RA14-011, County Station, Unit 1 - Cycle 16 Core Operating Limits Report (Colr): Difference between revisions

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{{Adams
#REDIRECT [[RA14-011, Cycle 16 Core Operating Limits Report (Colr)]]
| number = ML14051A818
| issue date = 02/20/2014
| title = County Station, Unit 1 - Cycle 16 Core Operating Limits Report (Colr)
| author name = Karaba P J
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000373
| license number = NPF-011
| contact person =
| case reference number = RA14-011
| document type = Letter type:RA, Operating Report
| page count = 22
}}
 
=Text=
{{#Wiki_filter:RA 14-011 10 CFR 50.59 February 20, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Unit 1 Facility Operating License No. NPF-1 1 NRC Docket No. 50-373
 
==Subject:==
Unit 1 Cycle 16 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 1 Cycle 16 reload licensing analyses under the provisions of 10 CFR 50.59, "Changes, tests and experiments," and to transmit Revision 0 of the Core Operating Limits Report (COLR) for Cycle 16, 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 Specifications (TS) 5.6.5, "Core Operating Limits Report (COLR)," item d.
The reload licensing analyses performed for Cycle 16 utilized NRC approved methodologies.
The Unit 1 Cycle 16 core, which consists of NRC approved fuel designs developed by AREVA NP Inc. and Global Nuclear Fuel - Americas, LLC (GNF-A) was designed to operate within approved fuel design criteria provided in the TS and related TS Bases.
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 licensing analyses does not require NRC review and approval.
February 20, 2014 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this submittal, please contact Mr. Guy V. Ford, Jr., Regulatory Assurance Manager, at (815) 415-2800.
Respectfully, Peter J. Karaba Site Vice President LaSalle County Station
 
==Attachment:==
Core Operating Limits Report for LaSalle Unit 1 Cycle 16, Revision 0 cc:Regional Administrator - NRC Region III NRC Senior Resident Inspector - LaSalle County Station COLR LaSalle 1 Revision 14 Page 1 of 20 Core Operating Limits Report for LaSalle Unit I Cycle 16 Revision 0 COLR LaSalle 1 Revision 14 Page 2 of 20 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.Scram Time
..............................................................................................................................8 5.3.Recirculation Flow Control Valve Settings .................................................................................
9 6.Linear Heat Generation Rate .........................................................................................................13 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 COLR LaSalle 1 Revision 14 Page 3 of 20 List of Tables 3-1Cycle Exposure Range Definitions
................................................................................................................
6 4-1MAPLHGR for GNF2 Fuel .............................................................................................................................7 4-2MAPLHGR for ATRIUM
-10 Fuel....................................................................................................................7 4-3MAPLHGR SLO Multiplier for GNF2 and ATRIUM-10 Fuel, BOC to EOC ...................................................7 5-1Scram Times Required for Option A and Option B Application at Notch Position 39 ...................................9 5-2Operating Limit Minimum Critical Power Ratio (OLMCPR) for ATRIUM-10 and GNF2 Fuel ......................10 5-3Power-Dependent MCPR Multipliers (Kp) for ATRIUM
-10 and GNF2 Fuel, DLO and SLO, BOC to EOC, Option A and Option B .................................................................................................................................11 5-4DLO Flow-Dependent MCPR Limits (MCPRF) for ATRIUM
-10 and GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B ................................................................................................12 5-5SLO Flow-Dependent MCPR Limits (MCPRF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B ................................................................................................12 6-1LHGR Limit for GNF2 Fuel
..........................................................................................................................
13 6-2LHGR Limit for ATRIUM-10 Fuel
.................................................................................................................
13 6-3Power-Dependent LHGR Multipliers (LHGRFACP) for ATRIUM
-10 and GNF2 Fuel, DLO and SLO, BOC to EOC.........................................................................................................................................................
14 6-4Flow-Dependent LHGR Multipliers (LHGRFACF) for ATRIUM
-10 and GNF2 Fuel, BOC to EOC, Pressurization (1 TCV/TSV Closed or OOS), All Application Groups .........................................................15 6-5Flow-Dependent LHGR Multipliers (LHGRFACF) for ATRIUM
-10 and GNF2 Fuel, BOC to EOC, No Pressurization (All TCV/TSV In-Service), All Application Groups
..........................................................
