ML24323A080

From kanterella
Jump to navigation Jump to search
Core Operating Limits Report for Dresden Unit 2 Cycle 29, Revision 21
ML24323A080
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 11/15/2024
From: Yoder B
Constellation Energy Generation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML24323A078 List:
References
SVPLTR 24-0037
Download: ML24323A080 (1)
v • d • e


Text

COLR Dresden 2 Revision 21 Page 1 of 25 Core Operating Limits Report For Dresden Unit 2 Cycle 29 Prepared By:

Date: __________

Ben Yoder - Nuclear Fuels Reviewed By: _____________________________________

Date: __________

Ann Eastmond - Nuclear Fuels Reviewed By: _____________________________________

Date: __________

Samia Alghazo - Nuclear Fuels Reviewed By: _____________________________________

Date: __________

James Aitken - Reactor Engineering Approved By: _____________________________________

Date: __________

John Wagner - Acting NF Senior Manager SQR By:

Date: __________

Brandon De Graaf - Station Qualified Reviewer Yoder, Ben Michael Digitally signed by Yoder, Ben Michael Date: 2024.11.07 15:41:40 -06'00' Eastmond, Ann Digitally signed by Eastmond, Ann Date: 2024.11.07 15:51:40 -06'00' Alghazo, Samia Digitally signed by Alghazo, Samia Date: 2024.11.07 15:55:40 -06'00' Aitken, James Michael 2024.11.07 15:59:46 -06'00' Wagner, John Digitally signed by Wagner, John Date: 2024.11.07 16:21:52 -06'00' Digitally signed by Degraaf, Brandon Michael Date: 2024.11.08 07:21:38 -06'00'

COLR Dresden 2 Revision 21 Page 2 of 25 Table of Contents Page List of Tables................................................................................................................................................. 3 Record of Dresden 2 Cycle 29 COLR Revisions.............................................................................................. 4

1. Terms and Definitions............................................................................................................................... 5
2. General Information................................................................................................................................. 7
3. Average Planar Linear Heat Generation Rate........................................................................................... 8
4. Operating Limit Minimum Critical Power Ratio........................................................................................ 9 4.1. Power-Dependent MCPR........................................................................................................ 10 4.2. Flow-Dependent MCPR........................................................................................................... 12 4.3. Scram Time.............................................................................................................................. 13 4.4. Recirculation Pump ASD Settings............................................................................................ 14 4.5. Safety Limit MCPR................................................................................................................... 15
5. Linear Heat Generation Rate.................................................................................................................. 16
6. Control Rod Block Setpoints................................................................................................................... 19
7. Stability Protection Setpoints................................................................................................................. 20
8. Modes of Operation................................................................................................................................ 21 8.1. Allowable Modes.................................................................................................................... 21 8.2. Common Notes...................................................................................................................... 23
9. Methodology........................................................................................................................................... 24
10. References............................................................................................................................................ 25

COLR Dresden 2 Revision 21 Page 3 of 25 List of Tables Page 2.1: Cycle Exposure Range Definitions 7

3.1: MAPLHGR Versus Average Planar Exposure - GNF3 8

3.2: MAPLHGR Versus Average Planar Exposure - A10XM 8

3.3: MAPLHGR SLO Multipliers 8

4.1: OLMCPR - GNF3 and A10XM 9

4.2: MCPRp Limits and Multipliers (Kp) - GNF3 10 4.3: MCPRp Limits and Multipliers (Kp) - A10XM 11 4.4: MCPRf Limits - GNF3 12 4.5: MCPRf Limits - A10XM 12 4.6: Scram Time Option B Applicability Determination 13 4.7: Cycle Specific SLMCPR (MCPR99.9%) - All Fuel Types 15 5.1: LHGR Limits - GNF3 16 5.2: LHGR Limits - A10XM 16 5.3: LHGRFACp Multipliers - GNF3 5.4: LHGRFACp Multipliers - A10XM 17 17 5.5: LHGRFACf Multipliers - GNF3 18 5.6: LHGRFACf Multipliers - A10XM 18 6.1: Rod Block Monitor Upscale Instrumentation Setpoints 19 7.1: OPRM PBDA Trip Settings 20 8.1: Modes of Operation 21 8.2: Core Thermal Power and Flow Restrictions for EOOS Conditions 22

COLR Dresden 2 Revision 21 Page 4 of 25 Record of Dresden 2 Cycle 29 COLR Revisions Revision Description 21 Issuance with implementation of TSTF-564 to add MCPR99.9% and make appropriate language/administrative changes, including those to increase consistency with the Unit 3 COLR 20 Initial issuance for D2C29

