NLS2018055, Core Operating Limits Report Cycle 31, Revision 0

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Core Operating Limits Report Cycle 31, Revision 0
ML18297A061
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Issue date: 10/03/2018
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NLS2018055
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NLS2018055 Page 1 of29 COOPER NUCLEAR STATION CORE OPERA TING LIMITS REPORT CYCLE 31, REVISION 0 NON-PROPRIETARY

ENCL0SURE2 KGO-NPP-HPl-18-125 Cooper Nuclear Station Cycle 31 Core Operating Limits Report Non-Proprietary Information INFORMATION NOTICE This is a non-proprietary version of Enclosure 1 of KGO-NPP-HPl-18-125, which has the proprietary information removed.

Portions of the document that have been removed are indicated by white space inside open and closed bracket as shown here ((

)).

Contains Non-Proprietary Information COOPER NUCLEAR STATION CNS Cycle 31 COLR Revision 0 CORE OPERA TING LIMITS REPORT Preparer Reviewer Reactor and Fuels Engineering Supervisor

.Director of Engineering Cycle 31 Revision O Print Ryan VanderPlas Lorne Covington Talisa Chambers Khalil Dia Sign Proprietary Information Notice Date 3-0d-2@18 This is the non-proprietary version of the Cooper Nuclear Station Cycle 31 COLR, which has GNF proprietary information removed.

Portions of the document that have been removed are indicated by white space inside open and closed bracket as show here ((

)).

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Revision 0

Contains Non-Proprietary Information Date 10/09/2018 REVISION HISTORY Description Original issue 2 of 27 CNS Cycle 31 COLR Revision 0

Contains Non-Proprietary Information TABLE OF CONTENTS CNS Cycle 31 COLR Revision 0

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: MAPLHGRsTD Values............................................................................... 7 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................................................................ 1 O 3.2 Two Recirculation Loop Operation................................................................ 10 3.3 Application of Scram Time Surveillance Data to OLMCPR(100).................. 11 3.4 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 LINEARHEAT 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: Bounding LHGRsTD 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............................................................. 25

8.

REFERENCES..................................................................................................... 26 3 of 27

Contains Non-Proprietary Information

1.

INTRODUCTION CNS Cycle 31 COLR Revision 0 The Core Operating Limits Report (COLR) provides the limits for operation of the Cooper Nuclear Station for Cycle 31 at a rated power of 2419 MWth. Cooper Nuclear Station Technical Specification 5.6.5(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, 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-26-US, "General Electric Standard Application for Reactor Fuel", January 2018 (Reference 1),

NEDE-23785-1-P-A, 'The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident", Volume Ill, Revision 1, October 1984 (Reference 2),

NED0-31960-A and NED0-31960-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 31 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 15, and Reference 16. The MAPLHGR limits in Table 2-1 are defined in Attachment M of Reference 15.

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 Attachment 2 of Reference 6. 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 Reference 5, and Attachment 2 of Reference 6.

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 limit defined above is only applicable for core conditions at or above 25% of rated power.

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Contains Non-Proprietary Information 2.3 Single Recirculation Loop Operation CNS Cycle 31 COLR Revision 0 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)

MAPFAC(SLO)

= MAPLHGRsro

= 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 of Attachment 2 of Reference 6 as shown in the table below.

Fuel Bundle Type All bundles 6 of 27 SLO MAPLHGR Multiplier 0.87

Contains Non-Proprietary Information Table 2-1: MAPLHGRsro Values CNS Cycle 31 COLR Revision 0 Average MAPLHGRsm Values for all GNF2 Planar bundles Exposure (kW/ft)

(GWd/MTU) 0.00 12.19 29.41 12.19 67.00 7.35 70.00 6.55 GNF Bundle#

GNF Fuel Bundle Identification EDB-4115 GNF2-P10DG2B390-14GZ-100T2-150-T6-4115 (GNF2)

EDB-4116 GNF2-P10DG2B389-12GZ-100T2-150-T6-4116 (GNF2)

EDB-4276 GNF2-P10DG2B391-14GZ-100T2-150-T6-4276 (GNF2)

EDB-4277 GNF2-P10DG2B390-2G7.0/10G6.0-100T2-150-T6-4277 (GNF2)

