RA11-016, Cycle 14 Core Operating Limits Report (COLR)
| ML110590447 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/25/2011 |
| From: | Rhoades D Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA11-016 | |
| Download: ML110590447 (22) | |
Text
Nuclear LaSalle Generating Station www.exeloncorp.com 2601 North 21st Road Marseilles, I L 61341-9757 RA11-016 10CFR50.59 February 25, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Unit 2 Facility Operating License No. NPF-18 NRC Docket No. 50-374
Subject:
Unit 2 Cycle 14 Core Operating Limits Report (COLR)
The purpose of this letter is to advise you of the Exelon Generation Company, LLC (EGC) review and approval of the LaSalle Unit 2 Cycle 14 reload under the provisions of 10 CFR 50.59, "Changes, tests and experiments," and to transmit the Core Operating Limits Report (COLR) for Cycle 14, consistent with Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits From Technical Specifications." This report is being submitted in accordance with LaSalle County Station Technical Specification (TS) 5.6.5, "Core Operating Limits (COLR)," item d.
The reload licensing analyses performed for Cycle 14 utilized NRC approved methodologies.
The Unit 2 Cycle 14 core, which consists of NRC approved fuel designs developed by AREVA NP Inc., was designed to operate within approved fuel design criteria provided in the Technical Specifications and related TS Bases. The core operating characteristics are bounded by the Updated Final Safety Analysis Report (UFSAR) allowable limits.
EGC has performed a review of the relevant reload licensing documents, associated TS Bases, and references in accordance with 10, CFR 50.59. This review concluded that the reload does not require NRC review and approval.
Should you have any questions concerning this submittal, please contact Mr. Terrence W.
Simpkin, Regulatory Assurance Manager, at (815) 415-2800.
Respectfully, David P. Rhoades Site Vice President LaSalle County Station Attachment cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - LaSalle County Station
bcc:
Phillip Hansett (w/o attachment)
Gary Benes (w/o attachment)
Frank Trikur (NFM) (w/o attachment)
NRC Project Manager - NRR (Stephen Sands)
DCD Licensing (hard copy and electronic)
Correspondence file (J. Houston)
COLR LaSalle 2 Revision 7 Core Operating Limits Report for LaSalle Unit 2 Cycle 14 LaSalle Unit 2 Cycle 14 Page 1 of 20
COLR LaSalle 2 Revision 7 Table of Contents
- 1. References..................................................................................................................4
- 2. Terms and Definitions..................................................................................................5
- 3. General Information..................................................................................................... 6
- 4. Average Planar Linear Heat Generation Rate............................................................. 7
- 5. Operating Limit Minimum Critical Power Ratio............................................................ 8 5.1. Manual Flow Control MCPR Limits.......................................................................8 5.1.1. Power-Dependent MCPR............................................................................... 8 5.1.2. Flow-Dependent MCPR.................................................................................. 8 5.2. Automatic Flow Control MCPR Limits................................................................... 8 5.3. Scram Time..........................................................................................................8 5.4. Recirculation Flow Control Valve Settings............................................................ 8
- 6. Linear Heat Generation Rate.....................................................................................12
- 7. Rod Block Monitor.....................................................................................................16
- 8. Traversing In-Core Probe System.............................................................................17 8.1. Description..........................................................................................................17 8.2. Bases..................................................................................................................17
- 9. Stability Protection Setpoints....................................................................................18
- 10. Modes of Operation.................................................................................................19
- 11. Methodology............................................................................................................ 20 LaSalle Unit 2 Cycle 14 Page 2 of 20