COLR Dresden 2 Revision 21 Page 5 of 25

1. Terms and Definitions A10XM ATRIUM 10XM Active Control Rods Total number of control rods minus any inoperable rods AOO Anticipated Operational Occurrence ARO All Rods Out ASD Adjustable Speed Drive BOC Beginning of Cycle Coastdown Operation beyond end of full power extension techniques, plant power gradually reducing as available core reactivity diminishes CPR Critical Power Ratio CRWE Control Rod Withdrawal Error D2C29 Dresden Unit 2 Cycle 29 EFPH Effective Full Power Hours EOC End of Cycle EOOS Equipment Out of Service EOR End of Rated FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heater Out of Service FWRV Feedwater Regulating Valve FWT Feedwater Temperature GWd/MT GigaWatt Days per Metric Ton GWd/ST GigaWatt Days per Short Ton ICF Increased Core Flow Kp Off-rated Power Dependent OLMCPR Multiplier kW/ft KiloWatts Per Foot LHGR Linear Heat Generation Rate LHGRFACf Flow dependent LHGR Multiplier LHGRFACp Power dependent LHGR Multiplier LOCA Loss of Coolant Accident LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPRf Flow Dependent MCPR MCPRp Power Dependent MCPR MCPR99.9%

Limiting MCPR value such that 99.9 percent of the fuel in the core is expected to avoid boiling transition MELLLA Maximum Extended Load Line Limit Analysis Mlb/hr Million Pounds per Hour MOC Middle of Cycle MSIVOOS Main Steam Isolation Valve Out of Service MWd/MT MegaWatt Days per Metric Ton

COLR Dresden 2 Revision 21 Page 6 of 25 Terms and Definitions (Continued)

MWd/ST MegaWatt Days per Short Ton MWth MegaWatts Thermal OLMCPR Operating Limit Minimum Critical Power Ratio OOS Out of Service OPRM Oscillation Power Range Monitor PBDA Period Based Detection Algorithm Pbypass Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRVOOS Safety Relief Valve Out of Service SQR Station Qualified Reviewer The cycle average scram insertion time for 20% insertion Option B Scram Time Acceptance Criterion TBSOOS Turbine Bypass System Out of Service TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valve Out of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Service TCVSC TCV Slow Closure TIP Traversing Incore Probe TLO Two Loop Operation TMOL Thermal Mechanical Operating Limit TRM Technical Requirements Manual TSV Turbine Stop Valve TSVOOS Turbine Stop Valve Out of Service

COLR Dresden 2 Revision 21 Page 7 of 25

2. General Information This report is prepared in accordance with Technical Specification 5.6.5 (Reference [4]). The D2C29 reload is licensed by Global Nuclear Fuels. However, some legacy analyses by Framatome are still applicable for A10XM fuel as described in References [2], [9]. The data presented in this report is valid for all the following conditions, from Reference [6]:

Maximum Extended Load Line Limit down to 95.3% of rated core flow during full power operation (rated core flow is 98 Mlbm/hr).

Operation up to 108% rated core flow is licensed for this cycle. However, core flow cannot exceed 103.4% rated core flow due to unit specific limitations. For allowed operating regions, see the applicable power/flow map.

Maximum reduction of 120°F of the feedwater temperature for FWHOOS/FFWTR.

Coastdown to 40% rated power (Reference [1]) (rated core thermal power is 2957 MWth).

Operation at a power level above that which can be achieved with ARO, ICF, FFWTR, and steady-state equilibrium Xenon concentrations is not supported.

Power and flow dependent limits are listed for various power and flow levels. Linear interpolation on power and flow, as applicable, is to be used to find intermediate values.

For thermal limit monitoring above 108% rated core flow, higher flow values are given in the COLR to be used for linear interpolation. Steady state operation is not allowed in this region.

Limits are provided for transient conditions only.

All thermal limits are analyzed to remain valid with all analyzed scram speeds.

OLMCPR varies with scram speed as shown in Table 4.1.

See Table 8.2 for EOOS applicable restrictions.

Various EOOS conditions separated by / in the COLR represent single EOOS conditions and not any combination of conditions. Refer to the Modes of Operation Section of the COLR for a detailed explanation of allowable EOOS conditions. Combined EOOS conditions are denoted by a +.

Table 2.1 defines the three exposure ranges used in the COLR. The term (EOR29 - 2174 MWd/ST) means the projected Cycle 29 EOR exposure minus 2174 MWd/ST of exposure. The value of the EOR29 exposure is based on actual plant operation and is thus determined from cycle projections. The MOC to EOC limits shall be applied prior to the projected EOR29-2174 MWd/ST exposure. For cycle exposure dependent limits at the exact MOC exposure, the more limiting of the BOC to MOC and the MOC to EOC limits should be used. This can be achieved by applying the MOC to EOC limits to the MOC point, as all cycle exposure dependent limits in the MOC to EOC limit sets are the same as, or more limiting than, those in the BOC to MOC limit sets.

