RA08-008, Cycle 13 Core Operating Limits Report (COLR)
| ML080860490 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/17/2008 |
| From: | Enright D Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA08-008 | |
| Download: ML080860490 (45) | |
Text
Exelkn LaSalle Generating Station www.exeloncoTp.com Nuclear 2601 North 21st Road Marseilles, I L 61341-9757 RA08-008 March 17, 2008 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 13 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 13 reload under the provisions of 10 CFR 50.59, "Changes, tests and experiments," and to transmit the Core Operating Limits Report (COLR) for Cycle 13, 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 13 utilized NRC approved methodologies.
The Unit 1 Cycle 13 core, which consists of NRC approved fuel designs developed by Global Nuclear-Fuel[(GNF) and.Framatome-Advanced-Nuclear-Fuelrlnc.- (i.e.-, Framatome)- 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, Daniel J. Enright Site Vice President LaSalle County Station Attachment cc:
Regional Administrator - NRC Region Ill 6o0o/
NRC Senior Resident Inspector - LaSalle County Station A -
COLR LaSalle 1 Revision 7 Page 1 LaSalle Unit 1 Cycle 13 Core Operating Limits Report Revision 0 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 2 Table of Contents
- 1. References...................................................................................................................................
5
- 2. Term s and Definitions...........................................................................................................
6
- 3. General Inform ation.....................................................................................................................
7
- 4. Average Planar Linear Heat Generation Rate........................................................................
8
- 5. O perating Lim it M inim um Critical Power Ratio.......................................................................
9 5.1. M anual Flow Control M CPR Lim its................................................................................
9 5.1.1. Power-Dependent M CPR..........................................................................................
9 5.1.2. Flow - Dependent M CPR..........................................................................................
9 5.2. Autom atic Flow Control M CPR Lim its............................................................................
9 5.3. Scram Tim e..........................................................................................................................
9 5.4. Recirculation Flow Control Valve Settings.....................................................................
9
- 6. Linear Heat Generation Rate.................................................................................................
24
- 7. Rod Block M onitor......................................................................................................................
39
- 8. Traversing In-Core Probe System.......................................................................................
40 8.1
Description:
40
8.2 Bases
40
- 9. Stability Protection Setpoints..............................................................................................
41
- 10. M odes of O peration.................................................................................................................
42
- 11. M ethodology............................................................................................................................
43 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 3 List of Tables Table 4-1 MAPLHGR for bundle(s):
A10-4046B-13GV80 A10-3537B-12GV80 A10-3537B-12GV80a Al 0-3913B-1 2GV80 A10-4041B-14GV80 A 10-3924B-14G V 80......................................................................................
8 Table 4-2 MAPLHGR for bundle(s):
GE14-P1OCNAB421-18GZ-120T-150-T6-2673 GE1 4-P1 OCNAB422-19GZ-1 20T-1 50-T6-2677...................................................... 8 Table 4-3 MAPLHGR SLO multiplier for GNF and AREVA Fuel.....................................
8 Table 5-1 MCPR(P) for ATRIUM-10 Fuel, BOC to NEOC, Nominal Scram Speed (NSS)..... 10 Table 5-2 MCPR(P) for ATRIUM-10 Fuel, BOC to NEOC, Technical Specification Scram S peed (T S S S )..................................................................................................
... 11 Table 5-3 MCPR(P) for GE14 Fuel, BOC to NEOC, Nominal Scram Speed (NSS)............ 12 Table 5-4 MCPR(P) for GE14 Fuel, BOC to NEOC, Technical Specification Scram S peed (T S S S )...................................................................................................... 13 Table 5-5 MCPR(P) for ATRIUM-10 Fuel, NEOC to EOC, Nominal Scram Speed (NSS)....... 14 Table 5-6 MCPR(P) for ATRIUM-10 Fuel, NEOC to EOC, Technical Specification Scram S peed (T S S S )..................................................................................................
... 15 Table 5-7 MCPR(P) for GE14 Fuel, NEOC to EOC, Nominal Scram Speed (NSS)............ 16 Table 5-8 MCPR(P) for GE14 Fuel, NEOC to EOC, Technical Specification Scram S peed (T S S S )..................................................................................................
... 17 Table 5-9 MCPR(P) for ATRIUM-10 Fuel, Coastdown Operation, Nominal Scram S peed (N S S )................................................................................................
.... 18 Table 5-10 MCPR(P) for ATRIUM-10 Fuel, Coastdown Operation, Technical Specification Scram Speed (TSSS).........................................................................
19 Table 5-11 MCPR(P) for GE14 Fuel, Coastdown Operation, Nominal Scram Speed (N S S ).............................................................................................................
20 Table 5-12 MCPR(P) for GE14 Fuel, Coastdown Operation, Technical Specification Scram Speed (TSSS)..........................................................................................
21 Table 5-13 MCPR(F) Limits for AREVA Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control System.................... 22 Table 5-14 MCPR(F) Limits for AREVA Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with 2 or more TBV Opening via the Pressure Control System............... 22 Table 5-15 MCPR(F) Limits for AREVA Fuel, DLO and SLO, Supports Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System............ 22 Table 5-16 MCPR(F) Limits for GNF Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control System.................... 23 Table 5-17 MCPR(F) Limits for GNF Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with 2 or more TBV Opening via the Pressure Control System............ 23 Table 5-18 MCPR(F) Limits for GNF Fuel, DLO and SLO, Supports Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System............ 23 Table 6-1: LHGR Limit for GEl 4-P10CNAB421-18GZ-120T-150-T6-2673...................... 24 Table 6-2: LHGR Limit for GE14-P1OCNAB422-19GZ-120T-150-T6-2677....................... 24 Table 6-3: LHGR Limit for GEl4-P1OCNAB421-18GZ-120T-150-T6-2673, Lattice 6098........ 25 Table 6-4: LHGR Limit for GE14-P1OCNAB421-18GZ-120T-150-T6-2673, Lattice 6099........ 26 Table 6-5: LHGR Limit for GE14-PbOCNAB422-19GZ-120T-150-T6-2677, Lattice 6120........ 27 Table 6-6: LHGR Limit for GE14-P1OCNAB422-19GZ-120T-150-T6-2677, Lattice 6121........ 28 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 4 Table 6-7: LHGR Limit for AREVA ATRIUM-10 Fuel A10-4046B-13GV80 Al 0-3537B-1 2GV80 Al 0-3537B-1 2GV80a A10-3913B-12GV80 A10-4041B-14GV80 A 10-3924B-14G V 80....................................................................................... 29 Table 6-8 LHGRFAC(P) for ATRIUM-10 Fuel, BOC to NEOC, Nominal Scram Speed (N S S )...........................................................................................................
