RA09-002, Cycle 3 Core Operating Limits Report

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Cycle 3 Core Operating Limits Report
ML090510150
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 02/06/2009
From: Enright D
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA09-002
Download: ML090510150 (38)
v • d • e


Text

LaSalle Generating Station www.exeloncorp.com Exeln 2601 North 21st Road Nuclear Marseilles, IL 61341-9757 RA09-002 1 CFR50.59 February 6, 2009 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 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 2 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 2 Cycle 13 core, which consists of NRC approved fuel designs developed by Global Nuclear Fuel (GNF) and 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, Daniel J. Enright KJ**

  • Site Vice President LaSalle County Station Attachment Ac"(

cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - LaSalle County Station

COLR LaSalle 2 Revision 6 Page 1 LaSalle Unit 2 Cycle 13 Core Operating Limits Report Revision 0 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 2 Table of Contents

1. References .................. ....................................... 5
2. Terms and Definitions ................................................. 6
3. General Information ................................................... 7
4. Average Planar Linear Heat Generation Rate ....................................................................... 8
5. Operating Limit Minimum Critical Power Ratio ......... .................................................................. 9 5.1. Manual Flow Control MCPR Limits ................................................................................ 9 5.1.1. Power-Dependent MCPR ......................................................................................... 9 5.1.2. Flow - Dependent MCPR .......................................................................................... 9 5.2. Automatic Flow Control MCPR Limits .............................................................................. 9 5.3. Scram Time ......................................... . . . ................................. 9 5.4. Recirculation Flow Control Valve Settings ....................................................................... 9
6. Linear Heat Generation Rate .................................................................................................. 20
7. Rod Block Monitor ...................................................................................................................... 32
8. Traversing In-Core Probe System ....................................................................................... 33 8.1

Description:

......................................................................................................................... 33

8.2 Bases

................................................................................................................................. 33

9. Stability Protection Setpoints .............................................................................................. 34
10. Modes of Operation ................................................................................................................. 35
11. Methodology ............. k...................................... ............ ........... .............. 36 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 3 List of Tables Table 4-1 MAPLHGR for bundle(s):.....

Al-0-4061 B-13GV80 A10-3561B-12GV80 Al 0-4029B-1 3GV80 A10-4020B-16GV80 A10-3847B-16GV80 DXM-3862B-14GV80 DXM-3881B-14GV80 A10-3537B -12G V 80 ....................................................................................... 8 Table 4-2 MAPLHGR for bundle(s):

GEl 4-P1 OCNAB406-18GZ-1 20T- 150-T6-2823 G El 4-P1 OCNAB407-16GZ-1 20T-1 50-T6-2822 ...................................................... 8 Table 4-3 MAPLHGR SLO multiplier for GNF and AREVA Fuel ......................................... 8 Table 5-1 MCPR(P) for ATRIUM-10 /ATRIUM 1OXM Fuel, BOC to EOC, Nominal Scram S peed (N S S ) .................................................................................................. . .. 10 Table 5-2 MCPR(P) for ATRIUM-10 /ATRIUM 1OXM Fuel, BOC to EOC, Technical Specification Scram Speed (TSSS) .......................................................................... 11 Table 5-3 MCPR(P) for GEl4 Fuel, BOC to EOC, Nominal Scram Speed (NSS) .............. 12 Table 5-4 MCPR(P) for GE14 Fuel, BOC to EOC, Technical Specification Scram Speed (TSS S) .................................................................................................... 13 Table 5-5 MCPR(P) for ATRIUM-10 / ATRIUM 1OXM Fuel, Coastdown Operation, Nominal Scram Speed (N SS) ........................................................................................... 14 Table 5-6 MCPR(P) for ATRIUM-10 / ATRIUM IOXM Fuel, Coastdown Operation, Technical Specification Scram Speed (TSSS) .......................................................................... 15 Table 5-7 MCPR(P) for GE14 Fuel, Coastdown Operation, Nominal Scram Speed (N S S) .............................................................................................................. . . 16 Table 5-8 MCPR(P) for GEl4 Fuel, Coastdown Operation, Technical Specification Scram Speed (TSSS) ............................................................................................ 17 Table 5-9 MCPR(F) Limits for ATRIUM-10 Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control System ............... 18 Table 5-10 MCPR(F) Limits for ATRIUM-10 Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with 2 or more TBV Opening via the Pressure Control System ......... 18 Table 5-11 MCPR(F) Limits for ATRIUM-10 Fuel, DLO and SLO, Supports Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System ......... 18 Table 5-12 MCPR(F) Limits for GE14/ATRIUM 1OXM Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with All TBV Opening via the Pressure Control S ystem ............................................................................................................ .. 19 Table 5-13 MCPR(F) Limits for GE14/ATRIUM 1OXM Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with 2 or more TBV Opening via the Pressure C ontrol S ystem ..................................................................................................... 19 Table 5-14 MCPR(F) Limits for GE14 / ATRIUM IOXM Fuel, DLO and SLO, Supports Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure C ontrol System .................................................................................................. 19 Table 6-1: LHGR Limit for GEl 4-P 1OCNAB406-18GZ-1 20T-1 50-T6-2823 ...................... 20 Table 6-2: LHGR Limit for GE14-P1OCNAB407-16GZ-120T-150-T6-2822 ...................... 20 Table 6-3: LHGR Limit for GE14-PIOCNAB406-18GZ-120T-150-T6-2823, Lattice 6815 ........ 21 Table 6-4: LHGR Limit for GE14-P10CNAB407-16GZ-120T-150-T6-2822, Lattice 6810 ........ 22 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 4 Table 6-5: LHGR Limit for AREVA ATRIUM-10 / ATRIUM 10XM Fuel A10-4061B-13GV80 A10-3561B-12GV80 Al 0-4029B-1 3GV80 .