COLR LaSalle 2 Revision 7 List of Tables Table 3-1 LaSalle Unit 2 Cycle 14 Core Exposure Definitions....................................................................6 Table 4-1 MAPLHGR for ATRIUM-10 and ATRIUM 1 OXM Fuel.................................................................7 Table 4-2 MAPLHGR SLO Multiplier for ATRIUM-10 and ATRIUM 1 OXM Fuel.........................................7 Table 5-1 Scram Times to Notch Positions for Scram Speed-Dependent MCPR Limits............................8 Table 5-2 MCPR(P) Limits for ATRIUM-10 and ATRIUM 1 OXM Fuel, BOC to EOC, Nominal Scram Speed (NSS)......................................................................................................9 Table 5-3 MCPR(P) Limits for ATRIUM-10 and ATRIUM 1 OXM Fuel, BOC to EOC, Technical Specification Scram Speed (TSSS)............................................................................9 Table 5-4 MCPR(P) Limits for ATRIUM-10 and ATRIUM 1 OXM Fuel, Coastdown Operation, Nominal Scram Speed (NSS)....................................................................................................10 Table 5-5 MCPR(P) Limits for ATRIUM-10 and ATRIUM 1 OXM Fuel, Coastdown Operation, Technical Specification Scram Speed (TSSS)..........................................................................10 Table 5-6 MCPR(F) Limits for ATRIUM-10 and ATRIUM 1 OXM Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control System...............................................................................................11 Table 5-7 MCPR(F) Limits for ATRIUM-10 and ATRIUM 1OXM Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with Two or More TBV Opening via the Pressure Control System...............................................................................................11 Table 5-8 MCPR(F) Limits for ATRIUM-10 and ATRIUM 1 OXM Fuel, DLO and SLO, Supports Combined EOOS 2 and Combined EOOS 3 with Two or More TBV Opening via the Pressure Control System...............................................................................................11 Table 6-1 Exposure-Dependent Steady-State LHGR Limit for ATRIUM-10 and ATRIUM 1 OXM Fuel.....12 Table 6-2 LHGRFAC(P) Multipliers for ATRIUM-10 and ATRIUM 1 OXM Fuel, DLO and SLO, BOC to EOC, Nominal Scram Speed (NSS).............................................................................13 Table 6-3 LHGRFAC(P) Multipliers for ATRIUM-10 and ATRIUM 1OXM Fuel, DLO and SLO, BOC to EOC, Technical Specification Scram Speed (TSSS)...................................................13 Table 6-4 LHGRFAC(P) Multipliers for ATRIUM-10 and ATRIUM 1 OXM Fuel, DLO and SLO, Coastdown Operation, Nominal Scram Speed (NSS)...............................................................14 Table 6-5 LHGRFAC(P) Multipliers for ATRIUM-10 and ATRIUM 1 OXM Fuel, DLO and SLO, Coastdown Operation, Technical Specification Scram Speed (TSSS).....................................14 Table 6-6 LHGRFAC(F) Multipliers for ATRIUM-10 and ATRIUM 1OXM Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control System...............................................................................................15 Table 6-7 LHGRFAC(F) Multipliers for ATRIUM-10 and ATRIUM 1 OXM Fuel, DLO and SLO, Supports Base Case, FHOOS, Combined EOOS 1 with Two or More TBV Opening via the Pressure Control System...............................................................................................15 Table 6-8 LHGRFAC(F) Multipliers for ATRIUM-10 and ATRIUM 1OXM Fuel, DLO and SLO, Supports Combined EOOS 2 and Combined EOOS 3 with Two or More TBV Opening via the Pressure Control System...............................................................................................15 Table 7-1 Rod Block Monitor Setpoints.....................................................................................................16 Table 9-1 OPRM PBDA Trip Setpoints......................................................................................................18 Table 10-1 Allowed Modes of Operation and EOOS Combinations............................................................19 LaSalle Unit 2 Cycle 14 Page 3 of 20
COLR LaSalle 2 Revision 7
- 1. References 1.
Exelon Generation Company, LLC Docket No. 50-374 LaSalle County Station, Unit 2, License No. NPF-18.
2.
NRC Letter from D. M. Crutchfield to All Power Reactor Licensees and Applicants, Generic Letter 88-16; Concerning the Removal of Cycle-Specific Parameter Limits from Technical Specifications, October 3, 1988.
3.
AREVA Report ANP-2977 Revision 1, LaSalle Unit 2 Cycle 14 Reload Analysis, AREVA NP, January 2011.
4.
AREVA Report ANP-2922(P) Revision 0, LaSalle Unit 2 Cycle 14 Principal Transient Analysis Parameters, AREVA NP, July 2010.
5.
Nuclear Fuels Transmittal NFM:MW:01-0106, from A. Giancatarino to J. Nugent, "LaSalle Unit 1 and Unit 2 Rod Block Monitor COLR Setpoint Change," April 3, 2001.
