RA-24-0058, Cycle 25 Core Operating Limits Report (COLR)
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|---|---|
| Site: | Brunswick  |
| Issue date: | 03/01/2024 |
| From: | Dewire M Duke Energy Progress |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
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| RA-24-0058 | |
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Text
March 1, 2024
U.S. Nuclear Regulatory Commission Page 2 of 2
Enclosure:
Brunswick Unit 1 Cycle 25 Core Operating Limits Report cc (with enclosure):
Ms. Laura Dudes, NRC Regional Administrator, Region II Mr. Luke Haeg, NRC Project Manager Mr. Gale Smith, NRC Senior Resident Inspector
RA-24-0058 Enclosure Brunswick Unit 1 Cycle 25 Core Operating Limits Report
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Applicable Facilities :
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Document Revision Number :
Document EC Number :
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Document Title :
Notes :
3/1/2024 Approver Lambert, Brad 2/29/2024 Reviewer Butler, Allen P 2/29/2024 Verifier Noel, Peter 2/29/2024 Originator Evans, Steve B1C25 CORE OPERATING LIMITS REPORT AD-NF-ALL-0807 000 BNEI-0400-0065 BNP BNP
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 1 BRUNSWICK UNIT 1, CYCLE 25 CORE OPERATING LIMITS REPORT March 2024 Prepared by:
[Signed Electronically]
Steve Evans Brunswick Nuclear Design Reviewed by:
[Signed Electronically]
Pete Noel Brunswick Nuclear Design Site Inspection by:
[Signed Electronically]
Brunswick Reactor Engineering Approved by:
[Signed Electronically]
Brad Lambert Manager, Brunswick Nuclear Design
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 2 Implementation Instructions for Revision 0 Revision Description Design Calculation 1B21-3021 Revision 0 documents the initial generation of the B1C25 Core Operating Limits Report in support of the B1C25 Reload Core Design.
Implementation Requirements The B1C25 COLR Revision 0 can be issued following the completion of core verification in accordance with AD-NF-BWR-0208.
Implementation Schedule The B1C25 COLR Revision 0 must be issued prior to entering MODE 2 for startup following the Unit 1 Spring 2024 refueling outage.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 3 LIST OF EFFECTIVE PAGES Page(s)
Revision 1-37 0
This document consists of 37 total pages.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 4 TABLE OF CONTENTS Subject Page Cover............................................................................................................................................... 1 Implementation Instructions for Revision 0....................................................................................... 2 List of Effective Pages...................................................................................................................... 3 Table of Contents............................................................................................................................. 4 List of Tables.................................................................................................................................... 5 List of Figures................................................................................................................................... 6 Nomenclature................................................................................................................................... 7 Introduction and Summary............................................................................................................... 9 APLHGR Limits.............................................................................................................................. 10 MCPR Limits.................................................................................................................................. 10 LHGR Limits................................................................................................................................... 11 CDA Setpoints................................................................................................................................ 11 RBM Setpoints............................................................................................................................... 12 Equipment Out-of-Service.............................................................................................................. 13 Single Loop Operation.................................................................................................................... 14 Inoperable Main Turbine Bypass System....................................................................................... 14 Feedwater Temperature Reduction................................................................................................ 15 References..................................................................................................................................... 16
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 5 CAUTION References to COLR Figures or Tables should be made using titles only; Figure and Table numbers may change from cycle to cycle.
LIST OF TABLES Table Title Page Table 1:
RBM System Setpoints................................................................................................. 18 Table 2:
RBM Operability Requirements..................................................................................... 19 Table 3.1: BSP Endpoints for Nominal Feedwater Temperature.................................................... 20 Table 3.2: BSP Endpoints for Reduced Feedwater Temperature................................................... 20 Table 3.3: ABSP Setpoints for the Scram Region......................................................................... 20 Table 4:
Exposure Basis for Brunswick Unit 1 Cycle 25 Transient Analysis................................ 21 Table 5:
Power-Dependent MCPRp Limits.................................................................................. 22 NSS Insertion Times Table 6:
Power-Dependent MCPRp Limits.................................................................................. 23 ESS Insertion Times Table 7:
Power-Dependent MCPRp Limits.................................................................................. 24 TSSS Insertion Times Table 8:
Flow-Dependent MCPRf Limits..................................................................................... 25 Table 9:
Framatome Fuel Steady-State LHGRSS Limits.............................................................. 26 Table 10: Framatome Fuel Power-Dependent LHGRFACp Multipliers.......................................... 27 NSS Insertion Times Table 11: Framatome Fuel Power-Dependent LHGRFACp Multipliers.......................................... 28 ESS Insertion Times Table 12: Framatome Fuel Power-Dependent LHGRFACp Multipliers.......................................... 29 TSSS Insertion Times Table 13: Framatome Fuel Flow-Dependent LHGRFACf Multipliers............................................. 30 Table 14: Framatome Fuel Steady-State MAPLHGRSS Limits....................................................... 31
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 6 CAUTION References to COLR Figures or Tables should be made using titles only; Figure and Table numbers may change from cycle to cycle.