Table 2.1: Cycle Exposure Range Definitions (Reference [6])

Nomenclature Cycle Exposure Range BOC to MOC BOC29 to (EOR29 - 2174 MWd/ST)

MOC to EOC (EOR29 - 2174 MWd/ST) to EOC29 BOC to EOC BOC29 to EOC29

COLR Dresden 2 Revision 21 Page 8 of 25

3. Average Planar Linear Heat Generation Rate Technical Specifications Sections 3.2.1 and 3.4.1 Table 3.1 provides the MAPLHGR limit for GNF3. Table 3.2 provides the MAPLHGR limit for A10XM fuel.

Limits listed in Tables 3.1 and 3.2 are for TLO. During SLO, the MAPLHGR limits given in Tables 3.1 and 3.2 must be multiplied by a fuel dependent SLO MAPLHGR multiplier provided in Table 3.3.

Table 3.1: MAPLHGR Versus Average Planar Exposure - GNF3 (Reference [6])

Avg. Planar Exposure (GWd/ST)

Avg. Planar Exposure (GWd/MT)

MAPLHGR Limit (kW/ft) 0.00 0.00 13.45 9.07 10.00 12.91 35.83 39.50 11.32 57.60 63.50 8.00 63.50 70.00 6.00 Table 3.2: MAPLHGR Versus Average Planar Exposure - A10XM (Reference [2])

Avg. Planar Exposure (GWd/ST)

Avg. Planar Exposure (GWd/MT)

MAPLHGR Limit (kW/ft) 0.00 0.00 12.20 18.14 20.00 12.20 60.78 67.00 7.73 Table 3.3: MAPLHGR SLO Multipliers (References [2], [6])

Fuel Type MAPLHGR SLO Multiplier GNF3 0.78 A10XM 0.80

COLR Dresden 2 Revision 21 Page 9 of 25

4. Operating Limit Minimum Critical Power Ratio Technical Specification Sections 3.1.4, 3.2.2, 3.4.1, and 3.7.7 The OLMCPRs for D2C29 were established so that less than 0.1% of the fuel rods in the core are expected to experience boiling transition during an AOO initiated from rated or off-rated conditions. The cycle-specific SLMCPR, known as MCPR99.9%, can be found in Table 4.7 for dual loop and single loop operating conditions. The values in Table 4.7 were used to calculate the rated and off-rated MCPR limits.

The rated OLMCPRs given in Table 4.1 are the maximum values obtained from analysis of the pressurization events, non-pressurization events, and the Option III stability evaluation. MCPR values are determined by the cycle-specific fuel reload analyses in Reference [6].

Tables 4.2-4.5 include MCPR limits and multipliers for various specified EOOS conditions and off rated conditions. The OLMCPR is determined for a given power and flow condition by evaluating the power-dependent MCPR and the flow-dependent MCPR and selecting the greater of the two.

Table 4.1: OLMCPR - GNF3 and A10XM (Reference [6])

Application Group TLO/SLO Exposure Range Option A Option B GNF3 A10XM GNF3 A10XM Base Case TLO BOC-MOC 1.62 1.56 1.50 1.46 MOC-EOC 1.67 1.59 1.52 1.48 SLO BOC-MOC 1.64 1.58 1.52 1.48 MOC-EOC 1.69 1.61 1.54 1.50 Base Case + TBSOOS TLO BOC-MOC 1.65 1.58 1.53 1.51 MOC-EOC 1.73 1.66 1.58 1.55 SLO BOC-MOC 1.67 1.60 1.55 1.53 MOC-EOC 1.75 1.68 1.60 1.57 Base Case +

TCVSC/PLUOOS/PROOS TLO BOC-MOC 1.62 1.56 1.50 1.46 MOC-EOC 1.67 1.59 1.52 1.48 SLO BOC-MOC 1.64 1.58 1.52 1.48 MOC-EOC 1.69 1.61 1.54 1.50 Base Case + 1 FWRV in Manual Mode TLO BOC-MOC 1.63 1.57 1.51 1.47 MOC-EOC 1.69 1.60 1.54 1.49 SLO BOC-MOC 1.65 1.59 1.53 1.49 MOC-EOC 1.71 1.62 1.56 1.51

COLR Dresden 2 Revision 21 Page 10 of 25 4.1. Power-Dependent MCPR For operation less than or equal to 38.5% Pbypass core thermal power for all EOOS combinations, the MCPRp as a function of core thermal power and/or flow is shown in Tables 4.2 and 4.3. For operation greater than 38.5% core thermal power, the MCPR as a function of core thermal power is determined by multiplying the applicable rated condition OLMCPR limit shown in Table 4.1 by the applicable MCPR multiplier Kp found in Table 4.2 and 4.3. Kp is dependent on fuel type, core thermal power, and EOOS condition. MCPRp values are not provided for power levels below 38.5% for 1 FWRV in Manual Mode because operation in that condition below 38.5% power is not allowed per Reference [6]. Kp values for SLO above 50.0% power and MCPRp for SLO above 51.0% flow are not provided because operation above 50.0% power or 51.0% flow is not allowed in SLO per Reference [8].