6.
AREVA Engineering Information Record 51-9114888-000, "Plant Startup Testing Requirements for Power Distribution Uncertainty Verification," AREVA NP, July 6, 2009.
7.
GE Hitachi Nuclear Energy Report GE-NE-0000-0099-8344-R1 Revision 1, Exelon Nuclear LaSalle Units I and 2 Thermal Power Optimization Task T0201: Operating Power/Flow Map, November 2009.
LaSalle Unit 2 Cycle 14 Page 4 of 20
COLR LaSalle 2 Revision 7
LHGRFAC(P)
MCPR(P)
MELLLA MSIVOOS NSS OLMCPR OPRM PBDA PLUOOS PROOS RWE SLMCPR SLO SRVOOS TBV TBVOOS TCV TIP TIPOOS TSSS TSV Beginning of cycle Dual loop operation Extended load line limit analysis End of cycle End of cycle recirculation pump trip function out of service Equipment out of service Feedwater heater out of service Increased core flow Linear heat generation rate Flow-dependent LHGR multiplier Power-dependent LHGR multiplier Local power range monitor Maximum average planar linear heat generation rate Minimum critical power ratio Flow-dependent MCPR limit Power-dependent MCPR limit Maximum extended load line limit analysis Main steam line isolation valve out of service Nominal scram speed Operating limit minimum critical power ratio Oscillation power range monitor Period based detection algorithm Power-load unbalance out of service Pressure regulator out of service Rod withdrawal error Safety limit minimum critical power ratio Single loop operation Safety-relief valve out of service Turbine bypass valve Turbine bypass valve out of service Turbine control valve Traversing in-core probe Traversing in-core probe out of service Technical Specification scram speed Turbine stop valve LaSalle Unit 2 Cycle 14 Page 5 of 20
COLR LaSalle 2 Revision 7
- 3. General Information Power and flow-dependent limits are listed herein for various power and flow levels. Linear interpolation is to be used to find intermediate values (including for table cells with no given value, as applicable).
The thermal limits provided in the COLR support SLO for all analyzed equipment out of service options.
However, SLO thermal limit sets for the Base and Combined EOOS 3 conditions are the only SLO thermal limit sets to be provided for online monitoring. Additional thermal limit sets can be provided for online monitoring as necessary.
Rated core flow is 108.5 Mlbm/hr. Increased core flow (ICF) operation up to 105% rated flow is licensed for this cycle. Licensed rated thermal power is 3546 MWth (Reference 4).
For thermal limit monitoring above 100% rated power or 100% rated core flow, the 100% rated power and the 100% core flow values, respectively, can be used unless otherwise indicated in the applicable table.
The OPRM PBDA trip settings are based, in part, on the cycle-specific OLMCPR and the power-dependent MCPR limits. Any change to the OLMCPR values and/or the power-dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA trip settings.
Table 3-1 LaSalle Unit 2 Cycle 14 Core Exposure Definitions (Reference 3)
Exposure Nomenclature Core Average Exposure (MWd/MTU)
EOC 34,399 Maximum Core Exposure 39,399 Some thermal limits presented in the COLR are functions of the core average exposure range in which the core is operating. L2C14 has two major ranges to which core average exposure-dependent thermal limits are applied. The BOC to EOC thermal limit range refers to operation from the BOC core average exposure to the EOC licensed core average exposure in Table 3-1. The Coastdown thermal limit range refers to operation at core average exposures above the EOC licensed exposure through the maximum licensed core average exposure in Table 3-1.
LaSalle Unit 2 Cycle 14 Page 6 of 20
COLR LaSalle 2 Revision 7
- 4. Average Planar Linear Heat Generation Rate The MAPLHGR values for the most limiting lattice (excluding natural uranium lattices) of each fuel type, as a function of average planar exposure, is given in Table 4-1. During single loop operation, these limits are multiplied by the SLO multiplier listed in Table 4-2.