LIST OF FIGURES Figure Title or Description Page Figure 1: MELLLA+ Power/Flow Map........................................................................................... 32 OPRM Operable, Two Loop Operation, 2923 MWt Figure 2: MELLLA+ Power/Flow Map........................................................................................... 33 OPRM Inoperable, Two Loop Operation, 2923 MWt Figure 3: MELLLA+ Power/Flow Map........................................................................................... 34 OPRM Operable, Single Loop Operation, 2923 MWt Figure 4: MELLLA+ Power/Flow Map........................................................................................... 35 OPRM Inoperable, Single Loop Operation, 2923 MWt Figure 5: MELLLA+ Power/Flow Map........................................................................................... 36 OPRM Operable, FWTR, 2923 MWt Figure 6: MELLLA+ Power/Flow Map........................................................................................... 37 OPRM Inoperable, FWTR, 2923 MWt
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 7 NOMENCLATURE 2PT Two Recirculation Pump Trip SLO Flow Uncertainty ABSP Automated Backup Stability Protection APLHGR Average Planar Linear Heat Generation Rate APRM Average Power Range Monitor (Subsystem)
ARTS APRM/RBM Technical Specification BEO-III Best-estimate Enhanced Option-III BOC Beginning of Cycle BSP Backup Stability Protection BWROG BWR Owners Group CAVEX Core Average Exposure CDA Confirmation Density Algorithm COLR Core Operating Limits Report CRWE Control Rod Withdrawal Error ECCS Emergency Core Cooling System EFPD Effective Full Power Day EOC End of Cycle EOCLB End of Cycle Licensing Basis EOFP End of Full Power EOOS Equipment Out-of-Service ESS Extended SCRAM Speed F
Flow (Total Core)
FHOOS Feedwater Heater Out-of-Service FFTR Final Feedwater Temperature Reduction FWTR Feedwater Temperature Reduction GE General Electric HFCL High Flow Control Line HPSP High Power Set Point HTSP High Trip Set Point ICF Increased Core Flow IPSP Intermediate Power Set Point ITSP Intermediate Trip Set Point LCO Limiting Condition of Operation LHGR Linear Heat Generation Rate LHGRSS Steady-State Maximum Linear Heat Generation Rate LHGRFAC Linear Heat Generation Rate Factor LHGRFACf Flow-Dependent Linear Heat Generation Rate Factor LHGRFACp Power-Dependent Linear Heat Generation Rate Factor LOCA Loss of Coolant Accident LPRM Local Power Range Monitor (Subsystem)
LPSP Low Power Set Point LTSP Low Trip Set Point
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 8 NOMENCLATURE (continued)
MAPLHGR Maximum Average Planar Linear Heat Generation Rate MAPLHGRSS Steady-State Maximum Average Planar Linear Heat Generation Rate MAPFAC Maximum Average Planar Linear Heat Generation Rate Factor MAPFACf Flow-Dependent Maximum Average Planar Linear Heat Generation Rate Factor MAPFACp Power-Dependent Maximum Average Planar Linear Heat Generation Rate Factor MAPFACSLO Maximum Average Planar Linear Heat Generation Rate Factor when in SLO MCE Maximum Core Exposure MCPR Minimum Critical Power Ratio MCPR99.9%
Cycle-specific safety limit MCPR that ensures at least 99.9% of fuel rods are not susceptible to boiling transition MCPRf Flow-Dependent Minimum Critical Power Ratio MCPRp Power-Dependent Minimum Critical Power Ratio MELLL Maximum Extended Load Line Limit MELLLA+
Maximum Extended Load Line Limit Analysis +
MEOD Maximum Extended Operating Domain MSIVOOS Main Steam Isolation Valve Out-of-Service N/A Not Applicable NCL Natural Circulation Line NEOC Near End of Cycle NFWT Nominal Feedwater Temperature NRC Nuclear Regulatory Commission NSS Nominal SCRAM Speed OLMCPR Operating Limit Minimum Critical Power Ratio OPRM Oscillation Power Range Monitor OOS Out-of-Service P
Power (Total Core Thermal)
PRNM Power Range Neutron Monitoring (System)
RBM Rod Block Monitor (Subsystem)
RDF Rated Drive Flow RFWT Reduced Feedwater Temperature RPT Recirculation Pump Trip RTP Rated Thermal Power SAD Amplitude Discriminator Setpoint SLO Single Loop Operation SRV Safety Relief Valve SRVOOS Safety Relief Valve Out-of-Service SS Steady-State STP Simulated Thermal Power TBV Turbine Bypass Valve TBVINS Turbine Bypass Valves In Service TBVOOS Turbine Bypass Valves Out-of-Service (all bypass valves OOS)
TIP Traversing Incore Probe TLO Two Loop Operation TS Technical Specification TSSS Technical Specification SCRAM Speed
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 9 CAUTION References to COLR Figures or Tables should be made using titles only; Figure and Table numbers may change from cycle to cycle.
Introduction and Summary The Brunswick Unit 1, Cycle 25 COLR provides values for the core operation limits and setpoints required by Technical Specifications (TS) 5.6.5.a.
Required Core Operating Limit (TS 5.6.5.a )
NRC Approved Methodology (TS 5.6.5.b)
Related TS Items
1, 6, 7, 26
TS 3.2.1 Limiting Condition for Operation (LCO) (APLHGR)
TS 3.4.1 LCO (Recirculation loops operating)
TS 3.7.6 LCO (Main Turbine Bypass out-of-service)
1, 6, 7, 8, 9, 11, 12, 13, 19, 22, 25
TS 3.4.1 LCO (Recirculation loops operating)
TS 3.7.6 LCO (Turbine bypass out-of-service)
3, 5, 6, 7, 8, 9, 12, 13, 20, 23, 24
TS 3.4.1 LCO (Recirculation loops operating)
TS 3.7.6 LCO (Turbine bypass out-of-service)
- 4. The Manual Backup Stability Protection (BSP) Scram Region (Region I), Manual BSP Controlled Entry Region (Region II),
the modified Average Power Range Monitor (APRM) Simulated Thermal Power
- High Scram setpoints used in the Automated BSP Scram Region, the BSP Boundary for TS 3.3.1.1.
18, 19, 22
TS Table 3.3.1.1-1, Function 2.f (OPRM Upscale)
TS 3.3.1.1, Condition I and J (Alternate instability detection)
- 5. The Allowable Values and power range setpoints for Rod Block Monitor (RBM)
Upscale Functions for TS 3.3.2.1.
6, 8
TS Table 3.3.2.1-1, Function 1 (RBM upscale and operability requirements)
The required core operating limits and setpoints listed in TS 5.6.5.a are presented in the COLR, have been determined using Nuclear Regulatory Commission (NRC) approved methodologies (COLR References 1 through 26) in accordance with TS 5.6.5.b, have considered all fuel types utilized in B1C25, and are established such that all applicable limits of the plant safety analysis are met in accordance with TS 5.6.5.c.
In addition to the TS required core operating limits and setpoints, this COLR also includes maps showing the allowable power/flow operating ranges including the stability ranges.
The generation of this COLR is documented in Reference 34 and is based on analysis results documented in References 31,32, and 33.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 10 APLHGR Limits Steady-state MAPLHGRSS limits are provided for Framatome Fuel (Table 14). These steady-state MAPLHGRSS limits must be modified as follows:
x Framatome Fuel MAPLHGR limits do not have a power, flow, or EOOS dependency.
x The applied MAPLHGR limit is dependent on the number of recirculation loops in operation. The steady-state MAPLHGR limit must be modified by a MAPFACSLO multiplier when in SLO.
The applied TLO and SLO MAPLHGR limits are determined as follows:
MAPLHGR LimitTLO = MAPLHGRSS MAPLHGR LimitSLO = MAPLHGRSS x MAPFACSLO where MAPFACSLO = 0.85 for ATRIUM 11 fuel Linear interpolation should be used to determine intermediate values between the values listed in the table.
MCPR Limits The MCPR limits presented in Tables 5 through 8 are based on the TLO and SLO MCPR99.9% values of 1.07 and 1.08, respectively, which meet the requirements of Technical Specification 2.1.1.2.
x MCPR limits have a core power and core flow dependency. Power-dependent MCPRp limits are presented in Tables 5 through 7 while flow-dependent MCPRf limits are presented in Table 8.
x Power-dependent MCPRP limits are dependent on CAVEX, SCRAM insertion speed, EOOS, fuel design, number of operating recirculation loops (i.e., TLO or SLO), core flow and core thermal power. Values for the CAVEX breakpoints are provided in Table 4. See COLR section titled Equipment Out-of-Service for a list of analyzed EOOS conditions. Care should be used when selecting the appropriate limits set.
x The MCPR limits are established such that they bound all pressurization and non-pressurization events.
x The power-dependent MCPRp limits (Tables 5-7) must be adjusted by an adder of +0.01 when in SLO.