15 7-1Rod Block Monitor Setpoints .......................................................................................................................16 9-1OPRM PBDA Trip Setpoints
........................................................................................................................
18 10-1Allowed Modes of Operation and EOOS Combinations ..............................................................................19 COLR LaSalle 1 Revision 14 Page 4 of 20 1.References 1.
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 Tech Specs, October 3, 1988.
3.Nuclear Fuels Letter 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.
4.GE Nuclear Energy Report NEDC-32694P-A, Revision 0, "Power Distribution Uncertainties for Safety Limit MCPR Evaluations," August 1999.
5.GE Nuclear Energy Document GE-NE-A1300384-07-01, Revision 1, "LaSalle County Station Power Uprate Project Task 201: Reactor Power/Flow Map", September 1999.
6.GE Hitachi Nuclear Energy Report, GE-NE-0000-0099-8344-R1, Revision 1, "Exelon Nuclear LaSalle Units 1 and 2 Thermal Power Optimization Task T0201: Operating Power/Flow Map", November 2009.
7.GNF Report 000N0801-SRLR, Revision 1, "Supplemental Reload Licensing Report for LaSalle Unit 1 Reload 15 Cycle 16," January 2014.
8.GNF Letter from B. R. Moore to Document Control Desk,
 
==Subject:==
"GNF2 Advantage Generic Compliance with NEDE-2401 1-P-A (GESTAR II), NEDC-33270P, Revision 5, May 2013," MFN 13-029, May 24, 2013 (ADAMS Accession No. ML13148A318) 9.AREVA Report ANP-2914(P), Revision 1, "Mechanical Design Report for LaSalle Units 1 and 2 MUR ATRIUM-10 Fuel Assemblies," AREVA NP Inc., June 2010.
10.Exelon Transmittal ES1300014, Revision 0, "LaSalle Unit 1 Cycle 16 Final Resolved OPL-3 Parameters," August 21, 2013.
11.GNF DRF A12-00038
-3, Vol. 4,"Scram Times Verses Notch Position," G. A. Watford, May 22, 1992.
12.GEH Nuclear Energy DRF Section 0000-0151-0765 Rev. 0, "Application of SLO MCPR", 2/12/13.
COLR LaSalle 1 Revision 14 Page 5 of 20
: 2. Terms and Definitions ARTS ATRM10 BOC BWR CFR COLR CRD DLO ELLLA EOC EOOS EOR16 FFWTR FWHOOS GNF ICF Kp L1C16 LHGR LHGRFACF LHGRFACP LPRM MAPLHGR MCPR MCPRF MELLLA MOC MSIVOOS OLMCPR OOS OPRM PBDA PLUOOS PROOS RPTOOS RWE SLMCPR SLO SRVOOS TBV TBVOOS TCV TCVSC TIP TIPOOS TSV 3DM Average Power Range Monitor, Rod Block Monitor and Technical Specification Improvement Program AREVA ATRIUM-10 fuel type Beginning of cycle Boiling water reactor Code of Federal Regulations Core operating limits report Control rod drive mechanism Dual loop operation Extended load line limit analysis End of cycle Equipment out of service End of rated operation for Cycle 16 Final feedwater temperature reduction Feedwater heater out of service Global Nuclear Fuels -
Americas Increased core flow Power-dependent MCPR Multiplier LaSalle Unit 1 Cycle 16 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 Maximum extended load line limit analysis Middle of Cycle Point for Licensing Purposes Main steam isolation valve out of service Operating limit minimum critical power ratio Out of service Oscillation power range monitor Period based detection algorithm Power load unbalance out of service Pressure regulator out of service Recirculation pump trip 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 Turbine control valve slow closure Traversing in-core probe Traversing in-core probe out of service Turbine stop valve 3-D Monicore COLR LaSalle 1 Revision 14 Page 6 of 20
: 3. General Information Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values.
Rated core flow is 108.5 Mlbm/hr. Operation up to 105% rated flow is licensed for this cycle. Licensed rated thermal power is 3546 MWth.
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.
Table 3-1 defines the three exposure ranges used in the COLR. The end of rated (EOR) exposure is defined as the cycle exposure corresponding to all rods out, 100% power/100% flow, and normal feedwater temperature.