Table 4-1 MAPLHGR for ATRIUM-10 and ATRIUM IOXM Fuel (Reference 3)
Avg. Planar Exposure (GWd/MTU)
MAPLHGR (kW/ft) 0 12.5 15 12.5 55 9.1 67 7.1 Table 4-2 MAPLHGR SLO Multiplier for ATRIUM -10 and ATRIUM 1OXM Fuel (Reference 3)
Fuel Type SLO Multiplier ATRIUM-10 and ATRIUM 10XM 0.82 LaSalle Unit 2 Cycle 14 Page 7 of 20
COLR LaSalle 2 Revision 7
- 5. Operating Limit Minimum Critical Power Ratio 5.1. Manual Flow Control MCPR Limits 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.
5.1.1. Power-Dependent MCPR The power-dependent MCPR limit, MCPR(P), is determined from Tables 5-2 through 5-5, and is dependent on exposure, fuel type, and scram speed, in addition to power level.
The MCPR(P) limit determined from these tables is the power-dependent MCPR.
5.1.2. Flow-Dependent MCPR Tables 5-6 through 5-8 give the MCPR(F) limit as a function of the flow based on the applicable plant condition. The MCPR(F) limit determined from these tables is the flow-dependent MCPR.
5.2. Automatic Flow Control MCPR Limits Automatic Flow Control MCPR limits are not provided.
5.3. Scram Time NSS and TSSS refer to scram speeds / scram times.
To utilize the MCPR limits for Technical Specification Scram Speed (TSSS), the scram insertion time must be equal to or less than the values for each notch position provided below.
To utilize the MCPR limits for Nominal Scram Speed (NSS), the scram insertion time must be equal to or less than the values for each notch position provided below.
Table 5-1 Scram Times to Notch Positions for Scram Speed -Dependent MCPR Limits (Reference 4)
Notch Position TSSS Time sec NSS Time (sec) 45 0.53 0.38 39 0.85 0.68 25 1.90 1.68 05 3.45 2.68 5.4. Recirculation Flow Control Valve Settings Cycle 14 was analyzed with a maximum core flow run-out of 108%; therefore the recirculation pump flow control valve must be set to maintain core flow less than 108% (117.18 Mlbm/hr) for all run-out events (Reference 4). This value is consistent with the analyses of Reference 3.
LaSalle Unit 2 Cycle 14 Page 8 of 20
COLR LaSalle 2 Revision 7 Table 5-2 MCPR(P) Limits for ATRIUM-10 and ATRIUM 1OXM Fuel, BOC to EOC, Nominal Scram Speed (NSS)
(Reference 3)
Core Thermal Power (% of rated)**
EOOS Combination 0.0 25.0 60.0 80.0 80.0(80.01) 100.0 MCPR(P) Limit Base Case 2.10 2.10 1.53 1.41
- Base Case SLO 2.11 2.11 1.54 1.42*
FHOOS 2.18 2.18 1.59 1.41
Combined EOOS 1 2.27 2.27 1.70 1.53 1.47 Combined EOOS 1 SLO 2.28 2.28 1.71 1.54 1.48 Combined EOOS 2 2.27 2.27 1.70 1.53 1.46 Combined EOOS 2 SLO 2.28 2.28 1.71 1.54 1.47 Combined EOOS 3 2.27 2.27 1.70 1.53 1.46 Combined EOOS 3 SLO 2.28 2.28 1.71 1.54 1.47 The actual value for DLO case found in Reference 3 is 1.40; however, the minimum steady state OLMCPR is conservatively set to 1.41 based on the cycle-specific stability analysis, to preserve the 1.11 OPRM amplitude trip setpoint identified in Reference 3. The SLO value was revised accordingly.
- Cells containing the diagonal hatch line do not have a numeric value given at the respective power in Reference 3. These values are to be determined using linear interpolation between the two nearest given MCPR(P) values in the table.
Table 5-3 MCPR(P) Limits for ATRIUM -10 and ATRIUM 1OXM Fuel, BOC to EOC, Technical Specification Scram Speed (TSSS)
(Reference 3)
Core Thermal Power (% of rated)**
EOOS Combination 0.0 25.0 60.0 80.0 80.0(80.01) 100.0 MCPR(P) Limit Base Case 2.14 2.14 1.58 1.43 Base Case SLO 2.15 2.15 1.59 1.44 FHOOS 2.23 2.23 1.63 1.43 FHOOS SLO 2.24 2.24 1.64 1.44 Combined EOOS 1 2.28 2.28 1.70 1.57 1.50 Combined EOOS 1 SLO 2.29 2.29 1.71 1.58 1.51 Combined EOOS 2 2.28 2.28 1.70 1.57 1.50 Combined EOOS 2 SLO 2.29 2.29 1.71 1.58 1.51 Combined EOOS 3 2.28 2.28 1.70 1.57 1.50 Combined EOOS 3 SLO 2.29 2.29 1.71 1.58 1.51
- Cells containing the diagonal hatch line do not have a numeric value given at the respective power in Reference 3. These values are to be determined using linear interpolation between the two nearest given MCPR(P) values in the table.
