NLS2022047, Core Operating Limits Report, Cycle 33, Revision 0

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Core Operating Limits Report, Cycle 33, Revision 0
ML22291A134
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Issue date: 10/14/2022
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NLS2022047
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Proprietary Information - Withhold Under 10 CFR 2.390 Nebraska Public Power District Al.ways there when you need us NLS2022047 October 14, 2022 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Core Operating Limits Report, Cycle 33, Revision 0 Cooper Nuclear Station, Docket No. 50-298, DPR-46

Dear Sir or Madam:

The purpose of this letter is to provide to the Nuclear Regulatory Commission the Core Operating Limits Report (COLR) for Cooper Nuclear Station (CNS) for Cycle 33. CNS Technical Specification 5.6.5.d requires that the COLR, including any midcycle revisions or supplements, be provided upon issuance for each reload cycle.

Global Nuclear Fuel (GNF) has determined that the CNS COLR contains GNF proprietary information, as defined by 10 CFR 2.390. The proprietary version of the COLR, Cycle 33, Revision 0, is provided in Enclosure 1. It is requested that Enclosure 1 be withheld from public disclosure. GNP, as the owner of the proprietary information, has executed an affidavit (Enclosure 3), which identifies that the proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure.

The proprietary information was provided to CNS in a GNF transmittal that is referenced by the affidavit. The proprietary information has been faithfully reproduced in the enclosed documentation such that the affidavit remains applicable. A non-proprietary version of the COLR,.Cycle 33, Revision 0, for public disclosure is provided in Enclosure 2.

This letter makes no regulatory commitments.

If you have

,, any questions regarding this submittal, please contact me at (402) 825-5416.

//- ff1, L 1 . ewhi~t Regulatory Affairs & Compliance Manager

/bk Enclosure 1 contains Proprietary Information. Upon separation from Enclosure 1, the cover letter and the remainder of the document are decontrolled.

COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com

Proprietary Information - Withhold Under 10 CFR 2.390 NLS2022047 Page 2 of2

Enclosures:

1. Cooper Nuclear Station Core Operating Limits Report, Cycle 33, Revision O - Proprietary
2. Cooper Nuclear Station Core Operating Limits Report, Cycle 33, Revision O - Non-Proprietary
3. Global Nuclear Fuel - Americas Affidavit cc: Regional Administrator w/enclosures USNRC - Region IV Cooper Project Manager w/enclosures USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/enclosures USNRC-CNS NPG Distribution w/o enclosures CNS Records w/enclosures contains Proprietary Information. Upon separation from Enclosure 1, the cover letter and the remainder of the document are decontrolled.

NLS2022047 Page 1 of27 COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT CYCLE 33, REVISION 0 NON-PROPRIETARY

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT Cycle 33 Revision 0 Print Sign Date Preparer Lome Covington fa-'-(,.. 7-"2 z Reviewer Ryan VanderPlas 6}-I.JtJ/4- /f)- L/ ~ l&1ll Reactor and Fuels Engineering Grant Reynolds ~~~ /t:J/1//2 2-Supervisor SED Manager I

Shannon Schulz /O/'i/~-i2-Infonnation Notice This is a non-proprietary version of the Cooper Nuclear Station Cycle 33 COLR, which has GNF proprietary information removed.

The removed GNF proprietary informatlon is identified by blank information inside double square brackets. (( )).

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 REVISION HISTORY Revision Date Description 0 10/4/2022 Original issue 2 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 TABLE OF CONTENTS

1. INTRODUCTION .................................................................................................4
2. AVERAGE PLANAR LINEAR HEAT GENERATION ............................................ 5 2.1 Technical Specification Reference ............................................................. 5 2.2 Two Recirculation Loop Operation ............................................................. 5 2.3 Single Recirculation Loop Operation .......................................................... 6 Table 2-1: MAPLHGRsrn Values .......................................................................... ?