Al0-4020B-16GV80 A10-3847B-16GV80 DXM-3862B-14GV80 DXM-3881B-14GV80 A10-3537B-12G V80 ..................................................................................... 23 Table 6-6 LHGRFAC(P) for ATRIUM-1 0/ATRIUM 1OXM Fuel, BOC to EOC, Nominal Scram Speed (N SS ) .................................................................................................... 24 Table 6-7 LHGRFAC(P) for ATRIUM-10 / ATRIUM 1OXM Fuel, BOC to EOC, Technical Specification Scram Speed (TSSS) ........................................ 25 Table 6-8 LHGRFAC(P) for ATRIUM-10 / ATRIUM 1OXM Fuel, Coastdown Operation, Nominal Scram Speed (NSS) ............................................................................................ 26 Table 6-9 LHGRFAC(P) for ATRIUM-10 / ATRIUM 1OXM Fuel, Coastdown Operation, Technical Specification Scram Speed (TSSS) ........................................................................ 27 Table 6-10 LHGRFAC(P) for GEl4 Fuel, DLO, All Exposures, Nominal Scram Speed (NSS)/

Technical Specification Scram Speed (TSSS) ....................................................... .28 Table 6-11 LHGRFAC(P) for GEl4 Fuel, SLO, All Exposures, Nominal Scram Speed (NSS)/

Technical Specification Scram Speed (TSSS) ............................................................ 28 Table 6-12 LHGRFAC(F) Multipliers for ATRIUM-10 / ATRIUM 1OXM Fuel, DLO and SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with all TBV Opening via the Pressure C ontrol System ................................................................................................... 29 Table 6-13 LHGRFAC(F) Multipliers for GE14 Fuel, DLO, Supports Base Case, FHOOS, and Combined EOOS 1 with all TBV Opening via the Pressure Control System ...................... 29 Table 6-14 LHGRFAC(F) Multipliers for GE14 Fuel, SLO, Supports Base Case, FHOOS, and Combined EOOS 1 with all TBV Opening via the Pressure Control System ..................... 29 Table 6-15 LHGRFAC(F) Multipliers for ATRIUM-10 / ATRIUM 10XM Fuel, DLO and SLO, Supports Base Case, FHOOS, Combined EOOS 1 with 2 or more TBV Opening via the Pressure Control System ................................................................................................... 30 Table 6-16 LHGRFAC(F) Multipliers for ATRIUM-10 / ATRIUM 10XM Fuel, DLO and SLO, Supports Combined EOOS 2 and Combined EOOS 3 with 2 or more TBV Opening via the Pressure Control System ................................................................... 30 Table 6-17 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 ............................................................................ 31 Table 6-18 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 ............................................................................ 31 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 5