The term (EOR - 3715 MWd/ST) means the FOR exposure minus 3715 MWd/ST of exposure. The value of the FOR exposure is based on actual plant operation and is thus determined from projections to this condition made near, but before, the time when the EOR16 - 3715 MWd/ST exposure will be reached. For cycle exposure dependent limits at the exact MOC exposure, the more limiting of the BOC to MOC and the MOC to EOC limits should be used. This can be achieved by applying the MOC to EOC limits to the MOC point as all cycle exposure dependent limits in the MOC to EOC limit sets are the same as, or more limiting than, those in the BOC to MOC limit sets.
Table 3-1 Cycle Exposure Range Definitions (Reference 7):
Nomenclature Cycle Exposure Range BOC to MOC BOC16 to (EOR16 - 3715 MWd/ST)
MOC to EOC (EOR16 - 3715 MWd/ST) to EOC16 BOC to EOC BOC16 to EOC16 COLR LaSalle 1 Revision 14 Page 7 of 20
: 4. Average Planar Linear Heat Generation Rate Technical Specification Sections 3.2.1 and 3.4.1 The MAPLHGR values for the most limiting lattice of each fuel type as a function of average planar exposure aregiven in Tables 4-1 and 4-2. During single loop operation, these limits are multiplied by the fuel-dependent SLO multiplier listed in Table 4-3. The MAPLHGR values in Tables 4-1 and 4-2 along with the MAPLHGR SLO multipliers in Table 4-3 provide coverage for all modes of operation.Table 4-1 MAPLHGR for GNF2 Fuel (Reference 7)
Avg. Planar MAPLHGR Exposure (kW/FT)GWd/ST 0.00 13.78 17.15 13.78 60.78 6.87 63.50 5.50 Table 4-2 MAPLHGR for ATRIUM-10 Fuel (Reference 7)
Avg. Planar Exposure GWd/ST MAPLHGR (kW/FT)0 12.81 21.41 12.81 55.42 9.10 63.86 7.30 Table 4-3 MAPLHGR SLO Multiplier for GNF2 and ATRIUM
-10 Fuel, BOC to EOC (Reference 7)
SLO Fuel Type MAPLHGR Multi p lier GNF2 0.78 ATRIUM-10 0.78 COLR LaSalle 1 Revision 14 Page 8 of 20
: 5. Operating Limit Minimum Critical Power Ratio Technical Specification Sections 3.2.2, 3.3.4.1, 3.4.1, and 3.7.7 5.1.Manual Flow Control MCPR Limits The steady-state OLMCPRs given in Table 5-2 are the maximum values obtained from analysis of the pressurization events, non-pressurization events, and the Option III stability evaluation.
MCPR values are determined by the cycle-specific fuel reload analyses in Reference 7. Table 5-2 is used in conjunction with the ARTS-based power (Kp) and flow (MCPRF) dependencies presented in Tables 5-3, 5-4, and 5-5 below. The OLMCPR is determined for a given power and flow condition by evaluating the power and flow dependent MCPR values and selecting the greater of the two.
5.1.1.Power-Dependent MCPR The power-dependent MCPR multiplier, Kp, is determined from Table 5-3, and is dependent only on the power level and the Application Group (EOOS). The product of the steady state OLMCPR and the proper KQ provides the power-dependent OLMCPR.
5.1.2. Flow
-Dependent MCPR Tables 5-4 through 5-5 give the MCPRF limit as a function of the core flow, based on the applicable plant conditions. The MCPRF limit determined from these tables is the flow-dependent OLMCPR.5.2.Scram Time Option A and Option B MCPR analyses and results are dependent upon core average control rod blade scram speed insertion times.
The Option A scram time is the Improved Technical Specification scram speed based insertion time. The core average scram speed insertion time for 20% insertion must be less than or equal to the Technical Specification scram speed insertion time to utilize the Option A MCPR limits. Reload analyses performed by GNF for Cycle 16 Option A MCPR limits utilized a 20% core average insertion time of 0.900 seconds (Reference 10).
To utilize the MCPR limits for the Option B scram speed insertion times, the core average scram speed insertion time for 20% insertion must be less than or equal to 0.694 seconds (Reference 10) (0.672 seconds at notch position 39, Reference 11). See Table 5-1 for a summary of scram time requirements related to the use of Option A and Option B MCPR limits.