.. 3 0 Table 6-9 LHGRFAC(P) for ATRIUM-10 Fuel, BOC to NEOC, Technical Specification Scram Speed (TSSS)........................................................................................
31 Table 6-10 LHGRFAC(P) for ATRIUM-10 Fuel, NEOC to EOC, Nominal Scram Speed (N S S ).............................................................................................................
.. 3 2 Table 6-11 LHGRFAC(P) for ATRIUM-10 Fuel, NEOC to EOC, Technical Specification S cram S peed (T S S S )............................................................................................
33 Table 6-12 LHGRFAC(P) for ATRIUM-10 Fuel, Coastdown Operation, Nominal Scram Speed (N S S ).............................................................................................................
34 Table 6-13 LHGRFAC(P) for ATRIUM-10 Fuel, Coastdown Operation, Technical Specification Scram Speed (TSSS)...........................................................................
35 Table 6-14 LHGRFAC(P) for GEl4 Fuel, DLO, All Exposures, Nominal Scram Speed (NSS)/
Technical Specification Scram Speed (TSSS)............................................................ 36 Table 6-15 LHGRFAC(P) for GEl4 Fuel, SLO, All Exposures, Nominal Scram Speed (NSS)/
Technical Specification Scram Speed (TSSS).........................................................
36 Table 6-16 LHGRFAC(F) Multipliers for ATRIUM-10 Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with all TBV Opening via the Pressure Control System...... 37 Table 6-17 LHGRFAC(F) Multipliers for GEl4 Fuel, DLO, Supports Base Case, FHOOS, and Combined EOOS 1 with all TBV Opening via the Pressure Control System...................... 37 Table 6-18 LHGRFAC(F) Multipliers for GEl4 Fuel, SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with all TBV Opening via the Pressure Control System........................ 37 Table 6-19 LHGRFAC(F) Multipliers for ATRIUM-10 Fuel, DLO and SLO, Supports Base Case, FHOOS, Combined EOOS 1, Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System................................................................
38 Table 6-20 LHGRFAC(F) Multipliers for GEl4 Fuel, DLO, Supports Base Case, FHOOS, Combined EOOS 1, Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System...................................................
38 Table 6-21 LHGRFAC(F) Multipliers for GEl4 Fuel, SLO, Supports Base Case, FHOOS, Combined EOOS 1, Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System................................................................................. 38 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 5
- 1. References
- 1.
Exelon Generation Company, LLC Docket No. 50-373 LaSalle County Station, Unit 1, License No.
- 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.
AREVA Report ANP-2678 Revision 0, "LaSalle Unit 1 Cycle 13 Reload Analysis," AREVA NP Inc.,
December 2007.
- 4.
AREVA Report ANP-2620 (P) Revision 1, "LaSalle Unit 1 Cycle 13 Principal Transient Analysis Parameters", AREVA NP, Inc., October 2007.
- 5.
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.
- 6.
Framatome ANP Letter from R. G. Grummer to N. J. Carr, "Plant Startup Testing with POWERPLEX-III", RGG:04:001, January 8, 2004.
- 7.
GNF Report 0000-0017-8285-SRLR,"Supplemental Reload Licensing Report for LaSalle County Nuclear Station Unit 1 Reload 10 Cycle 11," December 2003.
- 8.
GE Document GE-NE-0000-0026-4769-00, "GE14 Fuel Design Cycle-Independent Analyses for LaSalle Unit 1 and Unit 2," Revision 0, January 2005.
- 9.
GNF Letter TGO-EXN-HA103-011, from T. Orr to R. Chin, "Transmittal of Peak Pellet LHGR Limits for LaSalle 1 Cycle 11 GE14 Bundles with Gad Suppression," July 3, 2003.
- 10. GE Document GE-NE-0000-0022-8684-R1, "Exelon LaSalle Units 1 and 2 SAFER/GESTR Loss-of-Coolant-Accident Analysis for GE14 Fuel", December 2004.
- 11. GE Document GE-NE-Al 300384-07-01, Rev. 1, "LaSalle County Station Power Uprate Project, Task 201: Reactor Power/Flow Map", September 1999.
NJC:04:031, April 20, 2004.
LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 6
- 2. Terms and Definitions APLHGR APRM ATRM10 BOC DLO ELLLA EOC EOOS FANP FFTR FHOOS GE14 GNF ICF LHGR LHGRFAC(F)
LHGRFAC(P)
LPRM MAPFAC(F)
MAPFAC(P)
MCPR(P)
MELLLA MSIV MSIVOOS NEOC NSS OLMCPR OPRM PBDA PLUOOS PPD PROOS RBM RPT RPTOOS RWE SLMCPR SLO SRVOOS TBV TBVOOS TCV TCVOOS TIP TIPOOS TSSS TSV TSVOOS Average planar linear heat generation rate Average power range monitor ATRIUM-10 fuel Beginning of cycle Dual loop operation Extended load line limit analysis End of cycle Equipment out of service Framatome Advanced Nuclear Power Final feedwater temperature reduction Feedwater heater out of service GE14C fuel Global Nuclear Fuel Increased core flow Linear heat generation rate Flow dependent LHGR multiplier Power dependent LHGR multiplier Local power range monitor Flow dependent MAPLHGR multiplier Power dependent MAPLHGR multiplier Maximum average planar linear heat generation rate Minimum critical power ratio Flow dependent MCPR Power dependent MCPR Maximum extended load line limit analysis Main steam isolation valve Main steam isolation valve out of service Near end of cycle Nominal scram speed Operating limit minimum critical power ratio Oscillation power range monitor Period based detection algorithm Power load unbalance out of service Plant Parameter Document Pressure regulator out of service Rod block monitor Recirculation pump trip 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 out of service Traversing in-core probe Traversing in-core probe out of service Technical specification scram speed Turbine stop valve Turbine stop valve out of service LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 7
- 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 Mlb/hr. Operation up to 105% rated flow is licensed for this cycle.
Licensed rated thermal power is 3489 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.
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.
Core Exposure Definitions (Reference 3):
Exposure Nomenclature Core Average Exposure (MWD/MTU)
NEOC13 31192 EOC13 34209 Maximum Core Exposure 38209 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 8
- 4. Average Planar Linear Heat Generation Rate The MAPLHGR values for the most limiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Tables 4-1 and 4-2. During single loop operation, these limits are multiplied by the SLO multiplier listed in Table 4-3.
Table 4-1 MAPLHGR for bundle(s):
Al 0-4046B-1 3GV80 Al 0-353713-1 2GV80 Al 0-3537B-1 2GV80a Al 0-3913B-1 2GV80 Al 0-4041 B-1 4GV80 Al 0-3924B-1 4GV80 (Reference 3)
Avg. Planar Exposure MAPLHGR (GWd/MT)
(kW/ft) 0.00 12.5 15.00 12.5 55.00 9.1 67.00 7.1 Table 4-2 MAPLHGR for bundle(s):
GE1 4-P1 OCNAB421-18GZ-1 20T-1 50-T6-2673 GE1 4-P1 OCNAB422-1 9GZ-1 20T-1 50-T6-2677 (Reference 7)
Avg. Planar Exposure MAPLHGR (GWd/MT)
(kW/ft) 0.00 13.40 16.00 13.40 63.50 8.00 70.00 5.00 Table 4-3 MAPLHGR SLO multiplier for GNF and AREVA Fuel (Reference 3 and 7)
Fuel~ype SLO Fuel Type_
Multiplier ATRM10 0.82 GE14 0.78 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 9
- 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 5-1 through 5-12, and is dependent on exposure, fuel type, and scram speed, in addition to power level. Tables 5-1, 5-2, 5-5, 5-6, 5-9 and 5-10 are applicable to ATRIUM-10 fuel and Tables 5-3, 5-4, 5-7, 5-8, 5-11 and 5-12 are applicable to GE14 fuel.
5.1.2. Flow - Dependent MCPR Tables 5-13 through 5-18 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 OLMCPR.
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.
To utilize the MCPR limits for Technical Specification Scram Speed (TSSS), the scram speed insertion time must be equal to or less than the values provided below.
To utilize the MCPR limits for Nominal Scram Speed (NSS), the scram speed insertion time must be equal to or less than the values provided below (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 13 was analyzed with a maximum core flow runout of 105%; therefore the recirculation pump flow control valve must be set to maintain core flow less than 105%
(113.9 Mlb/hr) for all runout events (Reference 4). This value is consistent with the analyses of Reference 3.
LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-1 MCPR(P) for ATRIUM-10 Fuel BOC to NEOC Nominal Scram Speed (NSS)
(Reference 3)
Page 10 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination MCPRp Base Case 2.21 2.21 1.55 Base Case SLO 2.22 2.22 1.56 FHOOS 2.31 2.31 1.59 1.40' 1.41
- 1.40 1.41 1.45 FHOOS SLO 2.32 2.32 Combined EOOS 1 2.34 2.34 Combined EOOS 1 SLO 2.35 2.35 Combined EOOS 2 2.34 2.34 Combined EOOS 2 SLO 2.35 2.35 Combined EOOS 3 2.34 2.34 Combined EOOS 3 SLO 2.35 2.35 1.46 1.43 1.44 1.45 1.46
- The actual value for DLO case found in Reference 3 is 1.39; however, the minimum steady state OLMCPR is 1.40 based on the cycle specific stability requirements identified in Reference 3 and is reflected above. The SLO value was revised accordingly.
LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-2 MCPR(P) for ATRIUM-10 Fuel BOC to NEOC Technical Specification Scram Speed (TSSS)
(Reference 3)
Page 11 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination Base Case 2.29 2.29 1.57 Base Case SLO 2.30 2.30 1.58 FHOOS 2.39 2.39 1.61 1.43 1.44 1.43 1.44 1.48 FHOOS SLO 2.40 2.40 Combined EOOS 1 2.39 2.39 Combined EOOS 1 SLO 2.40 2.40 Combined EOOS 2 2.35 2.35 Combined EOOS 2 SLO 2.36 2.36 Combined EOOS 3 2.40 2.40 Combined EOOS 3 SLO 2.41 2.41
__i.
1.49 i
i.
1.45 i
i.
1.46 i
i 1.47 1.48 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-3 MCPR(P) for GE14 Fuel BOC to NEOC Nominal Scram Speed (NSS)
(Reference 3)
Page 12 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination MCPRp Base Case 2.07 2.07 1.49 Base Case SLO 2.08 2.08 1.50 FHOOS 2.16 2.16 1.55 1.40
- 1.41 1.41 1.42 1.48 FHOOS SLO 2.17 2.17 Combined EOOS 1 2.24 2.24 Combined EOOS 1 SLO 2.25 2.25 Combined EOOS 2 2.24 2.24 Combined EOOS 2 SLO 2.25 2.25 Combined EOOS 3 2.24 2.24 Combined EO S 3 SLO 2.25 2.25 1.49 1.44 1.45 1.50 1.51
- The actual value for DLO case found in Reference 3 is 1.39; however, the minimum steady state OLMCPR is 1.40 based on the cycle specific stability requirements identified in Reference 3 and is reflected above. The SLO value was revised accordingly.
LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-4 MCPR(P) for GE14 Fuel BOC to NEOC Technical Specification Scram Speed (TSSS)
(Reference 3)
Page 13 EOOS Combination Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 MCPRo Base Case 2.13 2.13 1.51 Base Case SLO 2.14 2.14 1.52 FHOOS 2.22 2.22 1.57 1.41 1.42 1.45 1.46 1.52 FHOOS SLO 2.23 2.23 1.58 Combined EOOS 1 2.25 2.25 Combined EOOS 1 SLO 2.26 2.26 Combined EOOS 2 2.25 2.25 Combined EOOS 2 SLO 2.26 2.26 Combined EOOS 3 2.25 2.25 Combined EOOS 3 SLO 2.26 2.26 1.72 1.57 1.73 1.58 1.53 1.72 1.52 1.48 1.73 1.53 1.49 1.72 1.59 1.53 1.73 1.60 1.54 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-5 MCPR(P) for ATRIUM-10 Fuel NEOC to EOC Nominal Scram Speed (NSS)
(Reference 3)
Page 14 Core Thermal Power (% of rated)
EOOS Combination 0
25 60 80 80(80.1) 100 MCPRP Base Case 2.21 2.21 1.55 Base Case SLO 2.22 2.22 1.56 FHOOS 2.31 2.31 1.59 1.41 1.42 1.41 1.42 1.47 FHOOS SLO 2.32 2.32 1.60 Combined EOOS 1 2.34 2.34 Combined EOOS 1 SLO 2.35 2.35 Combined EOOS 2 2.34 2.34 Combined EOOS 2 SLO 2.35 2.35 Combined EOOS 3 2.34 2.34 Combined EOOS 3 SLO 2.35 2.35 1.73 1.52 1.74 1.53 1.48 1.73 1.49 1.46 1.74 1.50 1.47 1.73 1.52 1.46 1.74 1.53 1.47 LaSalle-Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-6 MCPR(P) for ATRIUM-10 Fuel NEOC to EOC Technical Specification Scram Speed (TSSS)
(Reference 3)
Page 15 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination MCPRp Base Case 2.29 2.29 1.57 Base Case SLO 2.30 2.30 1.58 FHOOS 2.39 2.39 1.61 1.43 1.44 1.43 1.44 1.51 FHOOS SLO 2.40 2.40 1.62 Combined EOOS 1 2.39 2.39 Combined EOOS 1 SLO 2.40 2.40 Combined EOOS 2 2.35 2.35 Combined EOOS 2 SLO 2.36 2.36 Combined EOOS 3 2.40 2.40 Combined EOOS 3 SLO 2.41 2.41 1.73 1.54 1.74 1.55 1.52 1.73 1.53 1.51 1.74 1.54 1.52 1.73 1.54 1.51 1.74 1.55 1.52 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-7 MCPR(P) for GE14 Fuel NEOC to EOC Nominal Scram Speed (NSS)
(Reference 3)
Page 16 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination MCPRp Base Case 2.07 2.07 1.49 Base Case SLO 2.08 2.08 1.50 FHOOS 2.16 2.16 1.55 1.40 1.41 1.41 1.42 1.49 FHOOS SLO 2.17 2.17 Combined EOOS 1 2.24 2.24 Combined EOOS 1 SLO 2.25 2.25 Combined EOOS 2 2.24 2.24 Combined EOOS 2 SLO 2.25 2.25 Combined EOOS 3 2.24 2.24 Combined EOOS 3 SLO 2.25 2.25 1.50 1.49 1.50 1.50 1.51 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-8 MCPR(P) for GE14 Fuel NEOC to EOC Technical Specification Scram Speed (TSSS)
(Reference 3)
Page 17 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination MCPRp Base Case 2.13 2.13 1.51 Base Case SLO 2.14 2.14 1.52 FHOOS 2.22 2.22 1.57 1.41 1.42 1.45 1.46 1.54 FHOOS SLO 2.23 2.23 1.58 Combined EOOS 1 2.25 2.25 Combined EOOS 1 SLO 2.26 2.26 Combined EOOS 2 2.25 2.25 Combined EOOS 2 SLO 2.26 2.26 Combined EOOS 3 2.25 2.25 Combined EOOS 3 SLO 2.26 2.26 1.72 1.57 1.73 1.58 1.55 1.72 1.54 1.54 1.73 1.55 1.55 1.72 1.59 1.54 1.73 1.60 1.55 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-9 MCPR(P) for ATRIUM-10 Fuel Coastdown Operation Nominal Scram Speed (NSS)
(Reference 3)
Page 18 EOOS Combination Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 MCPRP Base Case 2.21 2.21 1.55 Base Case SLO 2.22 2.22 1.56 FHOOS 2.31 2.31 1.59 1.42 1.43 1.42 1.43 1.48 FHOOS SLO 2.32 2.32 1.60 Combined EOOS 1 2.34 2.34 Combined EOOS 1 SLO 2.35 2.35 Combined EOOS 2 2.34 2.34 Combined EOOS 2 SLO 2.35 2.35 Combined EOOS 3 2.34 2.34 Combined EOOS 3 SLO 2.35 2.35 1.73 1.53 1.74 1.54 1.49 1.73 1.52 1.48 1.74 1.53 1.49 1.73 1.52 1.48 1.74 1.53 1.49 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-10 MCPR(P) for ATRIUM-10 Fuel Coastdown Operation Technical Specification Scram Speed (TSSS)