Table 4.2: MCPRp Limits and Multipliers (Kp) - GNF3 (References [6], [8])

Application Group Core Flow

(%)

Core Thermal Power (%)

0.0 25.0 38.5 >38.5 50.0 >50.0 60.0 75.0 > 75.0 85.0 100.0 MCPRp Kp Base Case 60.0 3.30 3.30 2.86 1.667 1.517 1.229 1.164 1.101 1.101 1.099 1.000

<60.0 2.77 2.77 2.68 Base Case + SLO

>51.0 1.667 1.517 51.0 2.79 2.79 2.70 Base Case + TBSOOS 60.0 5.37 5.37 3.66 1.667 1.517 1.276 1.194 1.113 1.113 1.113 1.000

<60.0 4.02 4.02 2.84 Base Case + SLO +

TBSOOS

>51.0 1.667 1.517 51.0 4.04 4.04 2.86 Base Case +

TCVSC/PLUOOS/PROOS 60.0 3.30 3.30 2.86 1.667 1.517 1.517 1.409 1.291 1.101 1.099 1.000

<60.0 2.77 2.77 2.68 Base Case + SLO +

TCVSC/PLUOOS/PROOS

>51.0 1.667 1.517 51.0 2.79 2.79 2.70 Base Case + 1 FWRV in Manual Mode 60.0 1.667 1.517 1.229 1.164 1.101 1.101 1.099 1.000

<60.0 Base Case + SLO +

1 FWRV in Manual Mode

>51.0 51.0 1.667 1.517

COLR Dresden 2 Revision 21 Page 11 of 25 Table 4.3: MCPRp Limits and Multipliers (Kp) - A10XM (References [6], [8])

Application Group Core Flow

(%)

Core Thermal Power (%)

0.0 25.0 38.5 >38.5 50.0 >50.0 60.0 75.0 >75.0 85.0 100.0 MCPRp Kp Base Case 60.0 3.28 3.28 2.85 1.697 1.537 1.216 1.155 1.094 1.094 1.082 1.000

<60.0 2.82 2.82 2.73 Base Case + SLO

>51.0 1.697 1.537 51.0 2.84 2.84 2.75 Base Case + TBSOOS 60.0 5.32 5.32 3.62 1.697 1.537 1.315 1.231 1.102 1.102 1.095 1.000

<60.0 4.08 4.08 2.82 Base Case + SLO +

TBSOOS

>51.0 1.697 1.537 51.0 4.10 4.10 2.84 Base Case +

TCVSC/PLUOOS/PROOS 60.0 3.28 3.28 2.85 1.697 1.537 1.537 1.427 1.310 1.094 1.082 1.000

<60.0 2.82 2.82 2.73 Base Case + SLO +

TCVSC/PLUOOS/PROOS

>51.0 1.697 1.537 51.0 2.84 2.84 2.75 Base Case + 1 FWRV in Manual Mode 60.0 1.697 1.537 1.216 1.155 1.094 1.094 1.082 1.000

<60.0 Base Case + SLO +

1 FWRV in Manual Mode

>51.0 51.0 1.697 1.537

COLR Dresden 2 Revision 21 Page 12 of 25 4.2. Flow-Dependent MCPR Tables 4.4 and 4.5 give the OLMCPR limit as a function of the core flow (MCPRf) for GNF3 and A10XM, respectively. These limits are applicable for all analyzed EOOS conditions. MCPRf values are not provided for SLO above 51.0% rated core flow because operation above 51.0% rated flow is not allowed in SLO per Reference [8].

Table 4.4: MCPRf Limits - GNF3 (Reference [6])

Core Flow (%)

MCPRf TLO Limit MCPRf SLO Limit 0.00 1.76 1.78 30.0 1.58 1.60 51.0 1.45 1.47 85.2 1.25*

112.0 1.25*

Table 4.5: MCPRf Limits - A10XM (Reference [6])

Core Flow (%)

MCPRf TLO Limit MCPRf SLO Limit 0.0 1.74 1.76 30.0 1.58 1.60 51.0 1.47 1.49 92.2 1.25*

112.0 1.25*

  • This value is lower than the initial MCPR analyzed in the LOCA reports of record. However, because the core monitoring code calculates the off-rated MCPR by taking the maximum of the MCPRp, MCPRf,

and OLMCPR, the off-rated MCPR is inherently higher than that analyzed in the LOCA analysis and the LOCA analysis remains applicable at all conditions.