Table 2-2: Power Dependent LHGRFACp Multiplier ............................................ 8 Table 2-3: Flow Dependent LHGRFACf Multiplier ................................................ 9

3. MINIMUM CRITICAL POWER RATIO ............................................................... 10 3.1 Technical Specification Reference ........................................................... 10 3.2 Cycle Dependent MCPR99.9% .................................................................... 10 3.3 Two Recirculation Loop Operation ........................................................... 10 3.4 Application of Scram Time Surveillance Data to OLMCPR(100) ............... 11 3.5 Single Recirculation Loop Operation ........................................................ 14 Table 3-1: OLMCPR Values for OLMCPR(100) Calculation ............................... 15 Table 3-2: Power Dependent Kp and MCPRp .................................................... 16 Table 3-3: Flow Dependent MCPRf ................................................................... 17
4. TURBINE BYPASS SYSTEM RESPONSE TIME .............................................. 18 4.1 Technical Specification Reference ........................................................... 18 4.2 System Response Time ........................................................................... 18
5. ROD BLOCK MONITOR TRIP SETPOINTS ...................................................... 18 5.1 Technical Specification Reference ........................................................... 18 5.2 Trip Setpoints ........................................................................................... 18 Table 5-1: Rod Block Monitor Channel Settings ................................................. 19
6. MAXIMUM LINEAR HEAT GENERATION RATE .............................................. 20 6.1 Technical Specifications Reference ......................................................... 20 6.2 Two Recirculation Loop Operation ........................................................... 20 6.3 Single Recirculation Loop Operation ........................................................ 21 Table 6-1: LHGRsrn Values for GNF2 ................................................................ 22
7. STABILITY POWER/FLOW MAP ....................................................................... 23 7.1 Technical Specification Reference ........................................................... 23 7 .2 Stability Exclusion Region ........................................................................ 23 Figure 7-1: Stability Exclusion Region Map ........................................................ 24
8. REFERENCES ..................................................................................................25 3 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0

1. INTRODUCTION The Core Operating Limits Report (COLR) provides the limits for operation of the Cooper Nuclear Station for Cycle 33 at a rated power of 2419 MWth. Cooper Nuclear Station Technical Specification 5.6.S(a) requires the COLR to contain the following limits:
  • The Average Planar Linear Heat Generation Rate for Specifications 3.2.1 and 3.7.7.
  • The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.7.7, and the MCPR99.9% for Specification 3.2.2,
  • The Linear Heat Generation Rates for Specifications 3.2.3 and 3.7.7,
  • The three Rod Block Monitor Upscale Allowable Values for Specification 3.3.2.1,
  • The power/flow map defining the Stability Exclusion Region for Specification 3.4.1.

In addition, the following information is required to be in the COLR:

  • NEDE-24011-P-A-31, "General Electric Standard Application for Reactor Fuel", November 2020 (Reference 1),
  • NEDE-23785-1-P-A, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident", Volume 111, Revision 1, October 1984 (Reference 2),
  • NEDO-31960-A and NEDO-31960-A Supplement 1, "BWR Owner's Group Long-Term Stability Solutions Licensing Methodology", November 1995 (Reference 3).

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0

2. AVERAGE PLANAR LINEAR HEAT GENERATION 2.1 Technical Specification Reference Technical Specifications 3.2.1 and 3.7.7.

2.2 Two Recirculation Loop Operation During steady-state power operation, the Maximum Average Planar Linear Heat Generation Rate (MAPLHGR), as a function of fuel bundle type, axial location, and average planar exposure, shall not exceed the applicable limiting value.

MAPLHGR limits were determined as documented in Reference 14 and Reference

15. The MAPLHGR limits in Table 2-1 are defined in Attachment M of Reference 14.

The maximum Average Planar Linear Heat Generation Rate with two recirculation loops in operation is defined as follows:

MAPLHGR Limit = minimum [MAPLHGR(P), MAPLHGR(F)]

where, MAPLHGR(P) = MAPLHGRsrn

  • LHGRFACf, MAPLHGRsrn = Fuel bundle type and exposure dependent MAPLHGR values for rated core power and flow conditions represented by the values shown in Table 2-1, LHGRFACp = Core power dependent multiplier shown in Table 2-2, LHGRFACf = Core flow rate dependent multiplier shown in Table 2-3.

The MAPLHGRsrn values presented in Table 2-1 are the most limiting values for each fuel bundle type from the exposure dependent values defined in section 16.3 of Reference 6a. The core monitoring computer will be used to verify the MAPLHGR limits for each fuel bundle type are not violated.

The LHGRFACp and LHGRFACf multipliers presented in Table 2-2 and Table 2-3, respectively, are defined in Table 3-16 of Reference 5, and/or in Appendix D of the cycle specific SRLR (Reference 6a).

No thermal limits monitoring is required below 25% of rated power as defined in applicability section of Technical Specification 3.2.1. Therefore, the MAPLHGR 5 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 limit defined above is only applicable for core conditions at or above 25% of rated power.

