 8. The region boundaries shown in Figure 7 are def ined using the Generic Shape Function (GSF), which is described in Ref erence 3.0.

Table 8 BSP Endpoints for Normal Feedwater Temperature Endpoint Power (%) Flow (%) Definition Scram Region Boundary, A1 56.5 40.0 HFCL Scram Region Boundary, B1 42.5 33.7 NCL Controlled Entry Region A2 64.4 50.0 Boundary, HFCL Controlled Entry Region B2 28.5 31.2 Boundary, NCL Ref erence: Technical Specif ication 3.3.1.1 9.5 Actions For Entry Into Scram Region Immediate manual scram upon determination that the region has been entered. If entry is unavoidable, early scram initiation is appropriate.

Ref erence: Technical Specif ication 3.3.1.1 9.6 Actions For Entry Into Controlled Entry Region If entry is inadvertent or f orced, immediate exit f rom region is required. The region can be exited by control rod insertion or core f low increase. Increasing the core f low by restarting an idle recirculation pump is not an acceptable method of exiting the region.

Deliberate entry into the Controlled Entry Region requires compliance with at least one of the stability controls outlined below:

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 19 of 40

1. Maintain core average boiling boundary (BB) > 4.0 f eet.

2. Maintain core decay ratio (DR) < 0.6 as calculated by an on-line stability monitor.

3. Continuous dedicated monitoring of real time control room neutron monitoring instrumentation with manual scram required upon indication of a reactor instability induced power oscillation.

Caution is required whenever operating near the Controlled Entry Region boundary (i.e.,

within approximately 10% of core power or core f low), and it is recommended that the amount of time spent operating near this region be minimized.

Ref erence: Technical Specif ication 3.3.1.1 10.0 Turbine Bypass System Response Time The TURBINE BYPASS SYSTEM RESPONSE TIME shall be that time interval f rom when the main turbine trip solenoid is activated until 80% of the turbine bypass capacity is established.

The TURBINE BYPASS SYSTEM RESPONSE TIME shall be 1.1 seconds.

Ref erence: Technical Specif ication 1.1, Surveillance Requirement 3.7.7.3.

11.0 APRM Simulated Thermal Power - High, Delta W Allowable Value The APRM Simulated Thermal Power - High Flow Biased Scram Setpoint Allowable Value shall be:

For Two Loop Operation (TLO):

SSTP (0.61(W) + 67.2%RTP) and 116%RTP where:

SSTP = Scram setting in percent of rated thermal power (2004 MWt)

W= Loop recirculation f low rate in percent of rated For Single Loop Operation (SLO):

SSTP (0.55(W-W) + 61.5%RTP) where:

SSTP = Scram setting in percent of rated thermal power (2004 MWt)

W= Loop recirculation f low rate in percent of rated W = Dif ference between two-loop and single-loop effective recirculation flow at the same core f low (W = 5.4% f or single loop operation, W = 0.0 f or two -loop operation)

Ref erence: Technical Specif ication 5.6.3, item 5, Technical Specif ication Table 3.3.1.1-1, Function 2.b, f ootnote (b), and Ref erence 5.0 NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 20 of 40

Figure 1 Power Dependent LHGR Multipliers 1.10 1.00 0.90 ATRIUM 10XM 0.80 LHGRFAC(P) 0.70 Flow 50% ATRIUM 10XM GE14 0.60 Flow > 50%

ATRIUM 10XM 0.50 Flow 50% GE14 0.40 0.30 Flow > 50% GE14 0.20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

LHGRFACP = A + B*P Flow Type Power A B F 50 A10XM 25 P 40 0.2067 0.00933 F > 50 A10XM 25 P 40 0.0600 0.01200 All A10XM 40 50 GE14 25 P 40 0.2232 0.00467 All GE14 40 < P 100 0.3100 0.00650 P = Percent of Rated Core Power F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 21 of 40

Figure 2 Flow Dependent LHGR Multipliers 1.10 LHGR FLOW FACTOR - LHGRFAC(F) 1.00 GE14 0.90 0.80 ATRIUM 10XM 0.70 0.60 0.50 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