COLR Dresden 2 Revision 21 Page 13 of 25 4.3. Scram Time Option A and Option B refer to use of scram speeds for establishing MCPR operating limits. Option A scram speed time requirements are defined by Technical Specification section 3.1.4. Each operable control rod must demonstrate compliance with these scram times. If not, the rod is declared slow and counts as one of the 12 allowable slow rods per Technical Specification 3.1.4 (Reference [5]).

Option B scram speed time requirements are faster than Option A; therefore, MCPR margin is gained when rods meet the Option B criteria. Option B compliance is determined with a statistical calculation.

The cycle average scram insertion time for 20% insertion () must be less than or equal to the calculated in Table 4.6. Two equations are provided for Option B applicability determination in Table 4.6 for convenience of use. The first equation is simpler to apply and is the more conservative of the two equations provided. If Option B requirements are met with the first equation, there is no need to apply the second equation. The second equation can be used if the average scram times do not pass the first equation to meet the Option B requirements using the additional margin the second equation provides.

If the cycle average scram insertion time does not meet the Option B criteria, the appropriate MCPR value may be determined from a linear interpolation between the Option A and B limits as specified by Reference [10].

Table 4.6: Scram Time Option B Applicability Determination (References [10], [11])

Scram Time Required for Option B Application (secs) 0.694 OR 0.694+0.0264 1

=1 Where 1 is the number of active control rods measured at BOC, is the number of control rods measured in surveillance test i, and n is the number of surveillances.

COLR Dresden 2 Revision 21 Page 14 of 25 4.4. Recirculation Pump ASD Settings Technical Requirement Manual 2.1.a.1 D2C29 was analyzed with a slow flow excursion event assuming a failure of the recirculation flow control system such that the core flow increases slowly to the maximum flow physically permitted by the equipment, assumed to be 112% of rated core flow (Reference [6]); therefore, the recirculation pump ASD must be set to maintain core flow less than 112% (109.76 Mlb/hr) for all runout events.

COLR Dresden 2 Revision 21 Page 15 of 25 4.5 Safety Limit MCPR Technical Specification Section 3.2.2 The cycle-specific SLMCPR, known as MCPR99.9%, can be found in Table 4.7 for dual loop and single loop operating conditions. The values in Table 4.7 were used to calculate the rated and off-rated MCPR limits.

Table 4.7: Cycle Specific SLMCPR (MCPR99.9%) - All Fuel Types (Reference [6])

Loop Operation MCPR99.9%

Limit SLO 1.10 TLO 1.08

COLR Dresden 2 Revision 21 Page 16 of 25

5. Linear Heat Generation Rate Technical Specification Sections 3.2.3, 3.4.1, and 3.7.7 The TMOL at rated conditions for the GNF3 and A10XM fuel is established in terms of the maximum LHGR as a function of peak pellet (rod nodal) exposure. The LHGR limits for GNF3 fuel are presented in Table 5.1. The LHGR limits for A10XM fuel are presented in Table 5.2.

The power-and flow-dependent LHGR multipliers (LHGRFACp and LHGRFACf) are applied directly to the LHGR limits to protect against fuel melting and overstraining of the cladding during an AOO. In all conditions, the margin to the LHGR limits is determined by applying the lowest multiplier from the applicable LHGRFACp and LHGRFACf multipliers for the power/flow statepoint of interest to the steady state LHGR limit.

LHGRFACp and LHGRFACf multipliers were established to support base case and all EOOS conditions for all D2C29 exposures and scram speeds. The LHGRFACp multipliers for GNF3 and A10XM are presented in Table 5.3 and Table 5.4, respectively. The LHGRFAC p multipliers presented in Tables 5.3 and 5.4 are applicable to TLO at all powers and flows listed and SLO at or beneath 51.0% flow and 50.0% power. The LHGRFACf multipliers for GNF3 and A10XM are presented in Table 5.5 and Table 5.6, respectively.

LHGRFACf values are not provided for SLO above 51.0% rated core flow because operation above 51.0%

rated flow is not allowed in SLO per Reference [8]. For GNF3 only, a SLO multiplier is given in Reference

[6]; however, it is not used, nor represented, in Table 5.5. This is due to only the limiting multiplier being used and for the case of the SLO applicability flow range, the LHGRFACf multipliers are more restrictive than, and thereby bound, the SLO multiplier.