EDB-4420 GNF2-P10DG2B392-13GZ-100T2-150-T6-4420 (GNF2)

EDB-4421 GNF2-P10DG2B391-13GZ-100T2-150-T6-4421 (GNF2)

EDB-4422 GNF2-P10DG2B393-13GZ-100T2-150-T6-4422 (GNF2)

EDB-4423 GNF2-P10DG2B390-13GZ-100T2-150-T6-4423 (GNF2)

EDB-4555 GNF2-P1 ODG2B395-12G6.0-1 OOT2-150-T6-4555 (GNF2)

EDB-4556 GNF2-P10DG2B394-13GZ-100T2-150-T6-4556 (GNF2)

EDB-4557 GNF2-P1 ODG2B378-13G7.0-1 OOT2-150-T6-4557 (GNF2)

EDB-4558 GNF2-P10DG2B391-12G7.0-100T2-150-T6-4558 (GNF2)

EDB-4559 GNF2-P1 ODG2B393-13G7.0-1 OOT2-150-T6-4559 (GNF2)

EDB-4560 GNF2-P10DG2B394-14GZ-100T2-150-T6-4560 (GNF2) 7 of 27

Contains Non-Proprietary Information CNS Cycle 31 COLR Revision 0 Table 2-2: Power Dependent LHGRFACp Multiplier Equipment In Service and Turbine Bypass Valve Out-of-Service (1 Valve OOS)*

Limits for Power< 30.0%

Power(%)

Limit for Flow >50.0%

Limit for Flow s50.0%

25.0 0.405 0.505 30.0 0.422 0.530 Limits for Power ~30.0%

Power(%)

Limit 30.0 0.634 100.0 1.000 Values are based on Turbine Bypass Value Out-of-Service and are conservative to the All Equipment in Service values.

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Contains Non-Proprietary Information CNS Cycle 31 COLR Revision 0 Table 2-3: Flow Dependent LHGRFACf Multiplier Equipment in Service and Turbine Bypass Valve Out-of-Service (1 Valve OOS)

Limits for a Maximum Runout Flow of 107.0%

Flow(%)

Limit 32.5 0.677 90.0 1.000 107.0 1.000 Limits for a Maximum Runout Flow of 102.5%

Flow(%)

Limit 32.5 0.706 80.0 1.000 102.5 1.000 Limits for a Maximum Runout Flow of 112.0%

Flow(%)

Limit 32.5 0.642 90.0 1.000 112.0 1.000 Limits for a Maximum Runout Flow of 117.0%

Flow(%)

Limit 32.5 0.606 90.0 1.000 117.0 1.000 9 of 27

Contains Non-Proprietary Information CNS Cycle 31 COLR Revision 0

3.

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

3.2 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 (OLMCPR) defined as a function of cycle exposure and plant conditions.

The Operating Limit MCPR with two recirculation loops in operation is defined as follows:

where, MCPRp

. MCPRf OLMCPR = maximum [MCPRp, MCPRfJ

= Core power dependent MCPR shown in Table 3-2,

= 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 5, and Attachment 2 of Reference 6. As shown in Reference 4, the MCPRp value is calculated as follows:

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

  • Kp For P < 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.

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 3.3.

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 OLMCPR 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 31 COLR Revision 0 3.3 Application of Scram Time Surveillance Data to OLMCPR(100)

The OLMCPR(100) value applicable to the MCPRp calculation, presented in Section 3.2, 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.

3.3.1 Mean Scram Time {tavel The mean scram time for control rod insertion to notch 36 is calculated as follows:

where, i = 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,

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

3.3.2 20% Insertion Conformance Limit Scram Time {tsl The 20% insertion conformance limit scram time is calculated as follows from Reference 12:

where,

µ

= Mean of the distribution for average scram time insertion to position 36 used in the ODYN Option B analysis, cr

= Standard deviation of the distribution for average scram time insertion to position 36 used in the ODYN Option B

analysis, Ni = Total number of control rods measured during the first surveillance test performed at beginning of cycle.

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Contains Non-Proprietary Information The values for µ, cr and N1 are given below.