LHGRFACF = A + B*F Flow Type Power A B 30 F 34.2 A10XM All 0.2844 0.00952 34.2 < F 82.6 A10XM All 0.3343 0.00806 82.6 < F 107 A10XM All 1.0000 0.00000 30 F 34.2 A11 All 0.5343 0.00000 34.2 < F 57.26 A11 All 0.0729 0.01349 57.26 < F 78.65 A11 All 0.4560 0.00680 78.65 < F 99 A11 All 0.9908 0.00000 99 < F 107 A11 All 1.0000 0.00000 F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

In addition to the f low dependent multipliers, Monticello also requires an ECCS MAPLHGR multiplier of 0.9908 f or operation at or below 99% core f low f or GE14 f uel. This multiplier ensures that the of f -rated limits assumed in the EPU ECCS-LOCA analyses bound the cycle-specif ic off-rated limits calculated f or EFW operation.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 22 of 40

Figure 3 Power Dependent MCPR(P) Limits for TSSS Insertion Rates MCPRP = A + B*P Flow Type Power A B F 50 A10XM 25 P 40 4.2268 -0.05067 F > 50 A10XM 25 P 40 4.8933 -0.05733 All A10XM 40 50 GE14 25 P 40 4.7900 -0.05400 All GE14 40 < P 60 2.2000 -0.00900 All GE14 60 < P 80 1.6900 -0.00050 All GE14 80 < P 100 1.9300 -0.00350 P = Percent of Rated Core Power F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 23 of 40

Figure 4 Power Dependent MCPR(P) Limits for NSS - BOC to 11.9 GWd/MTU 3.60 Flow > 50%

ATRIUM 10XM 3.40 3.20 3.00 Flow > 50% GE14 2.80 MCPR(P) 2.60 Flow 50% GE14 2.40 Flow 50%

2.20 ATRIUM 10XM 2.00 GE14 1.80 1.60 ATRIUM 10XM 1.40 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

MCPRP = A + B*P Flow Type Power A B F 50 A10XM 25 P 40 4.2268 -0.05067 F > 50 A10XM 25 P 40 4.8933 -0.05733 All A10XM 40 50 GE14 25 P 40 4.7900 -0.05400 All GE14 40 < P 60 2.1000 -0.00750 All GE14 60 < P 80 1.6500 0.00000 All GE14 80 < P 100 2.2100 -0.00700 P = Percent of Rated Core Power F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 24 of 40

Figure 5 Power Dependent MCPR(P) Limits for NSS - BOC to Coastdown 3.60 Flow> 50%

ATRIUM 10XM 3.40 3.20 3.00 Flow > 50% GE14 2.80 MCPR(P) 2.60 Flow 50% GE14 2.40 Flow 50%

ATRIUM10XM 2.20 2.00 GE14 1.80 1.60 ATRIUM 10XM 1.40 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

MCPRP = A + B*P Flow Type Power A B F 50 A10XM 25 P 40 4.2268 -0.05067 F > 50 A10XM 25 P 40 4.8933 -0.05733 All A10XM 40 50 GE14 25 P 40 4.7900 -0.05400 All GE14 40 < P 60 2.1000 -0.00750 All GE14 60 < P 80 1.6500 0.00000 All GE14 80 < P 100 2.1700 -0.00650 P = Percent of Rated Core Power F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 25 of 40

Figure 6 Flow Dependent MCPR(F) Limits 1.85 1.80 Flow Deoendent MCPR Limit - MCPRF(F) 1.75 1.70 1.65 1.60 1.55 1.50 1.45 1.40 1.35 1.30 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

MCPRF = A + B*F Flow Type Power A B 30 F 80 Both All 2.0480 -0.00860 80 < F 107 Both All 1.3600 0.00000 F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

The f low-dependent MCPR limits shown above apply to both GE14 f uel and ATRIUM 10XM f uel.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 26 of 40