The applied TLO and SLO MCPR limits are determined as follows:
MCPR LimitTLO = (MCPRp, MCPRf)max MCPR LimitSLO = (MCPRp + 0.01, MCPRf)max Linear interpolation should be used to determine intermediate values between the values listed in the tables. Some of the limits tables show step changes at 26.0%P and 50.0%P. IF performing a hand calculation of a limit AND the power is exactly on the breakpoint (i.e. 26.0 or 50.0), THEN select the most restrictive limit associated with the breakpoint.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 11 LHGR Limits Steady-state LHGRSS limits are provided for Framatome Fuel (Table 9). These steady-state LHGRSS limits must be modified as follows:
x Framatome Fuel LHGR limits have a core power and core flow dependency. Framatome Fuel power-dependent LHGRFACp multipliers (Tables 10-12) and flow-dependent LHGRFACf multipliers (Table 13) must be used to modify the steady-state LHGRSS limits (Table 9) for off-rated conditions.
x Framatome Fuel power-dependent LHGRFACp multipliers are dependent on CAVEX, SCRAM insertion speed, EOOS, fuel design, core flow and core thermal power. Values for the CAVEX breakpoints are provided in Table 4. See COLR section titled Equipment Out-of-Service for a list of analyzed EOOS conditions. Care should be used when selecting the appropriate multiplier set.
x The applied LHGR limit is not dependent on the number of operating recirculation loops. No adjustment to the LHGR limit is necessary for SLO.
The applied LHGR limit is determined as follows:
LHGR Limit = LHGRSS x (LHGRFACp, LHGRFACf)min Linear interpolation should be used to determine intermediate values between the values listed in the tables. Some of the limits tables show step changes at 26.0%P and 50.0%P. IF performing a hand calculation of a limit AND the power is exactly on the breakpoint (i.e. 26.0 or 50.0), THEN select the most restrictive limit associated with the breakpoint.
The cycle-specific off-rated flow dependent LHGR set-down bounds those assumed in the MELLLA+ plant-specific ECCS-LOCA analyses.
CDA Setpoints Brunswick has implemented the Best-estimate Enhanced Option-III (BEO-III) with the Confirmation Density Algorithm (CDA) stability solution using the Oscillation Power Range Monitor (OPRM) as described in References 19 and 22. The Detect and Suppress function of the BEO-III w/ CDA solution based on the OPRM system relies on the CDA, which constitutes the licensing basis. The Backup Stability Protection (BSP) solution described in Reference 22 may be used by the plant in the event the OPRM Upscale function is declared inoperable.
The safety evaluation (Reference 30) concluded that the BEO-III w/ CDA solution is acceptable subject to certain cycle-specific limitations and conditions (Reference 35). As described in Reference 33, these limitations and conditions are met for B1C25.
A reload BEO-III w/ CDA evaluation has been performed in accordance with References 19 and 22. The MCPR limits presented in Tables 5 through 8 bound the minimum stability MCPR values determined for B1C25 in the reload evaluation.
The SAD setpoint value of 1.10 is applicable to TLO and SLO.
Reference 22 describes two BSP options that are based on selected elements from three distinct constituents: BSP Manual Regions, BSP Boundary, and Automated BSP (ABSP) setpoints.
Reference 22 defines the BSP boundary as the MELLLA boundary. The Manual BSP region boundaries were validated for Brunswick Unit 1 Cycle 25 for nominal feedwater temperature operation and reduced feedwater temperature. The endpoints of the regions are defined in Table 3.1 and Table 3.2. The Manual BSP region boundary endpoints are calculated with the Reference 18 methodology and connected using the Generic Shape Function (GSF), which is described in Reference 29.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 12 The ABSP Average Power Range Monitor (APRM) Simulated Thermal Power (STP) setpoints associated with the ABSP Scram Region are determined for Cycle 25 and are defined in Table 3.3. These ABSP setpoints are applicable to both TLO and SLO as well as nominal and reduced feedwater temperature operation.
The Manual Backup Stability Protection (BSP) Regions I and II are documented on the Power/Flow maps as is the modified APRM Simulated Thermal Power (STP) high SCRAM setpoints and the BSP Boundary.
The power/flow maps (Figures 1-6) were validated for B1C25 based on Reference 33 using the Reference 22 methodology to facilitate operation under BEO-III w/ CDA as implemented by Function 2.f of Table 3.3.1.1-1 and LCO Conditions I and J of Technical Specification 3.3.1.1. The generation of these maps is documented in Reference 32. All maps illustrate the region of the power/flow map above 23% RTP and below 75% drive flow (correlated to core flow) where the OPRM system is required to be enabled. Figures 5 and 6 are the power/flow maps for use in FWTR.
The maps supporting an operable OPRM (Figures 1, 3 and 5) show a Scram Avoidance Region, which is not a licensing requirement but is an operator aid to illustrate where there is increased probability the OPRM system may generate a scram to avoid an instability event. Figures 2, 4, and 6 support an inoperable OPRM and highlight the Manual Backup Stability Regions I and II, the modified APRM STP high SCRAM setpoints, and the BSP Boundary. Note that the STP scram and rod block limits are defined in Technical Specifications, the Technical Requirements Manual, and/or Plant procedures, and are included in the COLR as an operator aid rather than a licensing requirement.
Figures 3 and 4 implement the corrective action for AR-217345217345which restricts reactor power to no more than 50% RTP when in SLO with OPRM operable or inoperable. This operator aid is intended to mitigate a spurious OPRM trip signal which could result from APRM noise while operating at high power levels.
RBM Setpoints The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation are presented in Table 1 and were determined to be consistent with the bases of the ARTS program (Reference 27). These setpoints will ensure the power-dependent MCPR limits will provide adequate protection against violation of the MCPR99.9% during a postulated CRWE event. Reference 31 revised these setpoints to reflect changes associated with the installation of the NUMAC PRNM system. RBM operability requirements, consistent with Notes (a) through (e) of Technical Specification Table 3.3.2.1-1, are provided in Table 2.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 13 Equipment Out-of-Service Brunswick Unit 1, Cycle 25 is analyzed for the following operating conditions with applicable MCPR, APLHGR and LHGR limits.
x Base Case Operation x
SLO x
TBVOOS x
FHOOS x
Combined TBVOOS and FHOOS Base Case Operation as well as the above-listed EOOS conditions assume all the items OOS below. These conditions are general analysis assumptions used to ensure conservative analysis results and were not meant to define specific EOOS conditions beyond those already defined in Technical Specifications.
x Any 1 inoperable SRV x
1 inoperable TBV (Note that for TBVOOS, TBVOOS/FHOOS, all 4 TBVs are assumed inoperable) x Up to 40% of the TIP channels OOS x
Up to 50% of the LPRMs OOS Please note that during FFTR/Coastdown, FHOOS is included in Base Case Operation, and TBVOOS.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 14 Single Loop Operation Brunswick Unit 1, Cycle 25 may operate in SLO up to a maximum core flow of 45 Mlbm/hr which corresponds to a maximum power level of 71.1% RTP with applicable MCPR, APLHGR and LHGR limits.