If the core average scram insertion time does not meet the Option B criteria, but is within the Option A criteria, the appropriate steady state MCPR value may be determined from a linear interpolation between the Option A and B limits with standard mathematical rounding to two decimal places.
When performing the linear interpolation to determine MCPR limits, ensure that the time used for Option A is 0.900 seconds (0.875 seconds to notch position 39, Reference 11). Note that making interpolations using the Table 5-2 data is conservative because the stability based OLMCPR sets the limit in many conditions. The Option A to Option B linear interpolation need not include the stability OLMCPR penalty on the endpoints when the calculation is made. However, the result of the linear interpolation is required to be 1.51 or greater for the steady state OLMCPR due to the OPRM PBDA setpoint (see Section 9 of the COLR and Reference 7).
COLR LaSalle 1 Revision 14 Page 9 of 20 Table 5-1 Scram Times Required for Option A and Option B Application at Notch Position 39 (References 10 and 11)
Notch Position*Scram Time Required for Option A Application Scram Time Required for Option B Application 39<_ 0.875 sec.
<_ 0.672 sec.
* - The insertion time to a notch position is conservatively calculated using the CRD reed switch drop-out time per Reference 11.
5.3.Recirculation Flow Control Valve Settings Cycle 16 was analyzed with a maximum core flow runout of 105%; therefore the recirculation pump flow control valves must be set to maintain core flow less than 105% (113.925 Mlbm/hr) for all runout events.
COLR LaSalle 1 Revision 14 Page 10 of 20Table 5-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) for ATRIUM-10 and GNF2 Fuel (Reference 7)
A li ti G DLO/Exposure O p tion A O p tion B pp ca on roup SLO Ran g e GNF2 ATRMIO GNF2 ATRMIO BOC-MOC 1.51 1.51 1.51 1.51 B C DLO ase ase MOC-EOC 1.61 1.53 1.56 1.51 BOC-MOC 1.56 1.51 1.56 1.51 B C SLO ase ase MOC-EOC 1.63 1.55 1.58 1.52 BOC-MOC 1.58 1.56 1.51 1.51 Base Case+ TCVSC DLO+ RPTOOS + PRODS MOC-EOC 1.69 1.70 1.59 1.53 BOC-MOC 1.60 1.58 1.56 1.51 Base Case+ TCVSC+ RPTOOS + PRODS SLO MOC-EOC 1.71 1.72 1.61 1.55 BOC-MOC 1.53 1.51 1.51 1.51 Base Case + TCVSC +
DLO TBVOOS (all 5 valves)
MOC-EOC 1.65 1.56 1.60 1.53 BOC-MOC 1.56 1.51 1.56 1.51 Base Case + TCVSC +
TBVOOS (all 5 valves)
SLO MOC-EOC 1.67 1.58 1.62 1.55 Base Case + TCVSC +
BOC-MOC 1.61 1.59 1.51 1.51 TBVOOS ll 5 l (a va ves)DLO+ RPTOOS + PROOS MOC-EOC 1.73 1.74 1.63 1.57 Base Case+ TCVSC +BOC-MOC 1.63 1.61 1.56 1.51 TBVOOS ll 5 l (a va ves)SLO+ RPTOOS + PROOS MOC-EOC 1.75 1.76 1.65 1.59 COLR LaSalle 1 Revision 14 Page 11 of 20 Table 5-3 Power-Dependent MCPR Multipliers (Kp) for ATRIUM-10 and GNF2 Fuel, DLO and SLO, BOC to EOC, Option A and Option B (Reference 7)
Kp, MCPR Limit Multiplier (as a function of % rated power)
A lication Grou pp p 0% P 25%P 45% P 60%P 85% P 85.01%P 100% P Base Case 1.338 1.338 1.191 1.191 1.061 1.061 1.000 Base Case + TCVSC
+ RPTOOS +
1.488 1.488 1.378 1.296 1.174 1.097 1.000 PROOS Base Case + TCVSC
+ TBVOOS (all 5 1.379 1.379 1.228 1.207 1.097 1.097 1.000 valves)Base Case + TCVSC