2.3 Single Recirculation Loop Operation The maximum allowable Average Planar Linear Heat Generation Rate with one recirculation loop in operation (SLO) is defined as follows:

MAPLHGR Limit= minimum [MAPLHGR(P), MAPLHGR(F), MAPLHGR(SLO)]

where, MAPLHGR(SLO) = MAPLHGRsrn

MAPFAC(SLO) = Single loop operation MAPLHGR multiplier, and MAPLHGR(P) and MAPLHGR(F) are as defined in Section 2.2 above.

As shown above, it is not necessary to apply both the off-rated (LHGRFACp or LHGRFACf) and SLO multiplier corrections at the same time.

The single loop operation MAPLHGR multiplier for each fuel bundle type are defined in Section 16.3 of Reference 6a as shown in the table below.

SLO MAPLHGR Fuel Bundle Type Multiplier All bundles 0.87 6 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 Table 2-1: MAPLHGRsro Values Average MAPLHGRsTD Values for all GNF2 Planar bundles Exposure (GWd/MTU) (kW/ft) 0.00 12.19 29.41 12.19 67.00 7.35 70.00 6.55 GNF Bundle# GNF Fuel Bundle Identification EDB-4555 GNF2-P1 0DG2B395-12G6.0-1 00T2-150-T6-4555 (GNF2)

EDB-4556 GNF2-P1 0DG2B394-13GZ-1 00T2-150-T6-4556 (GN F2)

EDB-4557 GNF2-P1 0DG2B378-13G7.0-1 00T2-150-T6-4557 (GNF2)

EDB-4558 GNF2-P1 0DG2B391-12G7.0-1 00T2-150-T6-4558 (GNF2)

EDB-4559 GNF2-P1 0DG2B393-13G7.0-1 00T2-150-T6-4559 (GNF2)

EDB-4560 GNF2-P1 0DG2B394-14GZ-1 00T2-150-T6-4560 (GNF2)

EDB-4708 GNF2-P1 0DG2B395-12G6.0-1 00T2-150-T6-4708 (GNF2)

EDB-4709 GNF2-P1 0DG2B389-14GZ-1 00T2-150-T6-4709 (GNF2)

EDB-4710 GNF2-P1 0DG2B376-13G7.0-100T2-150-T6-4710 (GNF2)

EDB-4711 GNF2-P1 0DG2B393-12G7.0-1 00T2-150-T6-4711 (GNF2)

EDB-4712 GNF2-P1 0DG2B393-1 0G7.0/2G6.0-1 00T2-150-T6-4712 (GNF2)

EDB-4713 GNF2-P1 0DG2B392-12G7.0/1 G6.0-1 00T2-150-T6-4713 (GNF2)

EDB-4954 GNF2-P1 0DG2B399-12G6.0-1 00T2-150-T6-4954 (GNF2)

EDB-4955 GNF2-P1 0DG2B390-14GZ-1 00T2-150-T6-4955 (GNF2)

EDB-4956 GNF2-P1 0DG2B377-13G7.0-1 00T2-150-T6-4956 (GNF2)

EDB-4957 GNF2-P1 0DG2B393-12G7.0-1 00T2-150-T6-4957 (GNF2)

EDB-4958 GNF2-P1 0DG2B393-13GZ-1 00T2-150-T6-4958 (GNF2)

EDB-4959 GNF2-P1 0DG2B390-13G7.0-1 00T2-150-T6-4959 (GNF2) 7 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 Table 2-2: Power Dependent LHGRFACp Multiplier Applicable Plant Configuration:

  • Equipment In Service

LHGRFACp Multiplier for Power S 30.0%

Flow~ 50.0% Flow< 50.0%

Power(%) Multiplier Power(%) Multiplier 25.0 0.405* 25.0 0.505 30.0 0.422* 30.0 0.530 LHGRFACp Multiplier for Power> 30.0%

Power(%) Multiplier 30.0 0.634 100.0 1.000

  • The LHGRFACp multiplier to be applied for all applicable plant configurations is based on the conservative Turbine Bypass Valve Out-of-Service values. All other multipliers shown in the table are the same for Equipment In Service and Turbine Bypass Valve Out-of-Service.