These power and flow limitations also apply when operating with jet pump loop flow mismatch conditions (LCO 3.4.1). The following must be considered when operating in SLO:
x SLO is not permitted with RFWT (FHOOS/FFTR).
x SLO is not permitted with TBVOOS.
x SLO is not permitted with MSIVOOS.
x SLO is not permitted within the MELLLA+ operating domain.
Various indicators on the Power/Flow Maps are provided not as operating limits but rather as a convenience for the operators. The purposes for some of these indicators are as follows:
x The SLO Entry Rod Line is shown on the TLO maps to avoid regions of instability in the event of a pump trip.
x A maximum core flow line is shown on the SLO maps to avoid vibration problems.
x APRM STP Scram and Rod Block nominal trip setpoint limits are shown at the estimated core flow corresponding to the actual drive flow-based setpoints to indicate where the Operator may encounter these setpoints (See LCO 3.3.1.1, Reactor Protection System Instrumentation Function 2.b: Average Power Range Monitors Simulated Thermal Power - High Allowable Value).
x When in SLO, Figures 3 and 4 implement the corrective action for AR-217345217345which restricts reactor power to no more than 50% RTP with OPRM operable or inoperable. This operator aid is intended to mitigate a spurious OPRM trip signal which could result from APRM noise while operating at high power levels.
x If OPRMs are inoperable in SLO, the expansion of the ABSP region results in power being restricted to 39% RTP as shown in Figure 4.
Inoperable Main Turbine Bypass System Brunswick Unit 1, Cycle 25 may operate with an inoperable Main Turbine Bypass System over the entire MEOD range and in the MELLLA+ domain for all cycle exposures with applicable APLHGR, MCPR and LHGR limits as specified in the COLR. An operable Main Turbine Bypass System with only one inoperable bypass valve was assumed in the development of the Base Case Operation limits. Base Case Operation is synonymous with TBVINS. The following must be considered when operating with TBVOOS:
x Two or more inoperable bypass valves renders the entire Main Turbine Bypass System inoperable requiring the use of TBVOOS limits. The TBVOOS analysis supports operation with all bypass valves inoperable.
x Prior to reaching the EOCLB exposure breakpoint, operDWLRQZLWK):75!)DQGUHDFWRUSRZHU
23% RTP requires use of the combined TBVOOS/FHOOS limits.
x TBVOOS operation coincident with FHOOS is supported using the combined TBVOOS/FHOOS limits.
x SLO is not permitted with TBVOOS.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 15 Feedwater Temperature Reduction Brunswick Unit 1, Cycle 25 may operate with RFWT over the entire MEOD range and cycle with applicable APLHGR, MCPR and LHGR limits as specified in the COLR. NFWT is defined as the range of feedwater temperatures from NFWT to NFWT - )1):7DQGits allowable variation were assumed in the development of the Base Case Operation limits. The FHOOS limits and FFTR/Coastdown limits were GHYHORSHGIRUDPD[LPXPIHHGZDWHUWHPSHUDWXUHUHGXFWLRQRI)7KHIROORZLQJPXVWEHFRQVLGHUHG
when operating with RFWT:
x Although the acronyms FWTR, FHOOS, RFWT and FFTR all involve reduced feedwater temperature, the use of FFTR is reserved for cycle energy extension using reduced feedwater temperature at and beyond a core average exposure of EOCLB using FFTR/Coastdown limits.
x 3ULRUWRUHDFKLQJWKH(2&/%H[SRVXUHEUHDNSRLQWRSHUDWLRQZLWK):75!)DQGUHDFWRUSRZHU
23% RTP requires use of the FHOOS limits.
x Until a core average exposure of EOCLB is reached, implementation of the FFTR/Coastdown limits is not required even if coastdown begins early.
x When operating with RFWT, the appropriate MELLLA+ Power/Flow Maps (Figures 5 and 6) must be used.
x FHOOS operation coincident with TBVOOS is supported using the combined TBVOOS/FHOOS limits.
x SLO is not permitted with RFWT.
x FWTR operation within the MELLLA+ operating domain is not allowed.
x NFWT limits have not been conservatively adjusted to eliminate the need to use RFWT limits below 50% RTP.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 16 References In accordance with Brunswick Unit 1 Technical Specification 5.6.5.b, the analytical methods for determining Brunswick Unit 1 core operating limits have been specifically reviewed and approved by the NRC and are listed as References 1 through 26.
- 1.
NEDE-24011-P-A, "GESTAR II - General Electric Standard Application for Reactor Fuel," and US Supplement, Revision 15, September 2005.
- 2.
XN-NF-81-58(P)(A) and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Revision 2, March 1984.
- 3.
XN-NF-85-67(P)(A), Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Revision 1, September 1986.
- 4.
EMF-85-74(P) Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Revision 0, February 1998.
- 5.
ANF-89-98(P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs, Revision 1, May 1995.
- 6.
XN-NF-80-19(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, March 1983.
- 7.
XN-NF-80-19(P)(A) Volume 4, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Revision 1, June 1986.
- 8.
EMF-2158(P)(A), Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Revision 0, October 1999.
- 9.
XN-NF-80-19(P)(A) Volume 3, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX:
Thermal Limits Methodology Summary Description, Revision 2, January 1987.
- 10. ANP-10333P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA), Revision 0, March 2018.
- 11. ANP-10307PA, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, Revision 0, June 2011.
- 12. ANP-10300P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios, Revision 1, January 2018.
- 13. ANF-1358(P)(A), The Loss of Feedwater Heating Transient in Boiling Water Reactors, Revision 3, September 2005.
- 14. EMF-2209(P)(A), SPCB Critical Power Correlation, Revision 3, September 2009.
- 15. EMF-2245(P)(A), Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Revision 0, August 2000.
- 16. EMF-2361(P)(A), EXEM BWR-2000 ECCS Evaluation Model, Revision 0, May 2001.
- 17. EMF-2292(P)(A), ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients, Revision 0, September 2000.
- 18. EMF-CC-074(P)(A) Volume 4, BWR Stability Analysis - Assessment of STAIF with Input from MICROBURN-B2, Revision 0, August 2000.
- 19. ANP-3703P, BEO-III Analysis Methodology for Brunswick Using RAMONA5-FA, Revision 0, August 2018.
- 20.
BAW-10247PA, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Revision 0, April 2008.
- 21. ANP-10298P-A, ACE/ATRIUM 10XM Critical Power Correlation, Revision 1, March 2014.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 17
- 22. DPC-NE-1009-P, Brunswick Nuclear Plant Implementation of Best-estimate Enhanced Option-III, Revision 0, September 2018
- 23. BAW-10247P-A, Supplement 2P-A, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 2: Mechanical Methods, Revision 0, August 2018
- 24. ANP-10340P-A, Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods, Revision 0, May 2018
- 25. ANP-10335P-A, ACE/ATRIUM 11 Critical Power Correlation, Revision 0, May 2018
- 26. ANP-10332P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios, Revision 0, March 2019.