+ TBVOOS (all 5 1.488 1.488 1.378 1.296 1.174 1 097 1 000 valves) +..RPTOOS + PROOS COLR LaSalle 1 Revision 14 Page 12 of 20 Table 5-4 DLO Flow-Dependent MCPR Limits (MCPRF)for ATRIUM-10 and GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B (Reference 7)
Flow (% Rated)MCPRF 0.0 1.89 30.0 1.70 105.0 1.24 Table 5-5 SLO Flow
-Dependent MCPR Limits (MCPRF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, All Application Groups, Option A and Option B (References 7 and 12)Flow (% Rated)MCPRF 0.0 1.91 30.0 1.72 105.0 1.26 COLR LaSalle 1 Revision 14Page 13 of 20
: 6. Linear Heat Generation Rate Technical Specification Sections 3.2.3 and 3.4.1 The linear heat generation rate (LHGR) limit is the product of the exposure dependent LHGR limit from Table 6-1 or Table 6-2 and the minimum of: the power dependent LHGR Factor, LHGRFACP, or the flow dependent LHGR Factor, LHGRFACF as applicable. The LHGRFACP multiplier is determined from Table 6-3. The LHGRFACF multiplier is determined from either Table 6-4 or Table 6-5. The SLO multipliers in Tables 6-4 and 6-5 have been limited to a maximum value of 0.78, the SLO LHGR multiplier for GNF2 and ATRIUM-10 fuel.Table 6-1 LHGR Limit for GNF2 Fuel (Reference 8)
Peak Pellet ExposureU02 LHGR Limit See Table B-1 of Reference 8 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit See Table B-2 of Reference 8Table 6-2 LHGR Limit for ATRIUM
-10 Fuel (Reference 9)
Peak Pellet Exposure (GWd/ST)LHGR Limit (kW/ft)0.0 13.4 16.06 13.4 55.43 9.1 63.87 7.3 COLR LaSalle 1 Revision 14 Page 14 of 20 Table 6-3 Power-Dependent LHGR Multipliers (LHGRFACp) for ATRIUM-10 and GNF2 Fuel, DLO and SLO, BOC to EOC (Reference 7)
LHGRFACP (as a function of % rated power)
A lication Grou pp p 0% P 25%P 45% P 60% P 85% P 100% P Base Case 0.608 0.608 0.713 0.791 0.922 0.978 Base Case + TCVSC
+ RPTOOS +
0.608 0.608 0.713 0.761 0.831 0.978 PROOS Base Case + TCVSC
+ TBVOOS (all 5 0.608 0.608 0.713 0.791 0.922 0.978 valves)Base Case + TCVSC
+ TBVOOS (all 5 0.608 0.608 0 713 0 761 0 822 978 0 valves) +....RPTOOS + PROOS COLR LaSalle 1 Revision 14 Page 15 of 20 Table 6-4 Flow-Dependent LHGR Multipliers (LHGRFACF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, Pressurization (1 TCV/TSV Closed or OOS), All Application Groups (Reference 7)
Flow (% Rated)DLO LHGRFACF SLO LHGRFACF 0.0 0.110 0.110 30.0 0.410 0.410 67.0 0.78 0.78 89.0 1.000 0.78 105.0 1.000 0.78 Table 6-5 Flow-Dependent LHGR Multipliers (LHGRFACF) for ATRIUM-10 and GNF2 Fuel, BOC to EOC, No Pressurization (All TCVITSV In-Service), All Application Groups (Reference 7)
(% Flow (/&deg; Rated)
DLO LHGRFACF SLO LHGRFACF 0.0 0.250 0.250 30.0 0.550 0.550 53.0 0.78 0.78 75.0 1.000 0.78 105.0 1.000 0.78 COLR LaSalle 1 Revision 14 Page 16 of 20
: 7. Rod Block Monitor Technical Specification Sections 3.3.2.1 and 3.4.1 The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below (Reference 3):
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.
COLR LaSalle 1 Revision 14 Page 17 of 20 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 with 3DM (Reference 4):
The total number of failed and/or bypassed LPRMs does not exceed 25%. In addition, no more than 14 TIP channels can be OOS (failed or rejected).
Otherwise, with the TIP system inoperable, suspend use of the system for the above applicable calibration functions.
H.Z.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.