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 Table 2-3: Flow Dependent LHGRFACf Multiplier Applicable Plant Configuration:

  • Equipment In Service

LHGRFACf Multiplier for Maximum Runout Flow of 107.0%

Flow(%) Multiplier 32.5 0.677 90.0* 1.000 107.0 1.000 Multipliers for Other Maximum Runout Flow Setpoints:

LHGRFACf Multiplier for Maximum Runout Flow of 102.5%

Flow(%) Multiplier 32.5 0.706 80.0* 1.000 102.5 1.000 LHGRFACf Multiplier for Maximum Runout Flow of 112.0%

Flow(%) Multiplier 32.5 0.642 90.0* 1.000 112.0 1.000 LHGRFACf Multiplier for Maximum Runout Flow of 117.0%

Flow(%) Multiplier 32.5 0.606 90.0* 1.000 117.0 1.000

  • Flow values are conservative relative to the calculated flow values corresponding to the LHGRFACf =

1.000 intercept as presented in Reference 5.

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0

3. MINIMUM CRITICAL POWER RATIO 3.1 Technical Specification Reference Technical Specifications 3.2.2 and 3.7.7.

3.2 Cycle Dependent MCPR99.9%

The cycle-dependent Safety Limit Minimum Critical Power Ratio ensures that 99.9% of the fuel rods are not susceptible to boiling transition (MCPRss.s%) and which is used to calculate Operating Limit Minimum Critical Power Ratio. In Cycle 33, the MCPRss.s% value is 1.12 for two recirculation loop operation and is 1.14 for single recirculation loop operation as specified in Section 11 of Reference 6a. The use of MCPRss.s% was adopted in accordance with Reference 16.

3.3 Two Recirculation Loop Operation During steady-state power operation, the Minimum Critical Power Ratio (MCPR) shall be greater than or equal to the Operating Limit MCPR (OLM CPR) defined as a function of cycle exposure and plant conditions.

The OLMCPR with two recirculation loops in operation is defined as follows:

OLMCPR = maximum [MCPRp, MCPRfj where, MCPRp = Core power dependent MCPR shown in Table 3-2, MCPRf = Core flow rate dependent MCPR shown in Table 3-3.

The MCPRp and MCPRf values presented in Table 3-2 and Table 3-3, respectively, are defined in Reference 6a and Reference 5. As shown in Reference 4, the MCPRp value is calculated as follows:

For P > P(Bypass), MCPRp = OLMCPR(100)

  • KP For P s P(Bypass), MCPRp = MCPRp as a function of core flow where, P(Bypass) = P(Bypass) is the core power level below which the Turbine Stop Valve closure and Turbine Control Valve fast closure scrams are assumed to be bypassed. P(Bypass) is currently set at 30% of rated power per the current cycle OPL-3.

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 OLMCPR(100) = OLMCPR for rated core power and flow conditions.

OLMCPR(100) is defined as a function of scram time surveillance data as defined in Section 3.4.

KP = Core power dependent OLMCPR multiplier.

No thermal limits monitoring is required below 25% of rated power as defined in applicability section of Technical Specification 3.2.2. Therefore, the OLM CPR limit defined above is only applicable for core conditions at or above 25% of rated power.

3.4 Application of Scram Time Surveillance Data to OLMCPR(100)

The OLMCPR(100) value applicable to the MCPRp calculation, presented in Section 3.3, is determined based on scram time surveillance data recorded during the current operating cycle and with the following methodology defined in Reference 7, Reference 11 , and Reference 12.

3.4.1 Mean Scram Time {'rave}

The mean scram time for control rod insertion to notch 36 is calculated as follows:

where,

= Scram time test sequential identification number, n = Number of scram time tests performed to date in the cycle (including beginning of cycle),

N; = Number of control rods measured in test i,

,: i = Average insertion time to notch 36 measured in test i.

3.4.2 20% Insertion Conformance Limit Scram Time {i:s}

The 20% insertion conformance limit scram time is calculated as follows from Reference 12:

11 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 where,

µ = Mean of the distribution for average scram time insertion to position 36 used in the ODYN Option B analysis, a = Standard deviation of the distribution for average scram time insertion to position 36 used in the ODYN Option B analysis, N1 = Total number of control rods measured during the first surveillance test performed at beginning of cycle.

The values forµ, a and N1 are given below.

µ = 0.830 a = 0.019 N1 = 137 Using the values given above, Reference 7 defines the 20% insertion conformance limit scram time as, rB = 0.830+ 0.367 yJ .n LNi 1=!

3.4.3 Scram Time Quality Factor (1:)

The scram time quality factor is calculated as follows:

If 1:ave ~ 1:B, ,: = 0.

If 1:ave > 1:B, r = __;;;;,;_;;.__---.::;_

'Cave - '[ B

'CA -'[B where, TA = Technical Specification limit for 20% insertion (notch 36)

= 1.08 seconds (Technical Specification Table 3.1.4-1 ).