- 27. NEDC-31654P, Maximum Extended Operating Domain Analysis for Brunswick Steam Electric Plant, February 1989.
- 28. Not Used.
- 29. OG02-0119-260, Backup Stability Protection (BSP) for Inoperable Option III Solution, July 2002.
- 30.
NRC Letter to Duke Energy Progress, LLC, Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendment Nos. 299 and 327 to Revise Technical Specification 5.6.5b to Allow Application of Advanced Framatome ATRIUM 11 Fuel Methodologies (EPID L-2018-LLA-0273), dated March 6, 2020 (ADAMS Accession No. ML20073F186).
- 31. BNP Design Calculation 1C51-0001, Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (1-C51-APRM-1 through 4 Loops and 1-C51 RBM-A and B Loops), Revision 4, September 2018.
- 32. BNP Design Calculation 0B21-2045, BNP Power/Flow Maps for MELLLA+, Revision 2, January 2020.
- 33. ANP-4078P, Brunswick Unit 1 Cycle 25 Reload Safety Analysis, Revision 0, February 2024.
- 34. BNP Design Calculation 1B21-3021, Preparation of the B1C25 Core Operating Limits Report, Revision 0, February 2024.
- 35.
NRC E-mail Capture, Request for Additional Information - Brunswick ATRIUM 11 LAR, (ADAMS Accession Number ML19283C829), October 9, 2019.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 18 Table 1 RBM System Setpoints1 Setpoint a Setpoint Value Allowable Value Lower Power Setpoint (LPSPb)
< 27.7
< 29.0 Intermediate Power Setpoint (IPSPb)
< 62.7
< 64.0 High Power Setpoint (HPSPb)
< 82.7
< 84.0 Low Trip Setpoint (LTSPc,d)
< 120.1
< 120.6 Intermediate Trip Setpoint (ITSPc,d)
< 115.1
< 115.6 High Trip Setpoint (HTSPc,d)
< 110.3
< 110.8 RBM Time Delay (td2) 0 seconds
< 2.0 seconds a
See Table 2 for RBM Operability Requirements.
b Setpoints in percent of Rated Thermal Power.
c Setpoints relative to a full scale reading of 125. For example, < 120.1 means
< 120.1/125.0 of full scale.
d Trip setpoints and allowable values are based on a HTSP Analytical Limit of 113.2 with RBM filter.
1 This table is referred to by Technical Specification 3.3.2.1 (Table 3.3.2.1-1) and 5.6.5.a.5.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 19 Table 2 RBM Operability Requirements2 IF the following conditions are met, THEN RBM Not Required Operable Thermal Power
(% rated)
DQG
65 TLO
7 SLO
42 TLO 2
Requirements valid for all fuel designs, all SCRAM insertion times and all core average exposure ranges.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 20 Table 3.1 BSP Endpoints for Nominal Feedwater Temperature3,4 Endpoint Power
(%)
Flow
(%)
Definition A1 57.0 40.6 Scram Region Boundary, HFCL B1 42.0 31.7 Scram Region Boundary, NCL A2 64.5 50.0 Controlled Entry Region Boundary, HFCL B2 28.9 31.9 Controlled Entry Region Boundary, NCL Table 3.2 BSP Endpoints for Reduced Feedwater Temperature3,4 Endpoint Power
(%)
Flow
(%)
Definition A1 65.9 51.8 Scram Region Boundary, HFCL B1 36.5 31.9 Scram Region Boundary, NCL A2 69.8 56.8 Controlled Entry Region Boundary, HFCL B2 28.9 31.9 Controlled Entry Region Boundary, NCL Table 3.3 ABSP Setpoints for the Scram Region3,5 Parameter Symbol Value Slope of ABSP APRM flow-biased trip linear segment.
mTRIP 2.00 %RTP/%RDF ABSP APRM flow-biased trip setpoint power intercept. Constant Power Line for Trip from zero Drive Flow to Flow Breakpoint value.
PBSP-TRIP 42.0 %RTP ABSP APRM flow-biased trip setpoint drive flow intercept. Constant Flow Line for Trip.
WBSP-TRIP
5')
Flow Breakpoint value WBSP-BREAK 25.0 %RDF 3
These tables are referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-1) and 5.6.5.a.4.
4 The BSP Boundary for Nominal and Reduced Feedwater Temperature is defined by the MELLLA boundary line and extends from the natural circulation boundary to rated power.
5 When in SLO the ABSP STP Scram is modified by the applied SLO W as shown in Figure 4.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 21 Table 4 Exposure Basis6 for Brunswick Unit 1 Cycle 25 Transient Analysis Core Average Exposure (MWd/MTU)
Comments 33,017 Breakpoint for exposure dependent MCPRp limits (NEOC) 36,825 Design basis rod patterns to EOFP + 15 EFPD (EOCLB) 38,260 End of cycle with FFTR/Coastdown -
Maximum Core Exposure (MCE) 6 The exposure basis for the defined break points is the core average exposure (CAVEX) values shown above regardless of the actual BOC CAVEX value of the As-Loaded Core.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 22 Table 5 Power-Dependent MCPRp Limits7 NSS Insertion Times EOOS Condition Power
(% rated)
BOC to < NEOC MCPRp BOC to < EOCLB MCPRp BOC to < MCE8 (FFTR/Coastdown)
MCPRp 100.0 1.35 1.37 1.37 90.0 1.38 1.40 1.40 Base case operation 50.0 50.0 26.0 1.56
> 65%F 65%F 1.89 1.66 2.22 1.96 1.58
> 65%F 65%F 1.89 1.66 2.22 1.96 1.62
> 65%F 65%F 1.89 1.66 2.22 1.96 26.0 2.43 2.43 2.43 2.43 2.52 2.51 23.0 2.44 2.43 2.44 2.43 2.57 2.53 100.0 1.40 1.42 1.43 90.0 1.42 1.48 1.48 50.0 1.71 1.71 1.77 TBVOOS 50.0
> 65%F 65%F 1.89 1.66
> 65%F 65%F 1.89 1.66
> 65%F 65%F 1.89 1.66 26.0 2.22 1.96 2.22 1.96 2.22 1.96 26.0 2.94 2.87 2.94 2.87 3.10 2.88 23.0 3.13 2.87 3.13 2.87 3.18 2.97 100.0 1.35 1.37 90.0 1.38 1.40 50.0 1.60 1.62 FHOOS 50.0
> 65%F 65%F 1.89 1.66
> 65%F 65%F 1.89 1.66 26.0 2.22 1.96 2.22 1.96 26.0 2.52 2.51 2.52 2.51 23.0 2.57 2.53 2.57 2.53 100.0 1.40 1.43 90.0 1.44 1.48 50.0 1.73 1.77 TBVOOS FHOOS 50.0
> 65%F 65%F 1.89 1.66
> 65%F 65%F 1.89 1.66 26.0 2.22 1.96 2.22 1.96 26.0 3.10 2.88 3.10 2.88 23.0 3.18 2.97 3.18 2.97 7
Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.01. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.