COLR LaSalle 1 Revision 14 Page 18 of 20 9.Stability Protection Setpoints Technical Specification Section 3.3.1.3 Table 9-1 OPRM PBDA Trip Setpoints (Reference 7)
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.
COLR LaSalle 1 Revision 14 Page 19 of 20
: 10. Modes of Operation The allowed modes of operation with combinations of equipment out-of-service are as described below (Reference 7).
Table 10-1 Allowed Modes of Operation and EOOS Combinations (Reference 7)
Equipment Out of Service Options (1) (2)(4)(5)Short Name Base Case (Option A or B)
(3)Base Base Case+ SLO (Option A or B)
Base SLO Base Case+ TCVSC + RPTOOS + PROOS (Option A or B)
Combined EOOS 1 Base Case + TCVSC + RPTOOS + PROOS + SLO (Option A or B)
Combined EOOS 1 SLO Base Case + TCVSC + TBVOOS (all 5 valves)(Option A or B)
Combined EOOS 2 Base Case + TCVSC + TBVOOS (all 5 valves)
+ SLO (Option A or B)
Combined EOOS 2 SLO Base Case + TCVSC + TBVOOS (all 5 valves) + RPTOOS + PROOS (Option A or B)
Combined EOOS 3 Base Case+ TCVSC + TBVOOS (all 5 valves) + RPTOOS + PROOS + SLO (Option A or B)
Combined EOOS 3 SLO (1)Base case includes I SRVOOS + 1 TCVITSV OOS + FWHOOS/FFWTR + 1 MSIVOOS + 2 TBVOOS + PLUOOS, and also includes 1 TIPOOS (up to 14 TIP channels not available) any time during the cycle, including BOC, and up to 25% of the LPRMs out-of-service. The FWHOOS/FFWTR analyses cover a maximum reduction of 100&deg;F for the feedwater temperature.
A nominal LPRM calibration interval of 2000 EFPH (2500 EFPH maximum) is supported for L1C16.
(2)TBVOOS (all 5 valves) is the turbine bypass system out of service which means that 5 TBVs are not credited for fast opening and 3 TBVs are not credited to open in pressure control. For the 2 TBVOOS condition that is a part of the base case, the assumption is that both of the TBVs do not open on any signal and thus remain shut for the transients analyzed (i.e. 3 TBVs are credited to open in pressure control). The MCFL is currently set at 126.6 and will only allow opening of TBV's #1,#2, #3, and #4 during a slow pressurization event. The MCFL does not use the TBV position feedback signal to know how many TBVs have opened or how far each has opened. The #5 TBV is not available based on the current MCFL setpoint and thus cannot be used as one of the credited valves to open in pressure control.
(3)With all TCVITSV In-Service, the Base Case should be used with the LHGRFACF values from Table 6
-5 (Reference 7).
With 1 TCV/TSV OOS, the Base Case must be used with the LHGRFACF values from Table 6-4. The one Stuck Closed TCV and/or TSV EOOS conditions require power levels 85% of rated. The one MSIVOOS condition is also supported as long as thermal power is maintained 5 75% of the rated.
(4)The + sign that is used in the Equipment Out of Service Option / Application Group descriptions designates an "and/or".
(5)All EOOS Options (Reference 7 Application Groups) are applicable to ELLLA, MELLLA, ICF and Coastdown realms of operation with the exception that SLO is not applicable to MELLLA or ICF (References 5 and 6). The MOC to EOC exposure range limit sets are generated by GNF to include application to coastdown operation (Methodology Reference 5).
COLR LaSalle 1 Revision 14 Page 20 of 20
: 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," March 1984.
2.ANF-89-98 (P)(A), Revision 1 and Revision 1 Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," May 1995.
3.EMF-85-74 (P) Revision 0 Supplement 1(P)(A) and Supplement 2(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," February 1998.
4.XN-NF-85-67 (P)(A) Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986.
5.N EDE-2401 1 -P-A-20 (Revision 20), "General Electric Standard Application for Reactor Fuel," December 2013 and the U.S. Supplement NEDE-2401 1 -P-A-20-US, of December 2013.
6.NEDC-33106P-A Revision 2, "GEXL97 Correlation for ATRIUM-10 Fuel," June 2004.
7.NEDO-32465-A, "BWR Owner's Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.}}

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