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 3.4.4 Calculation of OLMCPR{100)

The OLMCPR for rated power and core flow conditions is calculated as follows based on the calculated values for -rave, -rs, and 1:

OLMCPR(100) =OLMCPR 8 + 1 * (OLMCPRA - OLMCPR 8 )

Using the following values obtained from Section 11 of Reference 6a:

OLMCPRA = Option A OLMCPR value given in Table 3-1, OLMCPRs = Option B OLMCPR value given in Table 3-1.

The stability OLMCPR was determined using the methodology in Reference 13. It is conservatively bounded by the Option A and B transient OLMCPR values as documented in Section 15.1 of Reference 6a.

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 3.5 Single Recirculation Loop Operation The Operating Limit MCPR with a single recirculation loop in operation is defined as follows:

OLMCPR = maximum [MCPR(SL-P), MCPR(SL-F)]

where, For P > P(Bypass),

OLMCPR(100) + .1OLMCPR(SLO)

MCPR(SL-P) = KP

  • maximum {

MCPR (SLO Pump Seizure)

For P s P(Bypass), MCPR(SL-P) = MCPRp + ~OLMCPR(SLO),

For all core flows, MCPR(SL-F) = MCPRf + ~OLMCPR(SLO).

~OLMCPR(SLO) = 0.02 from Section 11 of Reference 6a, and OLMCPR(100),

MCPRp, and MCPRf are as defined in Section 3.3.

The increase in the OLMCPR for single loop operation corresponds to an increase in the MCPR99.9% for single loop operation as described in Reference 6a and Reference 16.

MCPR (SLO Pump Seizure) is a constant value scaled to the cycle specific SLO MCPR99.9% and adjusted to rated conditions. The limiting MCPR(SLO Pump seizure) value= 1.44 from Section 11 of Reference 6a. This value does not require a LlOLMCPR(SLO) adjustment for SLO MCPR99.9%-

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 Table 3-1: OLMCPR Values for OLMCPR(100) Calculation Applicable Cycle OLMCPRA OLMCPRs Equipment Status Exposure Range GNF2 GNF2 BOC to 1.46 1.36 EOR-4. 759 GWd/MTU Equipment In-Service EOR-4. 759 GWd/MTU to 1.49 1.39 EOR-2.582 GWd/MTU EOR-2.582 GWd/MTU 1.55 1.45 to EOC BOC to 1.48 1.38 EOR-4. 759 GWd/MTU Turbine Bypass Valve EOR-4.759 GWd/MTU to Out of Service 1.51 1.41 EOR-2.582 GWd/MTU (TBVOOS)

EOR-2.582 GWd/MTU 1.58 1.48 to EOC NOTES:

1. The range of OLMCPR values are defined as follows:

OLMCPRA = Option A OLMCPR from Reference 6a based on Option A analysis using full core scram times defined in Technical Specification Table 3.1.4-1.

OLMCPRs = Option B OLMCPR from Reference 6a based on Option B analysis described in Reference 1.

2. The OLMCPR values presented above apply to rated power operation based on a two loop operation MCPR99.9% of 1.12.
3. The OLMCPR values presented above bound the operating domains from the MELLL load line to Increased Core Flow (ICF) operation to 105% of rated flow throughout the cycle.
4. Exposure ranges are defined as follows:

BOC = Beginning of cycle, EOC = End of cycle, EOR = End of rated power operation at rated core flow and all rods withdrawn.

The EOR exposure input in the core monitoring system will be adjusted periodically based on actual cycle operations.

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 Table 3-2: Power Dependent Kp and MCPRp Applicable Plant Configuration:

  • Equipment In Service

MCPRp for Powers 30.0%

Flow:? 50.0% Flow< 50.0%

Power(%) MCPRp Power(%) MCPRp 25.0 3.43* 25.0 2.68*

30.0 3.15* 30.0 2.39*

Kp Multiplier for Power > 30.0%

Power(%) Multiplier 30.0 1.481 45.0 1.280 60.0 1.151 85.0 1.082 100.0 1.000

  • The MCPRp for all applicable plant configurations is based on the conservative Turbine Bypass Valve Out-of-Service values. The Kp multipliers are the same for Equipment In Service and Turbine Bypass Valve Out-of-Service.