FHOOS not permitted in the MELLLA+ domain.
8 BOC to < MCE limits include FFTR/FHOOS and bound operation with NFWT.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 23 Table 6 Power-Dependent MCPRp Limits9 ESS Insertion Times EOOS Condition Power
(% rated)
BOC to < NEOC MCPRp BOC to < EOCLB MCPRp BOC to < MCE10 (FFTR/Coastdown)
MCPRp 100.0 1.36 1.37 1.39 90.0 1.38 1.40 1.40 Base case operation 50.0 50.0 26.0 1.56
> 65%F 65%F 1.89 1.66 2.22 1.96 1.58
> 65%F 65%F 1.89 1.66 2.22 1.96 1.62
> 65%F 65%F 1.89 1.66 2.22 1.96 26.0 2.43 2.43 2.43 2.43 2.52 2.51 23.0 2.44 2.43 2.44 2.43 2.57 2.53 100.0 1.41 1.44 1.46 90.0 1.42 1.48 1.48 50.0 1.71 1.71 1.77 TBVOOS 50.0
> 65%F 65%F 1.89 1.66
> 65%F 65%F 1.89 1.66
> 65%F 65%F 1.89 1.66 26.0 2.22 1.96 2.22 1.96 2.22 1.96 26.0 2.94 2.87 2.94 2.87 3.10 2.88 23.0 3.13 2.87 3.13 2.87 3.18 2.97 100.0 1.36 1.39 90.0 1.38 1.40 50.0 1.60 1.62 FHOOS 50.0
> 65%F 65%F 1.89 1.66
> 65%F 65%F 1.89 1.66 26.0 2.22 1.96 2.22 1.96 26.0 2.52 2.51 2.52 2.51 23.0 2.57 2.53 2.57 2.53 100.0 1.41 1.46 90.0 1.44 1.48 50.0 1.73 1.77 TBVOOS FHOOS 50.0
> 65%F 65%F 1.89 1.66
> 65%F 65%F 1.89 1.66 26.0 2.22 1.96 2.22 1.96 26.0 3.10 2.88 3.10 2.88 23.0 3.18 2.97 3.18 2.97 9
Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.01. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.
FHOOS not permitted in the MELLLA+ domain.
10 BOC to < MCE limits include FFTR/FHOOS and bound operation with NFWT.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 24 Table 7 Power-Dependent MCPRp Limits11 TSSS Insertion Times EOOS Condition Power
(% rated)
BOC to < NEOC MCPRp BOC to < EOCLB MCPRp BOC to < MCE12 (FFTR/Coastdown)
MCPRp 100.0 1.43 1.51 1.51 90.0 1.46 1.51 1.51 Base case operation 50.0 50.0 26.0 1.73
> 65%F 65%F 1.89 1.66 2.22 1.96 1.73
> 65%F 65%F 1.89 1.66 2.22 1.96 1.73
> 65%F 65%F 1.89 1.66 2.22 1.96 26.0 2.43 2.43 2.43 2.43 2.52 2.51 23.0 2.44 2.43 2.44 2.43 2.57 2.53 100.0 1.51 1.58 1.58 90.0 1.52 1.58 1.58 50.0 1.82 1.82 1.90 TBVOOS 50.0
> 65%F 65%F 1.89 1.70
> 65%F 65%F 1.89 1.70
> 65%F 65%F 1.90 1.82 26.0 2.22 1.98 2.22 1.98 2.22 2.04 26.0 2.94 2.87 2.94 2.87 3.10 2.88 23.0 3.13 2.87 3.13 2.87 3.18 2.97 100.0 1.43 1.51 90.0 1.46 1.51 50.0 1.73 1.73 FHOOS 50.0
> 65%F 65%F 1.89 1.66
> 65%F 65%F 1.89 1.66 26.0 2.22 1.96 2.22 1.96 26.0 2.52 2.51 2.52 2.51 23.0 2.57 2.53 2.57 2.53 100.0 1.51 1.58 90.0 1.52 1.58 50.0 1.90 1.90 TBVOOS FHOOS 50.0
> 65%F 65%F 1.90 1.82
> 65%F 65%F 1.90 1.82 26.0 2.22 2.04 2.22 2.04 26.0 3.10 2.88 3.10 2.88 23.0 3.18 2.97 3.18 2.97 11 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.01. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.
FHOOS not permitted in the MELLLA+ domain.
12 BOC to < MCE limits include FFTR/FHOOS and bound operation with NFWT.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 25 Table 8 Flow-Dependent MCPRf Limits13 Core Flow ATRIUM 11
(% of rated)
MCPRf 0.0 1.69 31.0 1.69 50.0 1.40 65.0 1.34 107.0 1.34 13 Limits valid for all SCRAM insertion times, all core average exposure ranges, all EOOS scenarios, and both TLO &
SLO.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 26 Table 9 Framatome Fuel Steady-State LHGRSS Limits Peak ATRIUM 11 Pellet Exposure LHGR (GWd/MTU)
(kW/ft) 0.0 13.6 21.0 13.6 53.0 10.2 80.0 3.5
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 27 Table 10 Framatome Fuel Power-Dependent LHGRFACp Multipliers14 NSS Insertion Times EOOS Condition Power
(% rated)
BOC to < EOCLB LHGRFACp BOC to < MCE15 (FFTR/Coastdown)
LHGRFACp 100.0 1.00 1.00 90.0 1.00 1.00 Base case operation 50.0 50.0 26.0 1.00
> 65%F 65%F 0.89 0.97 0.63 0.75 0.95
> 65%F 65%F 0.89 0.97 0.63 0.75 26.0 0.46 0.47 0.44 0.46 23.0 0.46 0.47 0.43 0.45 100.0 1.00 1.00 90.0 1.00 1.00 50.0 0.98 0.92 TBVOOS 50.0
> 65%F 65%F 0.89 0.97
> 65%F 65%F 0.89 0.97 26.0 0.63 0.75 0.63 0.75 26.0 0.40 0.47 0.37 0.44 23.0 0.37 0.42 0.35 0.40 100.0 1.00 90.0 1.00 50.0 0.95 FHOOS 50.0
> 65%F 65%F 0.89 0.97 26.0 0.63 0.75 26.0 0.44 0.46 23.0 0.43 0.45 100.0 1.00 90.0 1.00 50.0 0.92 TBVOOS
> 65%F 65%F FHOOS 50.0 0.89 0.97 26.0 0.63 0.75 26.0 0.37 0.44 23.0 0.35 0.40 14 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. FHOOS not permitted in the MELLLA+
domain.