Table 5.1: LHGR Limits - GNF3 (Reference [7], [16])

Peak Pellet Exposure UO2 LHGR Limit See Table A-1 of Reference [7]

Peak Pellet Exposure Gadolinia LHGR Limit See Table A-2 of Reference [7]

Table 5.2: LHGR Limits - A10XM (Reference [9])

Peak Pellet Exposure (GWd/ST)

Peak Pellet Exposure (GWd/MT)

LHGR Limit (kW/ft) 0.00 0.00 13.40 17.15 18.90 13.40 67.50 74.40 7.10

COLR Dresden 2 Revision 21 Page 17 of 25 Table 5.3: LHGRFACp Multipliers - GNF3 (Reference [6])

Application Group Core Flow

(%)

Core Thermal Power (%)

0.0 25.0 38.5

>38.5 50.0

>50.0 60.0 75.0 >75.0 85.0 100.0 LHGRFACp Base Case 60.0 0.400 0.400 0.440 0.690 0.770 0.870 0.910 0.950 0.950 0.970 1.000

<60.0 0.440 0.440 0.440 Base Case + TBSOOS 60.0 0.280 0.280 0.360 0.690 0.770 0.830 0.870 0.920 0.920 0.940 1.000

<60.0 0.370 0.370 0.440 Base Case +

TCVSC/PLUOOS/PROOS 60.0 0.400 0.400 0.440 0.690 0.770 0.770 0.820 0.877 0.950 0.970 1.000

<60.0 0.440 0.440 0.440 Base Case + 1 FWRV in Manual Mode 60.0 0.690 0.770 0.823 0.864 0.895 0.895 0.912 1.000

<60.0 Table 5.4: LHGRFACp Multipliers - A10XM (Reference [6])

Application Group Core Flow

(%)

Core Thermal Power (%)

0.0 25.0 38.5

>38.5 50.0

>50.0 60.0 75.0 >75.0 85.0 100.0 LHGRFACp Base Case 60.0 0.450 0.450 0.510 0.690 0.770 0.870 0.910 0.950 0.950 0.970 1.000

<60.0 0.540 0.540 0.550 Base Case + TBSOOS 60.0 0.300 0.300 0.430 0.690 0.770 0.830 0.870 0.920 0.920 0.940 1.000

<60.0 0.420 0.420 0.550 Base Case +

TCVSC/PLUOOS/PROOS 60.0 0.450 0.450 0.510 0.690 0.770 0.770 0.820 0.877 0.950 0.970 1.000

<60.0 0.540 0.540 0.550 Base Case + 1 FWRV in Manual Mode 60.0 0.690 0.770 0.823 0.864 0.895 0.895 0.912 1.000

<60.0

COLR Dresden 2 Revision 21 Page 18 of 25 Table 5.5: LHGRFACf Multipliers - GNF3 (Reference [6])

Flow

(%)

LHGRFACf Multiplier TLO LHGRFACf Multiplier SLO 0.00 0.606 0.606 30.0 0.606 0.606 50.0 0.606 0.606 51.0 0.624 0.624 60.0 0.783 70.0 0.898 80.0 0.966 90.0 1.000 112.0 1.000 Table 5.6: LHGRFACf Multipliers - A10XM (Reference [6])

Flow

(%)

LHGRFACf Multiplier TLO LHGRFACf Multiplier SLO 0.00 0.429 0.429 30.0 0.535 0.535 50.0 0.606 0.606 51.0 0.624 0.624 60.0 0.783 70.0 0.898 80.0 0.966 90.0 1.000 112.0 1.000

COLR Dresden 2 Revision 21 Page 19 of 25

6. Control Rod Block Setpoints Technical Specification Sections 3.3.2.1 and 3.4.1 The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown in Table 6.1.

Table 6.1: Rod Block Monitor Upscale Instrumentation Setpoints (Reference [3])

ROD BLOCK MONITOR UPSCALE TRIP FUNCTION ALLOWABLE VALUE Two Recirculation Loop Operation 0.65 Wd + 55%

Single Recirculation Loop Operation 0.65 Wd + 51%

Wd - percent of recirculation loop drive flow required to produce a rated core flow of 98.0 Mlb/hr.

The setpoint may be lower/higher and will still comply with the CRWE analysis because CRWE is analyzed unblocked (Reference [6]).

COLR Dresden 2 Revision 21 Page 20 of 25

7. Stability Protection Setpoints Technical Specification Section 3.3.1.3 The OPRM PBDA Trip Settings are provided in Table 7.1.

Table 7.1: OPRM PBDA Trip Settings (Reference [6])

PBDA Trip Amplitude Setpoint (Sp)

Corresponding Maximum Confirmation Count Setpoint (Np) 1.10 13 The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system (Reference [6]).

The OPRM PBDA trip settings are based, in part, on the cycle specific OLMCPR and the power/flow dependent MCPR limits. Any change to the OLMCPR values and/or the power/flow dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA trip settings.