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 Table 3-3: Flow Dependent MCPRf Applicable Plant Configuration:

  • Equipment In Service

MCPRf for Maximum Runout Flow of 107.0%

Flow(%) MCPRf 30.0 1.59 87.5 1.24 107.0 1.24 MCPRf for Other Maximum Runout Flow Setpoints:

MCPRf for Maximum Runout Flow of 102.5%

Flow(%) MCPRf 30.0 1.553 82.3 1.240 102.5 1.240 MCPRf for Maximum Runout Flow of 112.0%

Flow(%) MCPRf 30.0 1.639 93.6 1.240 112.0 1.240 MCPRf for Maximum Runout Flow of 117.0%

Flow(%) MCPRf 30.0 1.695 98.9 1.240 117.0 1.240 17 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0

4. TURBINE BYPASS SYSTEM RESPONSE TIME 4.1 Technical Specification Reference Technical Specification 3.7.7.3.

4.2 System Response Time The system response time for the Turbine Bypass System to be at 80% of rated bypass flow is 0.3 seconds. This was obtained from Reference 8.

5. ROD BLOCK MONITOR TRIP SETPOINTS 5.1 Technical Specification Reference Technical Specification 3.3.2.1.

5.2 Trip Setpoints The allowable values for the power dependent Rod Block Monitor (RBM) upscale trip setpoints are defined in Table 5-1, along with the applicable reactor power ranges associated with each trip setpoint. The Analytical Limit (AL) and Technical Specification Allowable Value (AV) presented in Table 5-1 were determined in Reference 9 and Reference 4.

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 Table 5-1: Rod Block Monitor Channel Settings Analytical Allowable Trip Function Limit 1 Value 1 Low Power Setpoint (LPSP) 30.0% 27.5%

Intermediate Power Setpoint (I PSP) 65.0% 62.5%

High Power Setpoint (HPSP) 85.0% 82.5%

Downscale Trip Setpoint (DTSP) 89.0% 92.0%

Scaled Cycle Applicable Core Generic Specific Analytical Allowable Trip Function Power Range MCPR MCPR Limit 4 Value 4 Limit 2 Limit3 Low Trip Setpoint LPSP :s; P < IPSP 1.36 1.36 :s; 123.0 I 125 S 120.0 / 125 (LTSP)

Intermediate Trip IPSP :s; P < HPSP 1.36 1.36 :s; 118.0 / 125 S115.0/125 Setpoint (ITSP)

High Trip Setpoint HPSP :s; P 1.36 1.36 :s; 113.2 / 125 S 110.5 / 125 (HTSP)

NOTES:

1. Setpoints are given in units of percent of rated power.
2. The scaled generic MCPR limit is based on an adjusted MCPR limit from the generic analysis documented in Section 5.1. of Reference 4 performed for an Analyzed Trip Level Setting (without RBM filter) of 114.0% of the reference level or an Analyzed Trip Level Setting (with RBM filter) of 113.2% of the reference level. The generic MCPR limit of 1.30 was calculated in Reference 4 for an SLMCPR of 1.07. The scaled generic MCPR limit documented above was calculated by multiplying the generic limit of 1.30 by the ratio of the MCPR99.9% and the SLMCPR used in Reference 4 (1.12 / 1.07).
3. The cycle specific MCPR Limit is determined as the minimum achievable OLMCPR during the cycle. This value can be set by the Rod Withdrawal Error OLMCPR or the Option B pressurization events OLMCPR at each exposure range as specified in Section 11 of Reference 6a.
4. RBM trip setpoints are given in units of divisions of full scale.

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0

6. MAXIMUM LINEAR HEAT GENERATION RATE 6.1 Technical Specifications Reference Technical Specifications 3.2.3 and 3.7.7.

6.2 Two Recirculation Loop Operation During steady-state power operation, the maximum Linear Heat Generation Rate (LHGR) in any fuel rod in any fuel bundle at any axial location shall not exceed the applicable limiting value.

The maximum Linear Heat Generation Rate with two recirculation loops in operation is defined as follows:

LHGR Limit = minimum [LHGR(P), LHGR(F)]

where, LHGR(P) = LHGRsrn

  • LHGRFACf, LHGRsro = Fuel bundle type, fuel rod type, and peak pellet exposure dependent maximum LHGR values for rated core power and flow conditions represented by the values shown in Table 6-1, LHGRFACp = Core power dependent multiplier shown in Table 2-2, LHGRFACf = Core flow rate dependent multiplier shown in Table 2-3.

The LHGRsro values presented in Table 6-1 represent the maximum allowable peak pellet power (LHGR) as a function of pellet exposure for each pin type in each fuel bundle design. The maximum allowable LHGR limit values have the following pin type dependencies: UO2 only pins which can either be full and partial length fuel rods, gadolinia rods based on the local gadolinia concentration in the rod. The values in Table 6-1 were obtained from Reference 5. The core monitoring computer will be used to verify the pellet specific LHGR limits for each fuel bundle type are not violated.