15 BOC to < MCE limits include FFTR/FHOOS and bound operation with NFWT.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 28 Table 11 Framatome Fuel Power-Dependent LHGRFACp Multipliers16 ESS Insertion Times EOOS Condition Power
(% rated)
BOC to < EOCLB LHGRFACp BOC to < MCE17 (FFTR/Coastdown)
LHGRFACp 100.0 1.00 1.00 90.0 1.00 1.00 Base case operation 50.0 50.0 26.0 1.00
> 65%F 65%F 0.89 0.97 0.63 0.75 0.95
> 65%F 65%F 0.89 0.97 0.63 0.75 26.0 0.46 0.47 0.44 0.46 23.0 0.46 0.47 0.43 0.45 100.0 1.00 1.00 90.0 1.00 1.00 50.0 0.98 0.92 TBVOOS 50.0
> 65%F 65%F 0.89 0.97
> 65%F 65%F 0.89 0.97 26.0 0.63 0.75 0.63 0.75 26.0 0.40 0.47 0.37 0.44 23.0 0.37 0.42 0.35 0.40 100.0 1.00 90.0 1.00 50.0 0.95 FHOOS 50.0
> 65%F 65%F 0.89 0.97 26.0 0.63 0.75 26.0 0.44 0.46 23.0 0.43 0.45 100.0 1.00 90.0 1.00 50.0 0.92 TBVOOS
> 65%F 65%F FHOOS 50.0 0.89 0.97 26.0 0.63 0.75 26.0 0.37 0.44 23.0 0.35 0.40 16 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. FHOOS not permitted in the MELLLA+
domain.
17 BOC to < MCE limits include FFTR/FHOOS and bound operation with NFWT.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 29 Table 12 Framatome Fuel Power-Dependent LHGRFACp Multipliers18, 19 TSSS Insertion Times EOOS Condition Power
(% rated)
BOC to < EOCLB LHGRFACp BOC to < MCE20 (FFTR/Coastdown)
LHGRFACp 100.0 1.00 1.00 90.0 Base case operation 50.0 50.0 26.0 0.97
> 65%F 65%F 0.89 0.97 0.63 0.75 0.92
> 65%F 65%F 0.89 0.97 0.63 0.75 26.0 0.46 0.47 0.44 0.46 23.0 0.46 0.47 0.43 0.45 100.0 1.00 0.99 90.0 50.0 0.92 0.87 TBVOOS 50.0
> 65%F 65%F 0.89 0.97
> 65%F 65%F 0.87 0.97 26.0 0.63 0.75 0.63 0.75 26.0 0.40 0.47 0.37 0.44 23.0 0.37 0.42 0.35 0.40 100.0 1.00 90.0 50.0 0.92 FHOOS 50.0
> 65%F 65%F 0.89 0.97 26.0 0.63 0.75 26.0 0.44 0.46 23.0 0.43 0.45 100.0 0.99 90.0 50.0 0.87 TBVOOS
> 65%F 65%F FHOOS 50.0 0.87 0.97 26.0 0.63 0.75 26.0 0.37 0.44 23.0 0.35 0.40 18 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. FHOOS not permitted in the MELLLA+
domain.
19 -- indicates that the fuel limit has no breakpoint at this exposure.
20 BOC to < MCE limits include FFTR/FHOOS and bound operation with NFWT.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 30 Table 13 Framatome Fuel Flow-Dependent LHGRFACf Multipliers21 Core Flow ATRIUM 11
(% of rated)
LHGRFACf 0.0 0.52 31.0 0.52 75.0 1.00 107.0 1.00 21 Multipliers valid for all SCRAM insertion times and all core average exposure ranges.
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design Design Calc. No. 1B21-3021 Rev 0 B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Page 31 Table 14 Framatome Fuel Steady-State MAPLHGRSS Limits22, 23 Average Planar ATRIUM 11 Exposure MAPLHGR (GWd/MTU)
(kW/ft) 0.0 12.0 20.0 12.0 60.0 9.0 69.0 7.2 22 Framatome Fuel MAPLHGR limits do not have a power, flow, or EOOS dependency.
23 ATRIUM 11 MAPLHGR limits must be adjusted by a 0.85 multiplier when in SLO. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.
Figure 1 MELLLA+ Power/Flow Map OPRM Operable, Two Loop Operation, 2923 MWt
Reference:
0B21-2045, Revision 2 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4
% Power Mlbs/hr Core Flow This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 I
C F
R e
g i
o n
APRM STP Scram APRM STP Rod Block 0
10 20 30 40 50 60 70 80 90 100 110 120
% Core Flow Minimum Power Line Natural Circulation Line 35% Approximate Minimum Pump Speed SLO Entry Rod Line Scram Avoidance Region MELLLA+ Line Power Minimum (MELLLA)
Core Flow Mlbs/hr Minimum (MELLLA+)
Core Flow Mlbs/hr Maximum (ICF)
Core Flow Mlbs/hr 100 76.19 65.45 80.47 99 75.04 64.42 80.47 98 73.89 63.39 80.47 97 72.75 62.35 80.47 96 71.61 61.32 80.47 95 70.49 60.29 80.47 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 91 66.03 56.16 80.47 90 64.93 55.13 80.47 89 63.83 54.10 80.47 88 62.74 53.06 80.47 87 61.66 52.03 80.51 86 60.58 51.00 80.60 85 59.50 49.97 80.69 84 58.43 48.94 80.79 83 57.37 47.90 80.90 82 56.31 46.87 81.05 81 55.25 45.84 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 78 52.12 42.74 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 69 42.94 83.06 68 41.94 83.22 67 40.95 83.37 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 62 36.04 84.14 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 OPRM Enabled Region MELLLA Line and BSP Boundary Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Design Calc. No. 1B21-3021 Rev. 0 Page 32
Figure 2 MELLLA+ Power/Flow Map OPRM Inoperable, Two Loop Operation, 2923 MWt
Reference:
0B21-2045, Revision 2 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4
% Power Power Minimum (MELLLA)
Core Flow Mlbs/hr Minimum (MELLLA+)
Core Flow Mlbs/hr Maximum (ICF)
Core Flow Mlbs/hr 100 76.19 65.45 80.47 99 75.04 64.42 80.47 98 73.89 63.39 80.47 97 72.75 62.35 80.47 96 71.61 61.32 80.47 95 70.49 60.29 80.47 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 91 66.03 56.16 80.47 90 64.93 55.13 80.47 89 63.83 54.10 80.47 88 62.74 53.06 80.47 87 61.66 52.03 80.51 86 60.58 51.00 80.60 85 59.50 49.97 80.69 84 58.43 48.94 80.79 83 57.37 47.90 80.90 82 56.31 46.87 81.05 81 55.25 45.84 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 78 52.12 42.74 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 69 42.94 83.06 68 41.94 83.22 67 40.95 83.37 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 62 36.04 84.14 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 Mlbs/hr Core Flow This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 I
C F
R e
g i
o n
APRM STP Scram APRM STP Rod Block 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Minimum Power Line Natural Circulation Line 35% Approximate Minimum Pump Speed SLO Entry Rod Line Region I - Manual Scram Region II - Controlled Entry ABSP STP Scram ABSP STP Rod Block Operator Awareness MELLLA Line and BSP Boundary OPRM Enabled Region MELLLA+ Line Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Design Calc. No. 1B21-3021 Rev. 0 Page 33
Figure 3 MELLLA+ Power/Flow Map OPRM Operable, Single Loop Operation, 2923 MWt
Reference:
0B21-2045, Revision 2 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4
% Power Mlbs/hr Core Flow This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 I