Figure 7 Power/Flow Map NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 27 of 40

Figure 8 Power Dependent MCPR(P) Limits for Pressure Regulator Out of Service (PROOS) 3.60 Flow > 50%

3.40 ATRIUM 10XM 3.20 3.00 Flow > 50% GE14 2.80 MCPR(P) 2.60 Flow 50% GE14 2.40 Flow 50%

ATRIUM 10XM GE14 2.20 2.00 1.80 ATRIUM 10XM GE14 1.60 1.40 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

MCPRP = A + B*P Flow Type Power A B F 50 A10XM 25 P 40 4.2268 -0.05067 F > 50 A10XM 25 P 40 4.8933 -0.05733 All A10XM 40 50 GE14 25 P 40 4.7900 -0.05400 All GE14 40 < P 60 2.9000 -0.01550 All GE14 60 < P 80 2.5400 -0.00950 All GE14 80 < P 85 2.1000 -0.00400 All GE14 85 < P 100 1.9800 -0.00400 P = Percent of Rated Core Power F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 28 of 40

Figure 9 Pressure Regulator Out Of Service Interim MFLCPR Limit 1.02 1.00 GE14 0.98 0.96 0.94 ATRIUM 10XM 0.92 Interim MFLCPR Limit for PROOS 0.90 0.88 ATRIUM 10XM 0.86 0.84 0.82 GE14 0.80 0.78 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

MFLCPR = A + B*P Flow Type Power A B All A10XM 25 P 40 1.0000 0.00000 All A10XM 40 < P 60 0.7776 0.00120 All A10XM 60 < P 85 0.6685 0.00302 All A10XM 85 < P 100 0.9627 -0.00015 All GE14 25 P 40 1.0000 0.00000 All GE14 40 < P 60 0.6934 0.00240 All GE14 60 < P 80 0.5693 0.00447 All GE14 80 < P 85 1.0765 -0.00187 All GE14 85 < P 100 1.1496 -0.00194 P = Percent of Rated Core Power Table is valid f or NSS and TSSS times.

The limits are not dependent on core f low.

Results f rom the Table above are accurate to two decimal places NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 29 of 40

Figure 10 Power Dependent LHGR Multipliers for Pressure Regulator Out of Service (PROOS) 1.10 1.00 0.90 0.80 LHGRFAC(P) 0.70 0.60 GE14 0.50 Flow 50%

GE14 0.40 Flow > 50%

0.30 GE14 0.20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

LHGRFACP = A + B*P Flow Type Power A B F 50 GE14 25 P 40 0.1367 0.00933 F > 50 GE14 25 P 40 0.2232 0.00467 All GE14 40 < P 85 0.3624 0.00444 All GE14 85 < P 100 0.2930 0.00667 P = Percent of Rated Core Power F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 30 of 40

Figure 11 Pressure Regulator Out of Service (PROOS)

Interim MFLPD Limit 1.02 Flow > 50% GE14 1.00 0.98 0.96 Flow 50%

GE14 0.94 Interim MFLPD Limit for PROOS 0.92 GE14 0.90 0.88 0.86 0.84 0.82 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 POWER (% Rated)

MFLPD = A + B*P Flow Type Power A B F 50 GE14 25 P 40 1.0630 -0.00252 F > 50 GE14 25 P 40 1.0000 0.00000 All GE14 40 < P 85 1.0269 -0.00199 All GE14 85 < P 100 0.9809 0.00019 P = Percent of Rated Core Power Results f rom the Table above are accurate to two decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 31 of 40

Figure 12 Power Dependent MCPR(P) Limits for SLO with NSS/TSSS Insertion Rates 3.60 Flow > 50% ATRIUM 10XM 3.40 3.20 3.00 Flow > 50% GE14 MCPR(P) 2.80 2.60 Flow 50% ATRIUM Flow 50% GE14 10XM GE14 2.40 2.20 ATRIUM 10XM 2.00 25 30 35 40 45 50 55 60 65 70 POWER (% Rated)