µ

= 0.830 cr

= 0.019 N1

= 137 CNS Cycle 31 COLR Revision 0 Using the values given above, Reference 7 defines the 20% insertion conformance limit scram time as, r, ~0.830+0.367 ~"I INi i=l 3.3.3 Scram Time Quality Factor (1:)

The scram time quality factor is calculated as follows:

where, If 'tave :S 'ts, If 'tave > 'ts,

't = 0.

Tave -TB r=~~-

TA-TB rA = 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 3.3.4 Calculation of OLMCPR(100)

CNS Cycle 31 COLR Revision 0 The OLMCPR for rated power and core flow conditions is calculated as follows based on the calculated values for 't:ave, 1:s, and 1::

{

OLMCPRRWE OLMCPR(100) = maximum OLMCPRs +,: * (OLMCPRA - OLMCPRs)

Using the following values obtained from Section 11 of Attachment 2 of Reference 6:

OLMCPRRWE = the RWE OLMCPR = 1.37 based on 114% RBM setpoint 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 14. It is conservatively bounded by the option A and B transient OLMCPR values as documented in Section 15.2 of Attachment 2 of Reference 6.

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I~

Contains Non-Proprietary Information 3.4 Single Recirculation Loop Operation CNS Cycle 31 COLR Revision 0 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),

MCPR(SL-P) =

maximum[OLMCPR(100)+~0LMCPR(SLO}, MCPR(SLO Pump seizure)]

  • Kp For P < P(Bypass},

MCPR(SL-P) = MCPRp + ~OLMCPR(SLO},

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

~OLMCPR(SLO) = 0.03 from Section 11 of Attachment 2 of Reference 6, and OLMCPR(100), MCPRp, and MCPRf are as defined in Section 3.2.

The increase in the OLMCPR for single loop operation corresponds to an increase in the safety limit MCPR (SLMCPR) for single loop operation as described in Attachment 2 of Reference 6.

MCPR(SLO Pump Seizure) is a constant value scaled to the cycle specific SLO SLMCPR and adjusted to rated conditions. The limiting MCPR(SLO Pump seizure) value= 1.46 for GNF2 fuel. This value does not require a f10LMCPR(SLO) adjustment for SLO SLMCPR.

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Contains Non-Proprietary Information CNS Cycle 31 COLR Revision 0 Table 3-1: OLMCPR Values for OLMCPR(100) Calculation Equipment Status Applicable Cycle OLMCPRA OLMCPRe Exposure Range GNF2 GNF2 BOC to 1.42 1.32 EOR-5.426 GWd/MTU Equipment In-Service EOR-5.426 to 1.49 1.39 EOR-3.222 GwD/MTU EOR-3.222 GWd/MTU 1.57 1.47 to EOC Turbine Bypass Valve BOC to EOR-5.426 1.45 1.35 GwD/MTU Out of Service EOR-5.426 to EOC (TBVOOS)

GwD/MTU 1.59 1.49 NOTES:

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

OLMCPRA =

Option A OLMCPR from Attachment 2 of Reference 6 based on Option A analysis using full core scram times defined in Technical Specification Table 3.1.4-1.

OLMCPRs =

Option B OLMCPR from Attachment 2 of Reference 6 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 Safety Limit MCPR (SLMCPR) of 1.13.
3. The OLMCPR values presented above bound 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 may be adjusted periodically based on actual cycle operations.

5. OLMCPR8 for GNF2 for equipment in service from BOC to EOR-3.222 GWd/MTU is set by the Inadvertent HPCI /L8 transient. From EOR-3.222 GWd/MTU through EOC it is set by the load rejection without bypass transient. For one turbine valve OOS, OLMCPR8 is set by the Inadvertent HPCI /L8 transient.

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Contains Non-Proprietary Information CNS Cycle 31 COLR Revision 0 Table 3-2: Power Dependent Kp and MCPRp Equipment in Service and Turbine Bypass Valve Out-of-Service (1 Valve OOS)*

Limits for Power <30.0%

Power(%)

Limit for Flow >50.0%

Limits for Flow :S50.0%

MCPRo MCPRo 25.0 3.46 2.71 30.0 3.18 2.41 Limits for Power ~30.0%

Power(%)

Limit Ko 30.0 1.481 45.0 1.280 60.0 1.151 85.0 1.082 100.0 1.000 Values are based on Turbine Bypass Value Out-of-Service and are conservative to the Equipment in Service values.