(Reference 3)
Page 19 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination MCPRp Base Case 2.29 2.29 1.57 Base Case SLO 2.30 2.30 1.58 FHOOS 2.39 2.39 1.61 1.43 1.44 1.43 1.44 1.52 FHOOS SLO 2.40 2.40 1.62 Combined EOOS 1 2.39 2.39 Combined EOOS 1 SLO 2.40 2.40 Combined EOOS 2 2.35 2.35 Combined EOOS 2 SLO 2.36 2.36 Combined EOOS 3 2.40 2.40 Combined EOOS 3 SLO 2.41 2.41 1.73 1.56 1.74 1.57 1.53 1.73 1.56 1.52 1.74 1.57 1.53 1.73 1.56 1.52 1.74 1.57 1.53 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-11 MCPR(P) for GE14 Fuel Coastdown Operation Nominal Scram Speed (NSS)
(Reference 3)
Page 20 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination MCPRp Base Case 2.07 2.07 1.49 Base Case SLO 2.08 2.08 1.50 FHOOS 2.16 2.16 1.55 1.40 1.41 1.41 1.42 1.51 FHOOS SLO 2.17 2.17 1.56 Combined EOOS 1 2.24 2.24 Combined EOOS 1 SLO 2.25 2.25 Combined EOOS 2 2.24 2.24 Combined EOOS 2 SLO 2.25 2.25 Combined EOOS 3 2.24 2.24 Combined EOOS 3 SLO 2.25 2.25 1.72 1.53 1.73 1.54 1.52 1.72 1.52 1.51 1.73 1.53 1.52 1.72 1.55 1.51 1.73 1.56 1.52 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 5-12 MCPR(P) for GE14 Fuel Coastdown Operation Technical Specification Scram Speed (TSSS)
(Reference 3)
Page 21 Core Thermal Power (% of rated)
EOOS Combination 0
25 60 80 80(80.1) )
100 MCPRp Base Case 2.13 2.13 1.51 Base Case SLO 2.14 2.14 1.52 FHOOS 2.22 2.22 1.57 1.41 1.42 1.45 1.46 1.55 FHOOS SLO 2.23 2.23 1.58 Combined EOOS 1 2.25 2.25 Combined EOOS 1 SLO 2.26 2.26 Combined EOOS 2 2.25 2.25 Combined EOOS 2 SLO 2.26 2.26 Combined EOOS 3 2.25 2.25 Combined EOOS 3 SLO 2.26 2.26 1.72 1.57 1.73 1.58 1.56 1.72 1.56 1.55 1.73 1.57 1.56 1.72 1.59 1.55 1.73 1.60 1.56 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 22 Table 5-13 MCPR(F) Limits for AREVA Fuel, DLO and SLO Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control System (Reference 3)
Flow MCPR(F)
(% rated)
Limit 105.0 1.11 100.0 1.19 30.0 1.55 0.0 1.55 Table 5-14 MCPR(F) Limits for AREVA Fuel, DLO and SLO Supports Base Case, FHOOS, and Combined EOOS 1 with 2 or more TBV Opening via the Pressure Control System (Reference 3)
Flow MCPR(F)
(% rated)
Limit 105.0 1.11 100.0 1.25 30.0 1.65 0.0 1.65 Table 5-15 MCPR(F) Limits for AREVA Fuel, DLO and SLO Supports Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System (Reference 3)
Flow MCPR(F)
(% rated)
Limit 105.0 1.11 100.0 1.35 30.0 1.80 0.0 1.80 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 23 Table 5-16 MCPR(F) Limits for GNF Fuel, DLO and SLO Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control System (Reference 3)
Flow MCPR(F)
(% rated)
Limit" 105.0 1.11 100.0 1.19 30.0 1.60 0.0 1.60 Table 5-17 MCPR(F) Limits for GNF Fuel, DLO and SLO Supports Base Case, FHOOS, and Combined EOOS 1 with 2 or more TBV Opening via the Pressure Control System (Reference 3)
Flow MCPR(F)
(% rated)
Limit 105.0 1.11 100.0 1.30 30.0 1.75 0.0 1.75 Table 5-18 MCPR(F) Limits for GNF Fuel, DLO and SLO Supports Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System (Reference 3)
Flow MCPR(F)
(% rated)
Limit 105.0 1.11 100.0 1.35 30.0 1.90 0.0 1.90 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 24
- 6. Linear Heat Generation Rate The linear heat generation rate (LHGR) limit is the product of the exposure dependent LHGR limit from Tables 6-1 through 6-7 and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), or the flow dependent LHGR Factor, LHGRFAC(F) as applicable. The LHGRFAC(P) is determined from Tables 6-8 through 6-15. The LHGRFAC(F) is determined from Table 6-16 through 6-21.