MCPRP = A + B*P Flow Type Power A B F 50 A10XM 25 P 40 4.2600 -0.05000 F > 50 A10XM 25 P 40 4.9433 -0.05733 All A10XM 40 50 GE14 25 P 40 4.8400 -0.05400 All GE14 40 < P 60 2.4500 -0.00300 All GE14 60 < P 66 2.7698 -0.00833 P = Percent of Rated Core Power F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 32 of 40

Figure 13 Power Dependent MAPLHGR Multipliers MAPFACP = A + B*P Flow Type Power A B F 50 GE14 25 P 40 0.3287 0.00773 F > 50 GE14 25 P 40 0.4577 0.00153 All GE14 40 < P 100 0.4780 0.00522 P = Percent of Rated Core Power F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 33 of 40

Figure 14 Flow Dependent MAPLHGR Multipliers MAPFACF = A + B*F Flow Type Power A B 30 F 78.6 GE14 All 0.4560 0.00680 78.6 < F 99 GE14 All 0.9908 0.00000 99 < F 107 GE14 All 1.0000 0.00000 F = Percent of Rated Core Flow In addition to the f low dependent multipliers, Monticello also requires an ECCS MAPLHGR multiplier of 0.9908 f or operation at or below 99% core f low f or GE14 f uel. This multiplier ensures that the of f -rated limits assumed in the EPU ECCS-LOCA analyses bound the cycle-specif ic off-rated limits calculated f or EFW operation.

Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 34 of 40

Figure 15 Pressure Regulator Out Of Service (PROOS)

Power Dependent MAPLHGR Multipliers MAPFACP = A + B*P Flow Type Power A B F 50 GE14 25 P 40 0.3287 0.00773 F > 50 GE14 25 P 40 0.4577 0.00153 All GE14 40 < P 85 0.4850 0.00400 All GE14 85 < P 100 0.2930 0.00707 P = Percent of Rated Core Power F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 35 of 40

Figure 16 Pressure Regulator Out of Service (PROOS)

Interim MAPRAT Limits MAPRAT = A + B*P Flow Type Power A B All GE14 25 P < 40 1.0000 0.00000 All GE14 40 P 85 0.9790 -0.00100 All GE14 85 < P 100 0.8000 0.00200 P = Percent of Rated Core Power Results f rom the Table above are accurate to three decimal places.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 36 of 40

Figure 17 MSIV Out-of-Service Flow Dependent LHGR Multipliers 1.10 LHGR FLOW FACTOR - LHGRFAC(F) 1.00 0.90 0.80 0.70 0.60 0.50 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

LHGRFACF = A + B*F Flow Type Power A B 30.0 F 34.2 Both All 0.5271 0.00024 34.2 < F 40.05 Both All 0.0729 0.01349 40.05 < F 48.14 Both All 0.3171 0.00826 48.14 < F 57.26 Both All 0.3190 0.00822 57.26 < F 78.65 Both All 0.3185 0.00823 78.65 < F 81.46 Both All 0.3161 0.00826 81.46 < F 81.59 Both All 0.3226 0.00818 81.59 < F 82.60 Both All 0.9908 0.00000 82.60 < F 99.0 Both All 0.9908 0.00000 99.0 < F 99.01 Both All -90.0892 0.92000 99.01 < F 107.0 Both All 1.00000 0.00000 F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

The LHGR mulipliers shown above apply to both GE14 f uel and ATRIUM 10XM f uel.