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 Tech Specs, October 3, 1988.
3. AREVA Report ANP-2774 Revision 0, "LaSalle Unit 2 Cycle 13 Reload Analysis," AREVA NP Inc., December 2008.
4. AREVA Report ANP-2723 (P) Revision 0, "LaSalle Unit 2 Cycle 13 Principal Transient Analysis Parameters", AREVA NP, Inc., June 2008.
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 NJC:04:001, from N. Carr to M. Hsaio, "Transmittal of Information for Plant Startup Testing for POWERPLEX-lIl", January 12, 2004.
7. GNF Report 0000-0034-6783-SRLR, Rev. 1, "Supplemental Reload Licensing Report for LaSalle Unit 2 Reload 10 Cycle 11," February 2005.
8. GNF Letter FRL-EXN-HA2-04-006, from F. Russell Lindquist to C. de la Hoz, T"ransmittal of Peak Pellet LHGR Limits for LaSalle Unit 2 Cycle 11 GE14 Bundles with Gad Suppression," August 5, 2004.
9. Framatome ANP Letter from N. Carr to M. Hsiao, "Startup with TIP Equipment Out of Service", NJC:04:031, April 20, 2004.

LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 6

2. Terms and Definitions APLHGR Average planar linear heat generation rate APRM Average power range monitor ATRM10 ATRIUM-10 fuel BOC Beginning of cycle DLO Dual loop operation ELLLA Extended load line limit analysis EOC End of cycle EOOS Equipment out of service FFTR Final feedwater temperature reduction FHOOS Feedwater heater out of service GEl4 GE14C fuel GNF Global Nuclear Fuel ICF Increased core flow LHGR Linear heat generation rate LHGRFAC(F) Flow dependent LHGR multiplier LHGRFAC(P) Power dependent LHGR multiplier LPRM Local power range monitor MAPFAC(F) Flow dependent MAPLHGR multiplier MAPFAC(P) Power dependent MAPLHGR multiplier MAPLHGR Maximum average planar linear heat generation rate MCE Maximum Core Exposure MCPR Minimum critical power ratio MCPR(F) Flow dependent MCPR MCPR(P) Power dependent MCPR MELLLA Maximum extended load line limit analysis MSIV Main steam isolation valve MSIVOOS Main steam isolation valve out of service NEOC Near end of cycle NSS Nominal scram speed OLMCPR Operating limit minimum critical power ratio OPRM Oscillation power range monitor PBDA Period based detection algorithm PLUOOS Power load unbalance out of service PPD Plant Parameter Document PROOS Pressure regulator out of service RBM Rod block monitor RPT Recirculation pump trip RPTOOS Recirculation pump trip out of service RWE Rod withdrawal error SLMCPR Safety limit minimum critical power ratio SLO Single loop operation SRVOOS Safety-relief valve out of service TBV Turbine bypass valve TBVOOS Turbine bypass valve out of service TCV Turbine control valve TCVOOS Turbine control valve out of service TIP Traversing in-core probe TIPOOS Traversing in-core probe out of service TSSS Technical specification scram speed TSV Turbine stop valve TSVOOS Turbine stop valve out of service LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 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 (including the shaded areas of tables, 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 Base case and Combined EOOS 3 are only provided for online monitoring. Additional thermal limit sets can be provided for online monitoring as necessary.

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 (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.

Core Exposure Definitions (Reference 3):

LaSalle Unit 2 Cycle 13

I.

COLR LaSalle 2 Revision 6 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):

Al0-4061B-13GV80 Al 0-3561 B-1 2GV80 Al 0-40298-13GV80 Al 0-4020B-1 6GV80 Al0-3847B-16GV80 DXM-3862B-14GV80 DXM-3881 B-1 4GV80 A10-3537B-12GV80 (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):

GE14-PIOCNAB406-18GZ-120T-150-T6-2823 GE14-P1OCNAB407-16GZ-120T-150-T6-2822 (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)

Fulfp S FuelType SLO Multipliel ATRM10 /ATRIUM 1OXM 0.82 GE14 0.78 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 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 5-8, and is dependent on exposure, fuel type, and scram speed, in addition to power level. Tables 5-1, 5-2, 5-5 and 5-6 are applicable to ATRIUM-10 / ATRIUM 1OXM fuel and Tables 5-3, 5-4, 5-7 and 5-8 are applicable to GE14 fuel.

5.1.2. Flow - Dependent MCPR Tables 5-9 through 5-14 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 108%; therefore the recirculation pump flow control valve must be set to maintain core flow less than 108%

(117.18 MIb/hr) for all runout events (Reference 4). This value is consistent with the analyses of Reference 3.

LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 10 Table 5-1 MCPR(P) for ATRIUM-10/ ATRIUM 1OXM Fuel BOC to EOC Nominal Scram Speed (NSS)

(Reference 3)

Core Thermal Power (%M1 rated)

EO08 Combination 0 25 60 80 80(60.01) 100 MCPR, Base Case 2.29 2.29 1.52 1.40 Base Case SLO 2.30 2.30 1.53 *, .. 1.41 FOS2.41 2.411.6.4 FHOOS SLO 2.42 2.42 1.5 1.4 *___

Combined EOOS 1 2.41 2.41 1.75 1.51 1.47 Combined EOOS 1 SLO 2.42 2.42 1.76 1.52 1.48 Combined EOOS 2 2.38 2.38 1.75 1.50 1.48 Combined EQOS 2 SL 2.39 2.39 .1.76 1.51 1.47 Combined EOOS 3 2.41 2.41 1.75 1.51 1.46 Combined EOOS3 SLO 2.42 2.42: 1.76 1.52 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 trip setpoint identified in Reference 3. The SLO value was revised accordingly.

LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 11 Table 5-2 MCPR(P) for ATRIUM-101 ATRIUM 1OXM Fuel BOC to EOC Technical Specification Scram Speed (TSSS)

(Reference 3)

Care Thermal Power (% of rated)

EOOS Combination 0 25 60 80 80(60.01) 100 MCPRP Base Case 2.39 2.39. 1.54 1.42 Base Case SLO 2.40 2.40 1.55". 1.43 FHOOS 2,51 2.51 1.58 1,42 FHOOS SLO 2.52 2.52 1.59 ... 1.43 Combined EOOS 1 2.51 2,51 1,75 1.53: 1.50 Combined EOOS 1 SLO 2.52 2.52 1.76 1.54 1.51 Combined EOOS 2 2.39 2.39 175 15 1.50 Combined EGOS 2 SLO 2.40 2.40 1.76 1.54 1.51 Combined EOOS 3 2.51 2.51 1. 1.53 1.50 Combined EOOS 3 SLO 2.52 2.52 1.76 1.54 1.51 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 12 Table 5-3 MCPR(P) for GE14 Fuel BOC to EOC Nominal Scram Speed (NSS)

(Reference 3)

Core Thermal Power (%of rated)

EOOS Combination 0 60 80 80(60.01) 100 MCPRP Base Case 2.09 2.09 1.48 j 1.40 Base Case SLO 2.10 2.10 1.49 W 1.41 FHOOS 2.18 2.18 151 1.41 FHOOS SLO 2.19 2.19 1.52,* 1.42 Combined EOOS 1 SLO 2.25 2.2545 1.7C E 12. 1.51 Combined EOOS 2 2.24 2.24 ..

Combined EOOS 2 SLO 2.25 2.25. 1.75 1.51 1.51 Combined EOOS 3 2.24 2.24

  • 1.74 1.50 1.50 Combined EOOS 3 SLO 2.25 2.25 .. 1.75 1.51 1.51
  • 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 trip setpoint identified in Reference 3. The SLO value was revised accordingly.

LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 13 Table 5-4 MCPR(P) for GE14 Fuel BOC to EOC Technical Specification Scram Speed (TSSS)

(Reference 3)

Core Thermal Power (% of rated)

EOOS Combination 0 25 60 80 80(80.01) 100 MCPRp Base Case 2.18 2.16 151 1.41 Base Case SLO 2.17 2.17 1.52 1.42 FHOOS 2.26 2.26 1.57 4 1.41 FHOOSLO 27 27 18 .1.42 Combined EOOS 1 SLO 2.27 2.27 Combinsed ECOS 2 2.26 2.26 1.74 1.4 1.54 Combined EOOS 2 2.26 2.26

  • 1.74 1,.54 1.54 Combined EOOS 2 SLO 2.27 2.27 17 .515 Combined Eoos 2 sL~o 2.27 2.27 I
  • 1.75 1.55 1.55 Combined EQOS 3 2.26 2.26 1.54 Combined EOOS 3 SLO 2.27 2.27 1.75 1.55 1.

LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 14 Table 5-5 MCPR(P) for ATRIUM-101 ATRIUM 1OXM Fuel Coastdown Operation Nominal Scram Speed (NSS)

(Reference 3)

Core Thermal Power (% of rated EOOS Combiation 025 60 80 50(8.01) 100 MCPRP BaseCase 2.29 2.29 1.52 1.41 Base Case sLO 2.30 2.30 1.53 1.42 FHOOS 2.41 2.41 1.56 1,41 FHOOSSLO, 2.42 2.42 1.57 ~ .1.42 Combined EOOS 1, 2.41 2.41 1.75 1.53 1.48 Combibned EOOS 1 SLO 2.42 2.4217154.4 Combined EOOS 2 2.38 2.38 1.75 1.51 1.48 Combined EOOS 2 SLO 2.39, 2.39 1.76 1.52 1.49 Combined £00s3 2.41 2.41 . 1.75 1.52 1.48 Combined EOM 3 SLO 2.42 2.42 1.76 1.53 1.49 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 15 Table 5-6 MCPR(P) for ATRIUM-100 ATRIUM 1OXM Fuel Coastdown Operation Technical Specification Scram Speed (TSSS)

(Reference-3)..

Core Thermal Power (% of rated)

EOOS Combination 0 60 80 80(80 01 ) 100 MCPRP Base Case 2.39 2-3 11.42 Base Case SLO 2.40, 2.40 1.55 - 1.43 Combined EOOS1 2.51 2.51 1.5 1.54 CombinedEOOS SLO 2.52 2.52 1.52 Combined EOOS2 2.39 2.39 175 1.55 1.51 Combined EOOS 2 SLO 2.40 2.40 1.78 1.56 1.52 Combined EOOS 3 2.51 2.51 1.75 1.55 1.51 Combined EOOS 3 SLO 2.52 2.52 1.78 1.56 1.52 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 16 Table 5-7 MCPR(P) for GE14 Fuel Coastdown Operation Nominal Scram Speed (NSS)

(Reference 3)

  • 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 trip setpoint identified in Reference 3. The SLO value was revised accordingly.

LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 17 Table 5-8 MCPR(P) for GE14 Fuel Coastdown Operation Technical Specification Scram Speed (TSSS)

(Reference 3)

Core Thermal Power (%of rated)

EOOS Combination 0 25 80 80 80(80.01) 100 MCPIP 1.41 Base Case 2.16 2.16 1.51 1.42 Base Case SLO 2.17 2.17 1.52 1.41 FHOOS 2.26 2.26 1.57 wAv*,A'.OIA 2I27 2.27 1,58 1.42 i, vw 1.55 Combined EOOS 1 2.26 2.26

_______ 4. 4.

Combined EOOS 1 SL0 2.27 2.27 1.56

4. 4.

Combined EOOS 2 2.26 2.28 1.55 Combined EOOS 2 SLO 2.27: 2.27 1.75 1.57 1.56 Combined EOOS 3 2.26 2.26 4.75 1.57 1.55 2.27 2.27 1.75 1.57 1.56 Combined EOOS 3 SLO LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 18 Table 5-9 MCPR(F) Limits 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 MCPR(F)

(% rated) Limit 108.0 1.15 40.0 1.65 0.0 1.65 Table 5-10 MCPR(F) Limits for ATRIUM-10 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 108.0 1.25 40.0 1.70 0.0 1.70 Table 5-11 MCPR(F) Limits for ATRIUM-10 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 108.0 1.30 40.0 1.80 0.0 1.80 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 19 Table 5-12 MCPR(F) Limits for GE14 / ATRIUM 1OXM 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 108.0 1.15 40.0 1.70 0.0 1.70 Table 5-13 MCPR(F) Limits for GEl 41 ATRIUM 1 OXM 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 108.0 1.25 40.0 1.75 0.0 1.75 Table 5-14 MCPR(F) Limits for GE14 / ATRIUM 1OXM 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)

FlowI MCPR(F)

(% rated) Limit 108.0 1.30 40.0 1.90 0.0 1.90 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 20

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 6-5 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 6-6 through 6-11. The LHGRFAC(F) is determined from Table 6-12 through 6-18.

Table 6-1: LHGR Limit for GE14-P1OCNAB406-18GZ-120T-150-T6-2823 (Reference 8)

Lattices 6806, 6812, 6813, 6814 and 6816 LHGR Limit kW/ft 6806: P1OCNAL071-NOG-120T-T6-6806 6812: P1OCNAL435-18G7.0-120T-T6-6812 6813: P1 OCNAL435-6G7.0/9G6.0-120T-T6-6813 6814: P1OCNAL429-6G7.0/9G6.0-120T-E-T6-6814 6816: P1OCNAL071-18GE-120T-V-T6-6816 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-P1OCNAB407-16GZ-120T-150-T6-2822 (Reference 8)