The OPRM PBDA trip settings are applicable when the OPRM system is declared operable, and the associated Technical Specifications are implemented.

COLR Dresden 2 Revision 21 Page 21 of 25

8. Modes of Operation 8.1. Allowable Modes The allowed modes of operation with equipment OOS and the associated thermal limit sets are as described in Table 8.1. See Table 8.2 for EOOS applicable power and flow restrictions. Common notes are provided in this section to expand on the applicability of the different modes of operation. All thermal limit sets in Table 8.1 have an option for TLO or SLO.

Table 8.1: Modes of Operation (Reference [6], [8])

EOOS Option

  • Thermal Limit Set **

Base Case BASE 1 TBVOOS (Common Note 3)

BASE 1 SRVOOS (Common Note 8)

BASE 1 MSIVOOS BASE 1 TCVOOS and/or 1 TSVOOS BASE FWHOOS/FFWTR (Common Note 2)

BASE 1 TCVSC PROOS PLUOOS PROOS PROOS PROOS 1 FWRV in Manual MANFRV TBSOOS (Common Note 4)

TBSOOS

  • The Base Case assumptions listed in Common Note 5 apply to all EOOS conditions.
    • Full thermal limit set names include designators for scram speed option and number of recirculation loops operating in addition to the EOOS option. The value listed under Thermal Limit Set corresponds to the EOOS option as it appears in the thermal limit set file name. To select the appropriate thermal limit set, the correct scram speed option and number of recirculation loops operating must also be selected.

COLR Dresden 2 Revision 21 Page 22 of 25 Table 8.2: Core Thermal Power and Flow Restrictions for EOOS Conditions (Reference [6], [8)))

EOOS Condition Core Flow (% of Rated)

Core Thermal Power (%

of Rated Power) 1 TCVOOS/TSVOOS*

N/A

< 75 1 MSIVOOS N/A 75 SLO 51 50 1 FWRV in Manual Mode N/A 38.5 (Pbypass)**

  • Operation with 1 TCVOOS and/or 1 TSVOOS is not allowed with TBSOOS.
    • Operation with 1 FWRV in manual mode in the fully closed position (e.g., startup and maintenance situations) is exempt from this scenario.

COLR Dresden 2 Revision 21 Page 23 of 25 8.2. Common Notes

1. All modes are allowed for operation at MELLLA, ICF, and coastdown subject to the power restrictions in Table 8.2. Coastdown is restricted to 40% rated power. Each OOS Option may be combined with each of the following conditions (Reference [12], [17]):
a. Up to 50% of the TIP channels OOS
b. Up to 25% of LPRMs OOS
2. For FWT reduction greater than 100°F, operation is restricted to equal or less than the 100% load line at rated power (Reference [13]). For off-rated conditions, see Table 1b of Reference [13] for FWT reduction.
3. The base case and EOOS limits and multipliers support operation with 8 of the 9 turbine bypass valves operational (i.e., one bypass valve out of service for both fast opening and pressure control opening) except for the TBSOOS condition, in which all bypass valves are inoperable. Use of the response curve in TRM Appendix H supports operation with any single TBV OOS. TRM Appendix H facilitates analysis with one valve OOS in that the capacity at 0.50 seconds from start of TSV closure is equivalent to the total capacity with eight out of the nine valves in service. The analyses also support Turbine Bypass flow of 29.8% of vessel rated steam flow, equivalent to one TBV OOS (or partially closed TBVs equivalent to one closed TBV), if the assumed opening profile for the remaining TBVs is met. If the opening profile is NOT met, or if the TBV system CANNOT pass an equivalent of 29.8% of vessel rated steam flow, utilize the TBSOOS condition (Reference [14]).
4. TBSOOS assumes that ALL the TBVs do not trip open on TCV fast closure or TSV closure and that ALL the TBVs are not capable of opening via the pressure control system (Reference [15]). Steam relief capacity is defined in Reference [14].
5. Base Case operation assumes:
a. 1 MSIVOOS at 75% rated power (Reference [6])
b. 1 TCVOOS and/or 1 TSVOOS at <75% rated power (Reference [6])
c. 1 SRVOOS (Reference [6])
d. 1 TBVOOS (the fast opening and pressure control opening both OOS) (Reference [6])
e. FWHOOS/FFWTR (Reference [6])
f. Operation with a feedwater temperature band of +10°F/-120°F (Reference [6])
6. Between 25% and 50% of rated thermal power, the PROOS thermal limit set ensures that the AOO acceptance criteria are met for a load rejection event if the 86 Device is OOS (Reference [18]).

Therefore, use the PROOS thermal limit set between 25% and 50% of rated thermal power if the 86 Device is OOS.