In addition to the f low dependent multipliers, Monticello also requires an ECCS MAPLHGR multiplier of 0.9908 f or operation at or below 99% core f low f or GE14 f uel. This multiplier ensures that t he of f -rated limits assumed in the EPU ECCS-LOCA analyses bound the cycle-specif ic off-rated limits calculated f or EFW operation.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 37 of 40

Figure 18 MSIV Out-of-Service Flow Dependent MCPR(F) Limits 2.00

- MCPR(F) 1.90 1.80 Flow Deoendent MCPR Limit 1.70 1.60 1.50 1.40 1.30 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

MCPRF = A + B*F Flow Type Power A B 30 F 80 Both All 2.326 -0.01120 80 < F 107 Both All 1.4300 0.00000 F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

The f low-dependent MCPR limits shown above apply to both GE14 f uel and ATRIUM 10XM f uel.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 38 of 40

Figure 19 MSIV Out-of-Service (MSIVOOS)

Interim MFLPD Multipliers 1.04 1.02 1.00 0.98 LHGR FLOW FACTOR -

0.96 0.94 0.92 LHGRFAC(F) 0.90 0.88 0.86 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 Core Flow (% Rated)

MFLPD = A + B*F Flow Type Power A B 30.0 F 34.2 Both All 1.3766 -0.01464 34.2 < F 40.05 Both All 0.5663 0.00905 40.05 < F 48.14 Both All 0.9726 0.00035 48.14 < F 57.26 Both All 1.2807 -0.00605 57.26 < F 78.65 Both All 0.8260 0.00189 78.65 < F 81.46 Both All 0.3227 0.00829 81.46 < F 81.59 Both All 0.9614 0.00045 81.59 < F 82.60 Both All 1.6549 -0.00804 82.60 < F 99.0 Both All 0.9908 0.00000 99.0 < F 99.01 Both All -90.0892 0.920000 99.01 < F 107.0 Both All 1 0.00000 F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

The f low-dependent MFLPD limits shown above apply to both GE and ATRIUM10XM f uel.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 39 of 40

Figure 20 MSIV Out-of-Service (MSIVOOS)

Interim MFLCPR Limits 0.98 Interim MFLCPR Limit for MSIVOOS 0.96 0.94 0.92 0.90 0.88 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

MFLCPRF = A + B*F Flow Type Power A B 30 F 80 Both All 0.8685 0.00103 80 < F 107 Both All 0.951 0.00000 F = Percent of Rated Core Flow Results f rom the Table above are accurate to three decimal places.

The f low-dependent MCPR limits shown above apply to both GE14 f uel and ATRIUM 10XM f uel.

NAD-MN-050NP, Monticello Cycle 31 COLR, Revision 2 Page 40 of 40

ENCLOSURE 2 AFFIDAVIT FOR MONTICELLO NUCLEAR GENERATING PLANT CYCLE 31 PROPRIETARY CORE OPERATING LIMITS REPORT REVISION 2 NAD-MN-050P (3 pages follow)

Global Nuclear Fuel - Americas AFFIDAVIT I, Kent E. Halac, state as follows:

(1) I am a Senior Engineer, Regulatory Affairs, Global Nuclear Fuel - Americas, LLC (GNF-A), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in Revision 2 of Monticello Nuclear Generating Plant, Cycle 31, Proprietary, Core Operating Limits Report NAD-MN-050P, dated March 2023. GNF proprietary information in Revision 2 of the Monticello Nuclear Generating Plant Cycle 31 COLR is identified by a dotted underline inside double square brackets. ((This sentence is an example.{3})) In each case, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.

(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group

v. FDA, 704F2d1280 (DC Cir. 1983).

(4) Some examples of categories of information which fit into the definition of proprietary information are:

a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;

b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;

c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;

d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.

Monticello Cycle 31 COLR, Revision 2 Affidavit Page 1 of 3

The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.

(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.

(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-As fuel design and licensing methodology.

The development of the methods used in these analyses, along with the testing, development and approval of the supporting methodology was achieved at a significant cost to GNF-A or its licensor.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.

Monticello Cycle 31 COLR, Revision 2 Affidavit Page 2 of 3

The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GNF-A.

The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.

GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on this 17th day of March 2023.

Kent E. Halac Senior Engineer, Regulatory Affairs Global Nuclear Fuel - Americas, LLC 3901 Castle Hayne Road Wilmington, NC 28401 Kent.Halac@ge.com Monticello Cycle 31 COLR, Revision 2 Affidavit Page 3 of 3

L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2

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