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Contains Non-Proprietary Information CNS Cycle 31 COLR Revision 0 Table 3-3: Flow Dependent MCPRf Equipment in Service and Turbine Bypass Valve Out-of-Service (1 Valve OOS)

Limits for a Maximum Runout Flow of 107.0%

Flow(%)

Limit MCPRf 30.0 1.610 90.6 1.240 107.0 1.240 Limits for a Maximum Runout Flow of 102.5%

Flow(%)

Limit 30.0 1.567 84.1 1.240 102.5 1.240 Limits for a Maximum Runout Flow of 112.0%

Flow(%)

Limit 30.0 1.654 95.3 1.240 112.0 1.240 Limits for a Maximum Runout Flow of 117.0%

Flow(%)

Limit 30.0 1.710 100.6 1.240 117.0 1.240 17 of 27

Contains Non-Proprietary Information CNS Cycle 31 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 31 COLR Revision 0 Table 5-1: Rod Block Monitor Channel Settings Trip Function Analytical Allowable Limit 1 Value 1 Low Power Setpoint (LPSP) 30.0%

27.5%

Intermediate Power Setpoint (IPSP) 65.0%

62.5%

High Power Setpoint (HPSP) 85.0%

82.5%

Downscale Trip Setpoint (DTSP) 89.0%

92.0%

Scaled Cycle Trip Function Applicable Core Generic Specific Analytical Allowable Power Range MCPR MCPR Limit 3 Value 3 Limit 2 Limit2 Low Trip Setpoint LPSP s P < IPSP 1.37 1.32 s 123.0 / 125 S 120.0 / 125 (LTSP)

Intermediate Trip IPSP s P < HPSP 1.37 1.32 s 118.0/ 125 S 115.0 / 125 Setpoint (ITSP)

High Trip Setpoint HPSP s P 1.37 1.32 S113.2/125 S 110.5 / 125 (HTSP)

NOTES:

1. Setpoints are given in units of percent of rated power.
2. The RBM trip level settings associated with the MCPR limit, shown in the cycle specific MCPR limit in the above table, were verified in Section 1 O of Attachment 2 of Reference 6 to bound the cycle specific Rod Withdrawal Error (RWE) analysis for an RBM setpoint of 114% of reference level. The scaled generic MCPR limit is based on an adjusted MCPR limit from the generic analysis documented in 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 SLMCPR values (1.13/1.07).

3. RBM trip setpoints are given in units of divisions of full scale.

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Contains Non-Proprietary Information CNS Cycle 31 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

= LHGRsrn

  • LHGRFACf, LHGRsrn = 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 LHGRsrn 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; U02 only pins which can either be full and partial length fuel rods, Gadolinia rods based on the local and maximum 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 6.3 Single Recirculation Loop Operation CNS Cycle 31 COLR Revision 0 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)

= LHGRsTD

  • LHGRFAC(SLO},

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 are defined in Section 16 of Attachment 2 of Reference 6 as shown in the table below.

Fuel Bundle Type All bundles 21 of 27 SLO PLHGR Multiplier 0.87

Contains Non-Proprietary Information CNS Cycle 31 COLR Revision 0 Table 6-1: Bounding LHGRsm Values for GNF2 For all GNF2 bundles LHGRsTD LHGRsTD Peak Pellet (kW/ft)

(kW/ft)

Exposure U02 Only bounding gad for all (GWd/MTU) gad cone to 7%max rr

))

un e ypes B

di T GNF Bundle#

GNF Fuel Bundle Identification EDB-41.15 GNF2-P10DG2B390-14GZ-1 OOT2-150-T6-4115 (GNF2)

EDB-4116 GNF2-P10DG2B389-12GZ-1 OOT2-150-T6-4116 (GNF2)

EDB-4276 GNF2-P10DG2B391-14GZ-100T2-150-T6-4276 (GNF2)

EDB-4277 GNF2-P10DG2B390-2G7.0/10G6.0-100T2-150-T6-4277 (GNF2)