LaSalle Unit 2 Cycle 14 Page 9 of 20
COLR LaSalle 2 Revision 7 Table 5-4 MCPR(P) Limits for ATRIUM-10 and ATRIUM IOXM Fuel, Coastdown Operation, Nominal Scram Speed (NSS)
(Reference 3)
Core Thermal Power (% of rated)'
EOOS Combination 0.0 25.0 60.0 80.0 80.0(80.01) 100.0 MCPR(P) Limit Base Case 2.10 2.10 1.53 1.41 Base Case SLO 2.11 2.11 1.54 1.42 FHOOS 2.18 2.18 1.59 1.41 FHOOS SLO 2.19 2.19 1.60 1.42 Combined EOOS 1 2.27 2.27 1.70 1.53 1.48 Combined EOOS 1 SLO 2.28 2.28 1.71 1.54 1.49 Combined EOOS 2 2.27 2.27 1.70 1.53 1.48 Combined EOOS 2 SLO 2.28 2.28 1.71 1.54 1.49 Combined EOOS 3 2.27 2.27 1.70 1.53 1.48 Combined EOOS 3 SLO 2.28 2.28 1.71 1.54 1.49
- Cells containing the diagonal hatch line do not have a numeric value given at the respective power in Reference 3. These values are to be determined using linear interpolation between the two nearest given MCPR(P) values in the table.
Table 5-5 MCPR(P) Limits for ATRIUM -10 and ATRIUM 10XM Fuel, Coastdown Operation, Technical Specification Scram Speed (TSSS)
(Reference 3)
Core Thermal Power (% of rated)'
EOOS Combination 0.0 25.0 60.0 80.0 80.0(80.01) 100.0 MCPR(P) Limit Base Case 2.14 2.14 1.58 1.43 Base Case SLO 2.15 2.15 1.59 1.44 FHOOS 2.23 2.23 1.63 1.43 FHOOS SLO 2.24 2.24 1.64 1.44 Combined EOOS 1 2.28 2.28 1.70 1.57 1.51 Combined EOOS 1 SLO 2.29 2.29 1.71 1.58 1.52 Combined EOOS 2 2.28 2.28 1.70 1.57 1.51 Combined EOOS 2 SLO 2.29 2.29 1.71 1.58 1.52 Combined EOOS 3 2.28 2.28 1.70 1.57 1.51 Combined EOOS 3 SLO 2.29 2.29 1.71 1.58 1.52
- Cells containing the diagonal hatch line do not have a numeric value given at the respective power in Reference 3. These values are to be determined using linear interpolation between the two nearest given MCPR(P) values in the table.
LaSalle Unit 2 Cycle 14 Page 10 of 20
COLR LaSalle 2 Revision 7 Table 5-6 MCPR(F) Limits for ATRIUM -10 and ATRIUM I OXM Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control System (Reference 3)
Flow
(% rated)
MCPR(F)
Limit 108 1.15 40 1.65 0
1.65 Table 5-7 MCPR(F) Limits for ATRIUM-10 and ATRIUM 1OXM Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with Two or More TBV Opening via the Pressure Control System (Reference 3)
Flow
(% rated)
MCPR(F)
Limit 108 1.30 40 1.70 0
1.70 Table 5-8 MCPR(F) Limits for ATRIUM-10 and ATRIUM 10XM Fuel, DLO and SLO, Supports Combined EOOS 2 and Combined EOOS 3 with Two or More TBV Opening via the Pressure Control System (Reference 3)
Flow
(% rated)
MCPR(F)
Limit 108 1.40 40 1.80 0
1.80 LaSalle Unit 2 Cycle 14 Page 11 of 20
COLR LaSalle 2 Revision 7
- 6. Linear Heat Generation Rate The linear heat generation rate (LHGR) limit is the product of the exposure -dependent LHGR limit from Table 6-1 and the minimum of: the power-dependent LHGR multiplication factor, LHGRFAC(P), or the flow-dependent LHGR multiplication factor, LHGRFAC(F). The LHGRFAC(P) is determined from Tables 6-2 through 6-5. The LHGRFAC( F) is determined from Tables 6-6 through 6-8.