Table 6-1: LHGR Limit for GE1 4-P1 OCNAB421-18GZ-1 20T-1 50-T6-2673 (Reference 9)
Lattices 6095, 6096, 6097, and 6100 LHGR Limit kW/ft U02 Pellet Burnup LHGR Limit (GWd/MTU)
(kW/ft) 0.0 13.4 16.0 13.4 63.5 8.0 70.0 5.0 Table 6-2: LHGR Limit for GE14-P1OCNAB422-19GZ-120T-150-T6-2677 (Reference 9)
Lattices 6095, 6118, 6119, and 6122 LHGR Limit kW/ft U02 Pellet Burnup LHGR Limit (GWd/MTU)
(kW/ft) 0.0 13.4 16.0 13.4 63.5 8.0 70.0 5.0 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 25 Table 6-3: LHGR Limit for GE1 4-P1 OCNAB421-18GZ-1 20T-1 50-T6-2673 Lattice 6098 (Reference 9)
Lattice 6098 LHGR Limit kW/ft U02 Pellet Burnup LHGR Limit (GWd/MTU)
(kW/ft) 0.0000 13.4000 15.5218 13.4000 16.8142 13.3074 17.5176 13.2275 18.7876 13.0831 20.0443 12.9402 22.5182 12.659 26.1598 12.245 32.1441 11.5647 38.0565 10.8925 43.8915 10.2292 49.6458 9.5177 55.3237 8.7773 60.9382 8.1186 66.5101 6.6107 70.0000 5.0000 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 26 Table 6-4: LHGR Limit for GE14-P1OCNAB421-18GZ-120T-150-T6-2673 Lattice 6099 (Reference 9)
Lattice 6099 LHGR Limit kW/ft U02 Pellet Burnup LHGR Limit (GWd/MTU)
(kW/ft) 0.0000 13.4000 15.0262 13.4000 16.3231 13.3633 17.6075 13.2172 18.8785 13.0728 20.1351 12.9299 22.6064 12.6490 26.2427 12.2356 32.2182 11.5562 38.1199 10.8609 43.9416 10.1559 49.6801 9.4886 55.3399 8.7823 60.9347 8.1259 66.4861 6.6218 70.0000 5.0000 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 27 Table 6-5: LHGR Limit for GE14-P1OCNAB422-19GZ-120T-150-T6-2677 Lattice 6120 (Reference 9)
Lattice 6120 LHGR Limit kW/ft U02 Pellet Burnup LHGR Limit (GWd/MTU)
(kW/4!)
0.0000 13.4000 15.6543 13.4000 16.9580 13.2911 17.6320 13.2145 18.9097 13.0692 20.1735 12.9255 22.6582 12.6431 26.3052 12.2285 32.2788 11.5494 38.1764 10.8789 43.9971 10.2172 49.7379 9.5062 55.4034 8.7676 61.0066 8.1105 66.5684 6.5838 70.0000 5.0000 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 28 Table 6-6: LHGR Limit for GE14-P1OCNAB422-19GZ-120T-150-T6-2677 Lattice 6121 (Reference 9)
Lattice 6121 LHGR Limit kW/ft U02 Pellet Burnup LHGR Limit (GWd/MTU)
(kW/ft) 0.0000 13.4000 15.1319 13.4000 16.4377 13.3502 17.7308 13.2032 19.0101 13.0578 20.2742 12.9141 22.7569 12.6318 26.3988 12.2178 32.3629 11.5398 38.2490 10.8484 44.0557 10.1457 49.7801 9.4804 55.4267 8.7718 61.0096 8.1170 66.5504 6.5921 70.0000 5.0000 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 29 Table 6-7: LHGR Limit for AREVA ATRIUM-10 Fuel Al 0-40461B-1 3GV80 Al 0-35371B-1 2GV80 Al 0-3537B-1 2GV80a Al 0-3913B-1 2GV80 Al 0-4041 B-1 4GV80 Al 0-39241B-1 4GV80 (Reference 3)
Pellet Exposure LHGR Limit (GWd/MTU)
(kW/ft) 0.00 13.40 17.70 13.40 61.10 9.10 70.40 7.30 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 6-8 LHGRFAC(P) for ATRIUM-10 Fuel BOC to NEOC Nominal Scram Speed (NSS)
(Reference 3)
Page 30 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination LHGRFACp Multiplier Base Case 0.71 0.71 1.00 Base Case SLO 0.71 0.71 1.00 FHOOS 0.67 0.67 0.94 1.00 1.00 1.00 1.00 1.00 FHOOS SLO 0.67 0.67 0.94 Combined EOOS 1 0.65 0.65 Combined EOOS 1 SLO 0.65 0.65 Combined EOOS 2 0.65 0.65 Combined EOOS 2 SLO 0.65 0.65 Combined EOOS 3 0.65 0.65 Combined EOOS 3 SLO 0.65 0.65 0.89 0.96 0.89 0.96 1.00 0.89 0.98 1.00 0.89 0.98 1.00 0.89 0.95 1.00 0.89 0.95 1.00 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 6-9 LHGRFAC(P) for ATRIUM-10 Fuel BOC to NEOC Technical Specification Scram Speed (TSSS)
(Reference 3)
Page 31 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination LHGRFACp Multiplier Base Case 0.69 0.69 1.00 Base Case SLO 0.69 0.69 1.00 FHOOS 0.66 0.66 0.93 1.00 1.00 1.00 1.00 0.97 FHOOS SLO 0.66 0.66 0.93 Combined EOOS 1 0.64 0.64 Combined EOOS 1 SLO 0.64 0.64 Combined EOOS 2 0.64 0.64 Combined EOOS 2 SLO 0.64 0.64 Combined EOOS 3 0.64 0.64 Combined EOOS 3 SLO 0.64 0.64 0.89 0.93 0.89 0.93 0.97 0.89 0.96 1.00 0.89 0.96 1.00 0.89 0.93 0.97 0.89 0.93 0.97 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 6-10 LHGRFAC(P) for ATRIUM-10 Fuel NEOC to EOC Nominal Scram Speed (NSS)
(Reference 3)
Page 32 EOOS Combination Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 LHGRFACp Multiplier Base Case 0.71 0.71 1.00 Base Case SLO 0.71 0.71 1.00 FHOOS 0.67 0.67 0.94 1.00 1.00 1.00 1.00 1.00 FHOOS SLO 0.67 0.67 0.94 Combined EOOS 1 0.65 0.65 Combined EOOS 1 SLO 0.65 0.65 Combined EOOS 2 0.65 0.65 Combined EOOS 2 SLO 0.65 0.65 Combined EOOS 3 0.65 0.65 Combined EOOS 3 SLO 0.65 0.65 0.89 0.96 0.89 0.96 1.00 0.89 0.98 1.00 0.89 0.98 1.00 0.89 0.95 0.99 0.89 0.95 0.99 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 6-11 LHGRFAC(P) for ATRIUM-10 Fuel NEOC to EOC Technical Specification Scram Speed (TSSS)
(Reference 3)