No thermal limits monitoring is required below 25% of rated power as defined in applicability section of Technical Specification 3.2.3. Therefore, the LHGR limit defined above is only applicable for core conditions at or above 25% of rated power.

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Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 6.3 Single Recirculation Loop Operation The maximum allowable Linear Heat Generation Rate with one recirculation loop in operation (SLO) is defined as follows:

LHGR Limit = minimum [LHGR(P), LHGR(F), LHGR(SLO)]

where, LHGR(SLO) = LHGRsrn

LHGRFAC(SLO) = Single loop operation PLHGR multiplier, and LHGR(P) and LHGR(F) are as defined in Section 6.2 above.

As shown above, it is not necessary to apply both the off-rated (LHGRFACp or LHGRFACf) and SLO multiplier corrections at the same time.

The single loop operation peak LHGR (PLHGR) multipliers for each fuel bundle type is selected from in Section 16 of Reference 6a as shown in the table below.

The application of the SLO Multiplier to the LHGR limit is described in Section 16.3 of Reference 6a.

SLO PLHGR Fuel Bundle Type Multiplier All bundles 0.87 21 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 Table 6-1: LHGRsro Values for GNF2 For all GNF2 bundles LHGRsro LHGRsro LHGRsro Peak Pellet (kW/ft) (kW/ft) (kW/ft)

Exposure U02 Only U02/GD203 U02/GD203 (GWd/MTU) 6%gad 7%gad rr 11 See cover page for removal of proprietary information statement GNF Bundle# GNF Fuel Bundle Identification EDB-4555 GNF2-P1 0DG2B395-12G6.0-1 00T2-150-T6-4555 (GNF2)

EDB-4556 GNF2-P1 0DG2B394-13GZ-1 00T2-150-T6-4556 (GNF2)

EDB-4557 GNF2-P1 0DG2B378-13G7.0-1 00T2-150-T6-4557 (GNF2)

EDB-4558 GNF2-P1 0DG2B391-12G7.0-1 00T2-150-T6-4558 (GNF2)

EDB-4559 GNF2-P1 0DG2B393-13G7.0-1 00T2-150-T6-4559 (GNF2)

EDB-4560 GNF2-P1 0DG2B394-14GZ-1 00T2-150-T6-4560 (GNF2)

EDB-4708 GNF2-P1 0DG2B395-12G6.0-1 00T2-150-T6-4708 (GNF2)

EDB-4709 GNF2-P1 0DG2B389-14GZ-1 00T2-150-T6-4709 (GNF2)

EDB-4710 GNF2-P1 0DG2B376-13G7.0-100T2-150-T6- 4710 (GNF2)

EDB-4711 GNF2-P10DG2B393-12G7.0-100T2 -150-T6-4711 (GNF2)

EDB-4712 GNF2-P1 0DG2B393-1 0G7.0/2G6.0-1 00T2-150-T6-4712 (GNF2)

EDB-4713 GNF2-P1 0DG2B392-12G7.0/1G6.0-1 00T2-150-T6-4713 (GNF2)

EDB-4954 GNF2-P1 0DG2B399-12G6.0-1 00T2-150-T6-4954 (GNF2)

EDB-4955 GNF2-P10DG2B390-14GZ-1 00T2-150-T6-4955 (GNF2)

EDB-4956 GNF2-P1 0DG2B377-13G7.0-1 00T2-150-T6-4956 (GNF2)

EDB-4957 GNF2-P1 0DG2B393-12G7.0-1 00T2-150-T6-4957(GNF2)

EDB-4958 GNF2-P1 0DG2B393-13GZ-1 00T2-150-T6-4958 (GNF2)

EDB-4959 GNF2-P1 0DG2B390-13G7.0-1 00T2-150-T6-4959 (GNF2) 22 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0

7. STABILITY POWER/FLOW MAP 7.1 Technical Specification Reference Technical Specification 3.4.1.

7.2 Stability Exclusion Region The stability region is represented by the Exclusion Region boundaries defined in Section 15 of Reference 6a. A detailed view of the Exclusion Region of the power/flow map is presented in Figure 7-1.

Intentional operation within the Exclusion Region is prohibited. The Exclusion Region is defined in the table below.