Table 6-1 Exposure-Dependent Steady-State LHGR Limit for ATRIUM-10 and ATRIUM IOXM Fuel (Reference 3)
Pellet Exposure (GWd/MTU)
LHGR Limit (kW/ft) 0.0 13.4 17.7 13.4 61.1 9.1 70.4 7.3 LaSalle Unit 2 Cycle 14 Page 12 of 20
COLR LaSalle 2 Revision 7 Table 6-2 LHGRFAC(P) Multipliers for ATRIUM -10 and ATRIUM I OXM Fuel, DLO and SLO, BOC to EOC, Nominal Scram Speed (NSS)
(Reference 3)
Core Thermal Power (% of rated)'
EOOS Combination 0.0 25.0 60.0 80.0 80.0(80.01) 100.0 LHGRFAC(P) Multiplier Base Case 0.74 0.74 1.00 1.00 1.00 FHOOS 0.70 0.70 0.96 1.00 1.00 Combined EOOS 1 0.66 0.66 0.89 0.99 0.99 Combined EOOS 2 0.66 0.66 0.89 0.99 0.99 Combined EOOS 3 0.66 0.66 0.89 0.97 0.99
- Cells containing the diagonal hatch line do not have a numeric value given at the respective power in Reference 3. These values are to be determined using linear interpolation between the two nearest given LHGRFAC(P) values in the table.
Table 6-3 LHGRFAC(P) Multipliers for ATRIUM-10 and ATRIUM 1 OXM Fuel, DLO and SLO, BOC to EOC, Technical Specification Scram Speed (TSSS)
(Reference 3)
Core Thermal Power (% of rated)
EOOS Combination 0.0 25.0 60.0 80.0 80.0(80.01) 100.0 LHGRFAC(P) Multiplier Base Case 0.72 0.72 0.97 1.00 1.00 FHOOS 0.69 0.69 0.94 1.00 1.00 Combined EOOS 1 0.66 0.66 0.89 0.95 0.95 Combined EOOS 2 0.66 0.66 0.89 0.97 0.97 Combined EOOS 3 0.66 0.66 0.89 0.94 0.97
- Cells containing the diagonal hatch line do not have a numeric value given at the respective power in Reference 3. These values are to be determined using linear interpolation between the two nearest given LHGRFAC(P) values in the table.
LaSalle Unit 2 Cycle 14 Page 13 of 20
COLR LaSalle 2 Revision 7 Table 6-4 LHGRFAC(P) Multipliers for ATRIUM-10 and ATRIUM IOXM Fuel, DLO and SLO, Coastdown Operation, Nominal Scram Speed (NSS)
(Reference 3)
Core Thermal Power (% of rated)'
EOOS Combination 0.0 25.0 60.0 80.0 80.0(80.01) 100.0 LHGRFAC(P) Multiplier Base Case 0.74 0.74 1.00 1.00 1.00 FHOOS 0.70 0.70 0.96 1.00 1.00 Combined EOOS 1 0.66 0.66 0.89 0.96 0.97 Combined EOOS 2 0.66 0.66 0.89 0.96 0.97 Combined EOOS 3 0.66 0.66 0.89 0.96 0.97
- Cells containing the diagonal hatch line do not have a numeric value given at the respective power in Reference 3. These values are to be determined using linear interpolation between the two nearest given LHGRFAC(P) values in the table.