Page 33 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination LHGRFACp Multiplier Base Case 0.69 0.69 1.00 Base Case SLO 0.69 0.69 1.00 FHOOS 0.66 0.66 0.93 FHC(S *1 066l 06 03.q 1.00 1.00 1.00 1.00 I I IVV* *V vvv Combined EOOS 1 0.64 0.64 Combined EOOS 1 SLO 0.64 0.64 Combined EOOS 2 0.64 0.64 Combined EOOS 2 SLO 0.64 0.64 Combined EOOS 3 0.64 0.64 Combined EOOS 3 SLO 0.64 0.64 0.89 0.93 0.97 0.89 0.93 0.97 0.89 0.96 0.97 0.89 0.96 0.97 0.89 0.93 0.97 0.89 0.93 0.97 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 6-12 LHGRFAC(P) for ATRIUM-10 Fuel Coastdown Operation Nominal Scram Speed (NSS)
(Reference 3)
Page 34 Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 EOOS Combination LHGRFACp Multiplier Base Case 0.71 0.71 1.00 Base Case SLO 0.71 0.71 1.00 FHOOS 0.67 0.67 0.94 1.00 1.00 1.00 1.00 0.98 FHOOS SLO 0.67 0.67 0.94 Combined EOOS 1 0.65 0.65 Combined EOOS 1 SLO 0.65 0.65 Combined EOOS 2 0.65 0.65 Combined EOOS 2 SLO 0.65 0.65 Combined EOOS 3 0.65 0.65 Combined EOOS 3 SLO 0.65 0.65 0.89 0.96 0.89 0.96 0.98 0.89 0.97 0.98 0.89 0.97 0.98 0.89 0.95 0.98 0.89 0.95 0.98 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Table 6-13 LHGRFAC(P) for ATRIUM-10 Fuel Coastdown Operation Technical Specification Scram Speed (TSSS)
(Reference 3)
Page 35 EOOS Combination Core Thermal Power (% of rated) 0 25 60 80 80(80.1) 100 LHGRFACp Mul oar Base Case 0.69 0.69 1.00 Base Case SLO 0.69 0.69 1.00 FHOOS 0.66 0.66 0.93 1.00 1.00 1.00 1.00 0.95 FHOOS SLO 0.66 0.66 0.93 Combined EOOS 1 0.64 0.64 Combined EOOS 1 SLO 0.64 0.64 Combined EOOS 2 0.64 0.64 Combined EOOS 2 SLO 0.64 0.64 Combined EOOS 3 0.64 0.64 Combined EOOS 3 SLO 0.64 0.64 0.89 0.91 0.89 0.91 0.95
.0.89 0.95 0.96 0.89 0.95 0.96 0.89 0.93 0.96 0.89 0.93 0.96 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 36 Table 6-14 LHGRFAC(P) for GE14 Fuel DLO, All Exposures Nominal Scram Speed (NSS)ITechnical Specification Scram Speed (TSSS)
(Reference 3)
Core Thermal Power (% of rated)
EOOS Combination 0
25 40 60 100 LHGRFACp Multiplier Base Case 0.57 0.57 0.79 1.00 FHOOS 0.52 0.52 Combined EOOS 1 0.40 0.40 0.52 Combined EOOS 2 0.40 0.40 0.52 Combined EOOS 3 0.40 0.40 0.52 S 0.79 1.00 0.99
..0.99 0.99 Table 6-15 LHGRFAC(P) for GE14 Fuel SLO, All Exposures Nominal Scram Speed (NSS)/Technical Specification Scram Speed (TSSS)
(Reference 3 and 7)
EOOS Combination Core Thermal Power (% of rated) 0 25 40 CP*
60 100 LHGRFACp Multiplier Base Case SLO 0.78 0.78 0.78 078 0.78 0.78 FHOOS SLO Combined EOOS 1 SLO Combined EOOS 2 SLO Combined EOOS 3 SLO 0.78 0.78 0.78 0.78 0.78 0.78
- CP is the cutoff power level and equal to 58.40% for Base Case SLO, 58.70% FHOOS SLO; and 73.19% for Combined EOOS 1 SLO, Combined EOOS 2 SLO and Combined EOOS 3 SLO conditions.
LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 37 Table 6-16 LHGRFAC(F) Multipliers for ATRIUM-10 Fuel, DLO and SLO Supports Base Case, FHOOS, and Combined EOOS 1 with all TBV Opening Via the Pressure Control System (Reference 3)
Flow LHGRFAC(F)
(% rated)
Multiplier 105.00 1.00 80.00 1.00 30.00 0.75 0.00 0.75 Table 6-17 LHGRFAC(F) Multipliers for GE14 Fuel, DLO Supports Base Case, FHOOS, and Combined EOOS 1 with all TBV Opening via the Pressure Control System (Reference 3)
Flow LHGRFAC(F)
(% rated)
Multiplier 105.00 1.00 75.00 1.00 30.00 0.55 0.00 0.55 Table 6-18 LHGRFAC(F) Multipliers for GE14 Fuel, SLO Supports Base Case, FHOOS, and Combined EOOS 1 with all TBV Opening via the Pressure Control System (Reference 3 and 7)
Flow LHGRFAC(F)
(% rated)
Multiplier 105.00 0.78 75.00 0.78 53.00 0.78 30.00 0.55 0.00 0.55 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 38 Table 6-19 LHGRFAC(F) Multipliers for ATRIUM-10 Fuel, DLO and SLO Supports Base Case, FHOOS, Combined EOOS 1, Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System (Reference 3)
Flow LHGRFAC(F)
(% rated)
Multiplier 105.00 1.00 80.00 1.00 30.00 0.75 0.00 0.75
. Table 6-20 LHGRFAC(F) Multipliers for GE14 Fuel, DLO Supports Base Case, FHOOS, Combined EOOS 1, Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System (Reference 3)
Flow LHGRFAC(F)
(% rated)
Multiplier 105.00 1.00 89.00 1.00 30.00 0.41 0.00 0.41 Table 6-21 LHGRFAC(F) Multipliers for GE14 Fuel, SLO Supports Base Case, FHOOS, Combined EOOS 1, Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System (Reference 3 and 7)
Flow LHGRFAC(F)
(% rated)
Multiplier 105.00 0.78 89.00 0.78 67.00 0.78 30.00 0.41 0.00 0.41 LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 39
- 7. Rod Block Monitor The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below (Reference 5):
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 0.66_W__+_48.7%
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 Mlb/hr.
LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 40
- 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:
The total number of failed and bypassed LPRMs does not exceed 50% (Reference 12).
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 adjusted using the previously calculated uncertainties, provided the following conditions are met:
(A) When there is not a prior complete TIP-calibrated data set available:
- 1. To comply With Technical Specification SR 3.3.1.1.8, LPRMs, within their calibration frequency, in locations without a TIP trace are not recalibrated,
- 2.
LPRMs in locations without a TIP trace will not be used by POWERPLEX in any core power distribution calculations, and
- 3.
The total number of out-of-service TIPs does not exceed 42% (18 channels).
(B) When there is a prior complete TIP-calibrated data set available:
- 1.
All TIP traces have previously been obtained at least once in the current operating cycle when the reactor core was operating above 20% power, (Reference 6) and
- 2.
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 monitoring or 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, is 3-dimensional BWR core monitoring software calculated data which is adjusted based on axial and radial factors calculated from previous TIP sets. 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 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 41
- 9. Stability Protection Setpoints The OPRM PBDA Trip Settings (Reference 3):
Corresponding Maximum PBDA Trip Amplitude Setpoint (Sp)
Confirmation Count Setpoint (Np) 1.11 1
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 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 42
- 10. Modes of Operation The allowed modes of operation with combinations of equipment out-of-service are as described below:
Equipment Out of Service Options (1}(2j Base Case Base Case + SLO Base Case + feedwater heater out-of-service (FHOOS) (Up to 100 degree F reduction)
Base Case + TCV slow closure + EOCRPTOOS + PROOS Base Case + TCV slow closure + EOCRPTOOS + 5 turbine bypass valves out of service (5 TBVOOS) (i.e., base case + 4)
Base Case + TCV slow closure + EOCRPTOOS + FHOOS (Up to 100 degree F reduction)
Combined EOOS 1 Base Case + TCV slow closure +EOCRPTOOS + one Stuck Closed TCV and/or Combined EQOS 2 TSV(3) + one MSIVOOS{3)
Base Case + TCV Slow Closure + EOCRPTOOS + one Stuck Closed TCV and/or TSV{3) + one MSIVOOS(3} + FHOOS (up to 100 degree reduction) + PROOS + 2 TBVOOS (i.e., base case + 1)
Base Case + TCV Slow Closure + EOCRPTOOS + one Stuck Closed TCV and/or Combined EQOS 3 TSV{3) + one MSIVOOS[3} + FHOOS (up to 100 degree reduction) + PROOS + 2 SLO TBVOOS (i.e., base case + 1) + SLO (1) Base case includes a feedwater temperature reduction of up to 30 F + 1 SRVOOS + 1 TBVOOS +
PLUOOS, and also includes 2 TIPOOS (or the equivalent number of TIP channels) 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. ICF and MELLLA are not valid during 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 at least two turbine bypass valves opening on pressure control.
[3) The one Stuck Closed TCV and/or TSV EOOS conditions assume initial power level < 85% of rated.
The one MSIVOOS condition is also supported as long as initial thermal power is maintained < 75% of the rated.
LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 43
- 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-524 (P)(A) Revision 2 and Supplements 1 and 2, "ANF Critical Power Methodology for Boiling Water Reactors," November 1990 [XN-NF-524 (P)(A)].
- 3.
ANF-913 (P)(A) Volume 1 Revision 1, and Volume 1 Supplements 2, 3, 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," August 1990.
- 4.
XN-NF-84-105 (P)(A), Volume 1 and Volume 1 Supplements 1 and 2; Volume 1 Supplement 4, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis,"
February 1987 and June 1988, respectively.
- 5.
EMF-2209 (P)(A), Revision 2, "SPCB Critical Power Correlation," September 2003.
- 6.
ANF-89-98 (P)(A), Revision 1 and Revision 1 Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," May 1995.
- 7.
EMF-85-74 (P)(A) Revision 0 and Supplement 1 (P)(A) and Supplement 2(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," February 1998.
- 8.
EMF-CC-074 (P) Volume 4 Revision 0, "BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2," August 2000.
- 9.
ANF-CC-33 (P)(A) Supplement 1 Revision 1 and Supplement 2, "HUXY: A Generalized Multirod Heatup Code with 10CFR50, Appendix K Heatup Option," August 1986 and January 1991, respectively.
- 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," June 1986.
- 11. XN-NF-85-67 (P)(A) Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel", 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," 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," March 1983.
- 14. NEDE-24011-P-A-14, June 2000 and the U.S. Supplement NEDE-24011-P-A-14-US, June 2000, "General Electric Standard Application for Reactor Fuel".
- 15. 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. EMF-2245 (P)(A), Revision 0, "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel", August 2000.
LaSalle Unit 1 Cycle 13
COLR LaSalle 1 Revision 7 Page 44
- 17. EMF-2361 (P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model", May 2001.
- 18. NEDO-32465-A, "BWR Owner's Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications", August 1996.
- 19. ANF-1358 (P)(A), Revision 3, 'The Loss of Feedwater Heating Transient in Boiling Water Reactors", September 2005.
LaSalle Unit 1 Cycle 13