7. Stability BSP regions for Nominal FWT are only applicable from +10°F/-30°F and Stability BSP regions for Reduced FWT are applicable from +10°F/-120°F.
8. 1 SRVOOS is included as an operating flexibility condition in Base Case (Reference [6]), but is not an allowable condition per Reference [19].

COLR Dresden 2 Revision 21 Page 24 of 25

9. Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1. NEDE-24011-P-A, Revision 31, "General Electric Standard Application for Reactor Fuel," Global Nuclear Fuels, November 2020.
2. NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," GE Nuclear Energy, August 1996.
3. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
4. ANF-89-98(P)(A), Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
5. EMF-85-74(P), Revision 0 Supplement 1 (P)(A) and Supplement 2 (P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Siemens Power Corporation, February 1998.
6. BAW-10247PA, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors," AREVA NP, February 2008.
7. XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.
8. XN-NF-80-19(P)(A), Volume 4 Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.
9. XN-NF-80-19(P)(A), Volume 3 Revision 2, "Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.
10. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2," Siemens Power Corporation, October 1999.
11. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient ThermalHydraulic Core Analysis," Exxon Nuclear Company, February 1987.
12. EMF-2361(P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model," Framatome ANP, May 2001.
13. EMF-2292 (P)(A), Revision 0, "ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients,"

Siemens Power Corporation, September 2000.

14. NEDC-33930P, Revision 0, "GEXL98 Correlation for ATRIUM 10XM Fuel," Global Nuclear Fuels, February 2021.
15. 006N8642-P, Revision 1, "Justification of PRIME Methodologies for Evaluating TOP and MOP Compliance for non GNF Fuels," Global Nuclear Fuels, January 2022.

COLR Dresden 2 Revision 21 Page 25 of 25

10. References
1.

Constellation Energy Generation, LLC, Docket No. 50-237, Dresden Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-19.

2.

Framatome Document, ANP-3950P, Revision 0, Dresden Unit 2 Cycle 28 Reload Safety Analysis, August 2021.

3.

GE Document, GE DRF C51-00217-01, Instrument Setpoint Calculation Nuclear Instrumentation Rod Block Monitor, December 1999.

4.

Constellation Technical Specifications for Dresden 2 and 3, Section 5.6.5, Core Operating Limits Report (COLR).

5.

Constellation Technical Specifications for Dresden 2 and 3, Section 3.1.4, Control Rod Scram Times.

6.

GNF Document, 007N0406, Revision 0, Supplemental Reload Licensing Report for Dresden Unit 2 Reload 28 Cycle 29, September 2023.

7.

GNF Document, NEDC-33879P, Revision 4, GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR II), August 2020.

8.

GNF Document, 007N2988, Revision 0, GNF3 Fuel Design Cycle-Independent Analyses for Dresden Nuclear Power Station Units 2 & 3, August 2023.

9.

Framatome Document, FS1-0065975, Revision 1, "ATRIUM 10XM T-M Design Req and Operating Limits for DRE and QCI Transition Cycles, including 4th Cycle Operation," June 2023.

10. GE Document, Supplement to NEDO-24154 Revision 0, "Supplemental Safety Evaluation For The General Electric Topical Report Qualification Of The One-Dimensional Core Transient Model For Boiling Water Reactors NEDO-24154 and NEDE-24154P Volumes I, II and III," January 1981.
11. GNF Letter, DRF A12-00038-3 Volume 4, "Scram Times versus Notch Position," May 1992.
12. GNF Report, 005N6665, Revision 0, "Exelon BWR Fleetwide Technical Evaluation of 50% TIP Strings Out-of-Service on Methods Uncertainties," March 2020.
13. Constellation Letter, NF-MW:02-0081, Approval of GE Evaluation of Dresden and Quad Cities Extended Final Feedwater Temperature Reduction, August 2002.
14. Constellation TODI, NF230273, Revision 0, "Dresden Unit 2 Cycle 29 OPL-3," May 2023.
15. Constellation TODI, NF230174, Revision 0, "Dresden Unit 2 Cycle 29 FRED Form," April 2023.
16. GNF Document, 007N0407, Revision 0, Fuel Bundle Information Report for Dresden Unit 2 Reload 28 Cycle 29, September 2023.
17. GE Document, NEDC-32694P-A, Revision 0, Power Distribution Uncertainty for Safety Limit MCPR Evaluations, August 1999.
18. Constellation TODI, NF205973, Revision 1, Dresden GNF3 NFI DIR F0900 CycleIndependent Transient Analyses Input Transmittal to GNF, October 2022.
19. Constellation Technical Specifications for Dresden 2 and 3, Section 3.4.3, Safety and Relief Valves
Retrieved from "https://kanterella.com/w/index.php?title=ML24323A080&oldid=5458654"