Table 6-5 LHGRFAC(P) Multipliers for ATRIUM-10 and ATRIUM 10XM Fuel, DLO and SLO, Coastdown Operation, Technical Specification Scram Speed (TSSS)
(Reference 3)
Core Thermal Power (% of rated)'
EOOS Combination 0.0 25.0 60.0 80.0 80.0(80.01) 100.0 LHGRFAC(P) Multiplier Base Case 0.72 0.72 0.97 1.00 1.00 FHOOS 0.69 0.69 0.94 1.00 1.00 Combined EOOS 1 0.66 0.66 0.89 0.91 0.94 Combined EOOS 2 0.66 0.66 0.89 0.94 0.95 Combined EOOS 3 0.66 0.66 0.89 0.94 0.95
- Cells containing the diagonal hatch line do not have a numeric value given at the respective power in Reference 3. These values are to be determined using linear interpolation between the two nearest given LHGRFAC( P) values in the table.
LaSalle Unit 2 Cycle 14 Page 14 of 20
COLR LaSalle 2 Revision 7 Table 6-6 LHGRFAC(F) Multipliers for ATRIUM-10 and ATRIUM 10XM Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control System (Reference 3)
Flow
(% rated)
LHGRFAC(F)
Multiplier 108 1.00 80 1.00 30 0.75 0
0.75 Table 6-7 LHGRFAC(F) Multipliers for ATRIUM-10 and ATRIUM 10XM Fuel, DLO and SLO, Supports Base Case, FHOOS, Combined EOOS 1 with Two or More TBV Opening via the Pressure Control System (Reference 3)
Flow
(% rated)
LHGRFAC(F)
Multiplier 108 1.00 80 1.00 30 0.75 0
0.75 Table 6-8 LHGRFAC(F) Multipliers for ATRIUM -10 and ATRIUM 10XM Fuel, DLO and SLO, Supports Combined EOOS 2 and Combined EOOS 3 with Two or More TBV Opening via the Pressure Control System (Reference 3)
Flow
(% rated)
LHGRFAC(F)
Multiplier 108 1.00 80 1.00 30 0.75 0
0.75 LaSalle Unit 2 Cycle 14 Page 15 of 20
COLR LaSalle 2 Revision 7
- 7. Rod Block Monitor The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below (Reference 5):
Table 7-1 Rod Block Monitor Setpoints ROD BLOCK MONITOR UPSCALE TRIP FUNCTION ALLOWABLE VALUE Two Recirculation Loop 0.66 Wd + 54.0%
Operation Single Recirculation Loop 0.66 Wd + 48.7%
Operation The setpoint may be lower/higher and will still comply with the rod withdrawal error (RWE) analysis because RWE is analyzed unblocked. The allowable value is clamped with a maximum value not to exceed the allowable value for a recirculation loop drive flow (Wd) of 100%.
Wd - percent of recirculation loop drive flow required to produce a rated core flow of 108.5 Mlbm/hr.
LaSalle Unit 2 Cycle 14 Page 16 of 20
COLR LaSalle 2 Revision 7
- 8. Traversing In-Core Probe System 8.1.
Description When the traversing in-core probe (TIP) system (for the required measurement locations) is used for recalibration of the LPRM detectors and monitoring thermal limits, the TIP system shall be operable with the following:
1.
movable detectors, drives and readout equipment to map the core in the required measurement locations, and 2.
indexing equipment to allow all required detectors to be calibrated in a common location.
The following applies for use of the SUBTIP methodology (Reference 6):
The total number of failed and bypassed LPRMs does not exceed 50%. With one or more TIP measurement locations inoperable, the TIP data for an inoperable measurement location may be replaced by data obtained from a 3-dimensional BWR core monitoring software system algorithm, provided the total number of simulated channels (measurement locations) does not exceed 42%
(18 channels).
Otherwise, with the TIP system inoperable, suspend use of the system for the above applicable calibration functions.
8.2.
Bases The operability of the TIP system with the above specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core. The normalization of the required detectors is performed internal to the core monitoring software system.
Substitute TIP data, if needed, are derived from adjusted 3-dimensional BWR core monitoring software calculated data that is based on measured and calculated axial and radial factors. Since the simulation and adjustment process could introduce uncertainty, a maximum of 18 channels may be simulated to ensure that the uncertainties assumed in the substitution process methodology remain valid.