EDB-4420 GNF2-P10DG2B392-13GZ-100T2-150-T6-4420 (GNF2)

EDB-4421 GNF2-P10DG2B391-13GZ-100T2-150-T6-4421 (GNF2)

EDB-4422 GNF2-P10DG2B393-13GZ-100T2-150-T6-4422 (GNF2)

EDB-4423 GNF2-P10DG2B390-13GZ-100T2-150-T6-4423 (GNF2)

EDB-4555 GNF2-P10DG2B395-12G6.0-100T2-150-T6-4555 (GNF2)

EDB-4556 GNF2-P10DG2B394-13GZ-100T2-150-T6-4556 (GNF2)

EDB-4557 GNF2-P10DG2B378-13G7.0-100T2-150-T6-4557 (GNF2)

EDB-4558 GNF2-P10DG2B391-12G7.0-100T2-150-T6-4558 (GNF2)

EDB-4559 GNF2-P10DG2B393-13G7.0-100T2-150-T6-4559 (GNF2)

EDB-4560 GNF2-P10DG2B394-14GZ-100T2-150-T6-4560 (GNF2) 22 of 27

Contains Non-Proprietary Information

7.

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

7.2 Stability Exclusion Region CNS Cycle 31 COLR Revision 0 The stability region is represented by the Exclusion Region boundaries defined in Section 15 of Attachment 2 of Reference 6. 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 CL TP Flow (% of Rated)

Rated)

Highest Flow Control 74.4 48.1 Line Endpoint Natural Circulation 39.2 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

= a core thermal power value on the region boundary (% of rated},

W

= the 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},

P8

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

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Contains Non-Proprietary Information CNS Cycle 31 COLR Revision 0 WA

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

W8

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

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110 100 90 80

~ 70 0 -

(1) 60

~

0 l:L.

cu 50 E..

Ql

~ 40 30 20 10 0

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25 of 27

Contains Non-Proprietary Information

8. REFERENCES The following references are identified in this report:

CNS Cycle 31 COLR Revision 0

1.

NEDE-24011 -P-A-26, "General Electric Standard Application for Reactor Fuel", January 2018.

2.

NEDE-23785-1-P-A, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident", Volume Ill, Revision 1, October 1984.

3.

NED0-31960-A and NED0-31960-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, May 1991.

5.

NEDC-33270P, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II}", Revision 6, March 2016.

6.

CNS Engineering Report 2018-024, "001 N5305-RO, "Fuel Bundle Information Report (FBIR), Supplemental Reload Licensing Report (SRLR) for Cooper Nuclear Station Reload 30 Cycle 31 and Supplemental transmittals", Revision 0, August 2018.

7.

CNS Procedure 10.9, "Control Rod Scram Time Evaluation", current revision.

8.

GE Design Specification 22A2859, "Turbine-Generator and Steam Bypass System", Paragraph 4.3.8, Revision 3.

9.

NEDC 98-024, "APRM - RBM Setpoint Calculation", current revision.

10.

NEDE-33213P-A, "ODYSY Application for Stability Licensing Calculations Including Option 1-0 and II Long Term Solutions", April 2009.

11.

GE Letter DTl:NPPD 81-029, "ODYN Option B Scram Time Surveillance Procedures," March 29, 1981.

12.

GE Letter DGC:89-190, "Cooper Reload 13 Technical Specification Changes," November 30, 1989.

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Contains Non-Proprietary Information CNS Cycle 31 COLR Revision 0

13.

NEDC-33763P, "GNF2 Fuel Design Cycle-Independent Analyses for Cooper Nuclear Station", Revision 1, July 2012.

14.

GEH Licensing Topical Report, GEH Simplified Stability Solution (GS3),

NEDE-33766P-A,Revision 1, March 2015.

15.

CNS Calculation NEDC 99-046 "Review of GE Calculation - Cooper Nuclear Station SAFER/GESTR-LOCA Analysis", Revision 11, January 2018.

16.

Licensing Topical Report, Global Nuclear Fuel, The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance, Technical Basis -

NEDC-33256P-A, Revision 1, Qualification - NEDC-33257P-A, Revision 1, and Application Methodology - NEDC-33258P-A, Revision 1, September 2010.

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