C F
R e
g i
o n
APRM STP Scram APRM STP Rod Block 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Minimum Power Line Natural Circulation Line 35% Approximate Minimum Pump Speed MELLLA Line and BSP Boundary Scram Avoidance Region Power Minimum (MELLLA)
Core Flow Mlbs/hr Minimum (MELLLA+)
Core Flow Mlbs/hr Maximum (ICF)
Core Flow Mlbs/hr 100 76.19 65.45 80.47 99 75.04 64.42 80.47 98 73.89 63.39 80.47 97 72.75 62.35 80.47 96 71.61 61.32 80.47 95 70.49 60.29 80.47 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 91 66.03 56.16 80.47 90 64.93 55.13 80.47 89 63.83 54.10 80.47 88 62.74 53.06 80.47 87 61.66 52.03 80.51 86 60.58 51.00 80.60 85 59.50 49.97 80.69 84 58.43 48.94 80.79 83 57.37 47.90 80.90 82 56.31 46.87 81.05 81 55.25 45.84 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 78 52.12 42.74 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 69 42.94 83.06 68 41.94 83.22 67 40.95 83.37 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 62 36.04 84.14 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 OPRM Enabled Region MELLLA+ Line (MELLLA+ Operations prohibited during SLO) 45 Mlb/hr Max Core Flow Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Design Calc. No. 1B21-3021 Rev. 0 Page 34
Figure 4 MELLLA+ Power/Flow Map OPRM Inoperable, Single Loop Operation, 2923 MWt
Reference:
0B21-2045, Revision 2 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4
% Power Power Minimum (MELLLA)
Core Flow Mlbs/hr Minimum (MELLLA+)
Core Flow Mlbs/hr Maximum (ICF)
Core Flow Mlbs/hr 100 76.19 65.45 80.47 99 75.04 64.42 80.47 98 73.89 63.39 80.47 97 72.75 62.35 80.47 96 71.61 61.32 80.47 95 70.49 60.29 80.47 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 91 66.03 56.16 80.47 90 64.93 55.13 80.47 89 63.83 54.10 80.47 88 62.74 53.06 80.47 87 61.66 52.03 80.51 86 60.58 51.00 80.60 85 59.50 49.97 80.69 84 58.43 48.94 80.79 83 57.37 47.90 80.90 82 56.31 46.87 81.05 81 55.25 45.84 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 78 52.12 42.74 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 69 42.94 83.06 68 41.94 83.22 67 40.95 83.37 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 62 36.04 84.14 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 Mlbs/hr Core Flow This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 I
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APRM STP Scram 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Minimum Power Line Natural Circulation Line 35% Approximate Minimum Pump Speed Region I - Manual Scram Region II - Controlled Entry ABSP STP Scram ABSP STP Rod Block APRM STP Rod Block 45 Mlb/hr Max Core Flow Operator Awareness MELLLA Line and BSP Boundary OPRM Enabled Region MELLLA+ Line (MELLLA+ Operations prohibited during SLO)
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Design Calc. No. 1B21-3021 Rev. 0 Page 35
Figure 5 MELLLA+ Power/Flow Map OPRM Operable, FWTR, 2923 MWt
Reference:
0B21-2045, Revision 2 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4
% Power Mlbs/hr Core Flow This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 I
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APRM STP Scram APRM STP Rod Block 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Minimum Power Line Natural Circulation Line 35% Approximate Minimum Pump Speed SLO Entry Rod Line (SLO prohibited during FWTR)
MELLLA Line and BSP Boundary Scram Avoidance Region Power Minimum (MELLLA)
Core Flow Mlbs/hr Minimum (MELLLA+)
Core Flow Mlbs/hr Maximum (ICF)
Core Flow Mlbs/hr 100 76.19 65.45 80.47 99 75.04 64.42 80.47 98 73.89 63.39 80.47 97 72.75 62.35 80.47 96 71.61 61.32 80.47 95 70.49 60.29 80.47 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 91 66.03 56.16 80.47 90 64.93 55.13 80.47 89 63.83 54.10 80.47 88 62.74 53.06 80.47 87 61.66 52.03 80.51 86 60.58 51.00 80.60 85 59.50 49.97 80.69 84 58.43 48.94 80.79 83 57.37 47.90 80.90 82 56.31 46.87 81.05 81 55.25 45.84 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 78 52.12 42.74 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 69 42.94 83.06 68 41.94 83.22 67 40.95 83.37 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 62 36.04 84.14 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 OPRM Enabled Region MELLLA+ Line (MELLLA+ Operations prohibited during FWTR)
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Design Calc. No. 1B21-3021 Rev. 0 Page 36
Figure 6 MELLLA+ Power/Flow Map OPRM Inoperable, FWTR, 2923 MWt
Reference:
0B21-2045, Revision 2 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4
% Power Power Minimum (MELLLA)
Core Flow Mlbs/hr Minimum (MELLLA+)
Core Flow Mlbs/hr Maximum (ICF)
Core Flow Mlbs/hr 100 76.19 65.45 80.47 99 75.04 64.42 80.47 98 73.89 63.39 80.47 97 72.75 62.35 80.47 96 71.61 61.32 80.47 95 70.49 60.29 80.47 94 69.36 59.26 80.47 93 68.25 58.22 80.47 92 67.13 57.19 80.47 91 66.03 56.16 80.47 90 64.93 55.13 80.47 89 63.83 54.10 80.47 88 62.74 53.06 80.47 87 61.66 52.03 80.51 86 60.58 51.00 80.60 85 59.50 49.97 80.69 84 58.43 48.94 80.79 83 57.37 47.90 80.90 82 56.31 46.87 81.05 81 55.25 45.84 81.21 80 54.20 44.81 81.36 79 53.16 43.77 81.51 78 52.12 42.74 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 69 42.94 83.06 68 41.94 83.22 67 40.95 83.37 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 62 36.04 84.14 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 Mlbs/hr Core Flow This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 I
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APRM STP Scram APRM STP Rod Block 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Minimum Power Line Natural Circulation Line 35% Approximate Minimum Pump Speed Region I - Manual Scram Region II - Controlled Entry ABSP STP Scram Operator Awareness MELLLA Line and BSP Boundary OPRM Enabled Region MELLLA+ Line (MELLLA+ Operations prohibited during FWTR)
ABSP STP Rod Block SLO Entry Rod Line (SLO prohibited during FWTR)
Duke Energy, Nuclear Fuels Engineering, Fuel Management and Design B1C25 Core Operating Limits Report, BNEI-0400-0065 Rev. 0 Design Calc. No. 1B21-3021 Rev. 0 Page 37