LaSalle Unit 2 Cycle 14 Page 17 of 20
COLR LaSalle 2 Revision 7
- 9. Stability Protection Setpoints The OPRM PBDA Trip Settings (Reference 3):
Table 9-1 OPRM PBDA Trip Setpoints PBDA Trip Amplitude Setpoint (Sp)
Corresponding Maximum Confirmation Count Setpoint (Np) 1.11 14 The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system.
The OPRM PBDA trip settings are based, in part, on the cycle-specific OLMCPR and the power-dependent MCPR limits. Any change to the OLMCPR values and/or the power-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.
LaSalle Unit 2 Cycle 14 Page 18 of 20
COLR LaSalle 2 Revision 7
- 10. Modes of Operation The allowed modes of operation with combinations of equipment out of service are as described below.
Table 10-1 Allowed Modes of Operation and EOOS Combinations (Reference 3)
Equipment Out of Service Options 1,2,4 Thermal Limit Set Base Case Base Base Case + SLO Base SLO Base Case + FHOOS (up to 100°F reduction)
FHOOS Base Case + TCV Slow Closure + EOCRPTOOS + PROOS Base Case + TCV Slow Closure + EOCRPTOOS + 5 Turbine Bypass Valves out Combined EOOS 1 of service (5 TBVOOS) (i.e., Base Case + 4)
Base Case + TCV Slow Closure + EOCRPTOOS + FHOOS (up to 100°F reduction)
Base Case + TCV Slow Closure + EOCRPTOOS + one Stuck Closed TCV and/or Combined EOOS 2 TSV3 + one MSIVOOS3 Base Case + TCV Slow Closure + EOCRPTOOS + one Stuck Closed TCV and/or TSV3 + one MSIVOOS3 + FHOOS (up to 100°F reduction) + PROOS +
Combined EOOS 3 2 TBVOOS (i.e., Base Case + 1)
Base Case + TCV Slow Closure + EOCRPTOOS + one Stuck Closed TCV and/or Combined EOOS 3 TSV3 + one MSIVOOS3 + FHOOS (up to 100°F reduction) + PROOS +
SLO 2 TBVOOS (i.e., Base Case + 1) + SLO I - Base case includes a feedwater temperature reduction of up to 30°F + I SRVOOS + 1 TBVOOS +
PLUOOS, and also includes 2 TIPOOS (or the equivalent number of TIP channels) any time during the cycle, including BOC, and up to 50% of the LPRMs out of service. The base case limits support the ICF, ELLLA, and MELLLA operating domains and coastdown operation. SLO operation is only valid for ELLLA (Reference 7). See Section 3 for SLO.
2 - The TBVOOS nomenclature described in the specific equipment out of service options represents the number of turbine bypass valves that the specific analysis supports not fast opening on either turbine control valve fast closure or turbine stop valve position. Additionally, the thermal limit sets in place to support all EOOS options (including the base case) require two or more turbine bypass valves opening on pressure control.
3 - The one Stuck Closed TCV and/or TSV EOOS conditions require the reactor thermal power to be
< 85% of rated. The one MSIVOOS condition is also supported as long as the reactor thermal power is maintained at <_ 75% of rated.
4 - The "+" sign used in the equipment out of service options descriptions above designates "and/or" logic.
LaSalle Unit 2 Cycle 14 Page 19 of 20
COLR LaSalle 2 Revision 7
- 11. 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.
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.
2.
ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
3.
ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3, and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.
4.
XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T.* A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.
5.
EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
6.
ANF-89-98(P)(A), Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
7.
EMF-85-74(P) Revision 0 and Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.
8.
EMF-CC-074(P)(A) Volume 4 Revision 0, BWR Stability Analysis - Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.
9.
XN-NF-CC-33(P)(A) Supplement 1 Revision 1, HUXY: A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option, Exxon Nuclear Company, August 1986 (equivalent to ANF-CC-33).
- 10. 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.
- 11. XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.
- 12. 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.
- 13. 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.
- 14. 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.
- 16. NEDO-32465-A, Licensing Topical Report, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, GE Nuclear Energy, August 1996.
- 17. AN F-1 358(P)(A) Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.
- 18. XN-NF-84-105(P)(A) Volume 1 Supplement 4, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis Void Fraction Model Comparison to Experimental Data, Advanced Nuclear Fuels Corporation, June 1988.
LaSalle Unit 2 Cycle 14 Page 20 of 20