Exclusion Region Power (% of CLTP Rated) Flow (% of Rated)

Highest Flow Control 73.5 47.1 Line Endpoint Natural Circulation 39.8 32.5 Line Endpoint The region boundaries are defined using the modified shape function given in Reference 10. The calculation of the region boundaries as a function of core thermal power and core flow rate is summarized below.

where, P = core thermal power value on the region boundary(% of rated),

W = core flow rate corresponding to power, P, on the region boundary (%

of rated),

PA = core thermal power at the highest flow control line endpoint (% of rated on the highest flow control line),

Ps = core thermal power at the natural circulation line endpoint(% of rated on the natural circulation line),

WA= core flow rate at the highest flow control line endpoint(% of rated on the highest flow control line),

Ws = core flow rate at the natural circulation line endpoint (% of rated on the natural circulation flow control line).

23 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 Figure 7-1: Stability Exclusion Region Map 33 Power-Flow Map 80 75 10 45 I

I Stability Exclusion region - - - -

I I Stability Buffer region I

40 so 60 90 HYJ 24 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0

8. REFERENCES The following references are identified in this report:
1. NEDE-24011-P-A-31, "General Electric Standard Application for Reactor Fuel", November 2020.
2. NEDE-23785-1-P-A, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident", Volume 111, Revision 1, October 1984.
3. NEDO-31960-A and NEDO-31960-A Supplement 1, "BWR Owner's Group Long-Term Stability Solutions Licensing Methodology", November 1995.
4. NEDC-31892P, "Extended Load Line Limit and ARTS Improvement Program Analyses for Cooper Nuclear Station Cycle 14", Revision 1, June 1991.
5. NEDC-33270P, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)", Revision 11, August 2020.
6. CNS Engineering Report 2022-015, "Cycle 33 SRLR/FBIR ", Revision 0, May 2022, and the accepted Global Nuclear Fuel reference documents:
a. 006N2092, "Supplemental Reload Licensing Report for Cooper Nuclear Station Reload 32 Cycle 33", Revision 0, May 2022
7. CNS Procedure 10.9, "Control Rod Scram Time Evaluation", current revision.
8. CNS Procedure 6.TG.301, "MAIN TURBINE STEAM BYPASS SYSTEM RESPONSE TIME TEST", current revision
9. NEDC 98-024, "APRM - RBM Setpoint Calculation", current revision.
10. NEDE-33213P-A, "ODYSY Application for Stability Licensing Calculations Including Option I-D and 11 Long Term Solutions", April 2009.
11. GE Letter DTl:NPPD 81-029, "ODYN Option B Scram Time Surveillance Procedures," March 19, 1981.
12. GE Letter DGC:89-190, "Cooper Reload 13 Technical Specification Changes,"

November 30, 1989.

13. NEDE-33766P-A, "GEH Simplified Stability Solution (GS3)", Revision 1, March 2015.
14. CNS Calculation NEDC 99-046 "Review of GE Calculation - Cooper Nuclear Station SAFER/GESTR-LOCA Analysis", Revision 12, February 2019.
15. Licensing Topical Report, Global Nuclear Fuel, The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance, Technical Basis - NEDC-25 of 26

Contains Non-Proprietary Information CNS Cycle 33 COLR Revision 0 33256P-A, Revision 1, Qualification - NEDC-33257P-A, Revision 1, and Application Methodology - NEDC-33258P-A, Revision 1, September 2010.

16. USNRC to John Dent (NPPD), Cooper Nuclear Station - Issuance of Amendment no. 265, RE: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-564, Revision 2, "Safety Limit MCPR" (EPID I-2019-LLA-0127), May 12, 2020.
17. CNS Procedure 10.3, Cycle 33 OPL-3 Rev. 0.

26 of 26

NLS2022047 Page 1 of 4 GLOBAL NUCLEAR FUEL - AMERICAS AFFIDAVIT

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 O of "Cooper Nuclear Station Cycle 33 Core Operating Limits Report," dated October 2022. GNF proprietary information in Revision O of the Cooper Nuclear Station Cycle 33 COLR is identified by a dotted underline inside double square brackets. ((This_ sentence _is an_ example.l3 1J] In each case, the superscript notation t 31 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, 704F2dl280 (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.

Cooper Nuclear Station Cycle 33 COLR 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-A's 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.

Cooper Nuclear Station Cycle 33 COLR 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 4th day of October 2022.

Kent E. Halac Senior Engineer, Regulatory Affairs Global Nuclear Fuel - Americas, LLC 3901 Castle Hayne Road Wilmington, NC 2840 I Kent.Halac@ge.com Cooper Nuclear Station Cycle 33 COLR Affidavit Page 3 of 3

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