Lattices 6806, 6807, 6808, 6809 and 6811 LHGR Limit kW/ft 6806: P1OCNAL071-NOG-120T-T6-6806 6807: P1OCNAL437-6G8.0/10G7.0-120T-T6-6807 6808: P1OCNAL437-2G8.0/7G7.0/5G6.0-120T-T6-6808 6809: P1OCNAL430-2G8.0/7G7.0/5G6.0-120T-E-T6-6809 6811: P1OCNAL071-16GE-120T-V-T6-6811 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 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 21 Table 6-3 LHGR Limit for: GE14-P1OCNAB406-18GZ-120T-150-T6-2823, Lattice 6815 (Reference 8)

Lattice 6815 LHGR Limit kW/ft P1 OCNAL429-6G7.0/9G6.0-120T-V-T6-6815 U02 Pellet Burnup LHGR Limit (GWd/MTU) (kW/ft) 0.0 13.40 16.0 13.40 17.3 13.25 18.5 13.11 19.8 12.97 21.8 12.74 25.5 12.32 31.5 11.63 37.6 10.95 43.5 10.27 49.4 9.61 55.1 8.89 60.8 8.24 66.5 6.63 70.0 5.00 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 22 Table 6-4 LHGR Limit for GE14-P1OCNAB407-16GZ-120T-150-T6-2822, Lattice 6810

. . .. . . .. . (Reference 8)..

Lattice 6810 LHGR Limit kW/ft P1OCNAL430-2G8.O/7G7.015G6.0-120T-V-T6-6810 U02 Pellet Burnup LHGR Limit (GWdIMTU) kWft 0.0 13.40 14.8 13.40 16.1 13.39 17.4 13.24 18.6 13.10 19.9 12.96 21.7 12.75 25.4 12.33 31.4 11.64 37.4 10.96 43.4 10.29 49.2 9.62 55.0 8.91 60.7 8.26 66.4 6.68 70.0 5.00 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 23 Table 6-5: LHGR Limit for AREVA ATRIUM-10/ ATRIUM 1OXM Fuel Al 0-4061 B-1 3GV80

. A1 0-3561B-12GV80- .

Al0-4029B-13GV80 Al 0-4020B-1 6GV80 Al 0-38471B-1 6GV80 DXM-3862B-14GV80 DXM-3881B-14GV80 Al 0-3537B-1 2GV80 (Reference 3)

Pellet Exposure LHGR Limit (GWd/MTU) (kWtft) 0.00 13.40 17.70 13.40 61.10 9.10 70.40 7.30 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 24 Table 6-6 LHGRFAC(P) for ATRIUM-10 / ATRIUM 1OXM Fuel BOC to EOC Nominal Scram Speed (NSS)

(Reference 3)

Core Thermal Power (% of ra*t)

EOOS Combination 025 60 80 80(80.01) 100 LHGRFACp Multiplier Base Case 0.67 0.67 1 00 1.00 Base Case SLO 0.67 0,67 1.00.

FHOOS 0.64 0.04 0.90 FHOOS SLO 0.64 0:64 0.95 0.. 1.00 Combined EOOS 2 0.64 0.64 o..0 0..00 Combined EOOS 2 SLO 0.64 0.64 0.89. 0.96 1.00 Combined EOOS 3 0.64 0.64 0.89 0.95 1.00 Combined EOOS3 SLO 0.64 0.64 0.89 0.99 1.00 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 25 Table 6-7 LHGRFAC(P) for ATRIUM-1 0/ ATRIUM 1OXM Fuel BOC to EOC Technical Specification Scram Speed (TSSS)

(Reference 3)

Core Thermal Power (% of rated)

EOOS Combination 0 25 so I o 80(80,01) 100 LHGRFACp Multiplier Base Case 0.r 0.60 .... 1o0 Base CaseSLO 0.66 0;66 1100 1.00 FHOOS 0.63 063 0.93.00 FHOOS SLO 0.63 0,63 0.93, 1.00 Combined EoOS 1 0.63, 0.63 .0.89. 0.95 o.98 Combined EOOS iSLO 0.63 0.63 0.89 0.95 0.98 Combined EOOS 2 0.64 0.64 0.89 0.97 0.98 Combined EOOS 2 SLO 0.64 0.64 0.89 0.97 0.98 Combined EOOS 3 0,63 0.63 089 0.93 0.97 Combined EOOS 3 SLO 0.63 0.63 0.89 0.93 0.97 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 26 Table 6-8 LHGRFAC(P) for ATRIUM-1 0 ATRIUM 1OXM Fuel Coastdown Operation Nominal Scram Speed (NSS)

(Reference 3)

Core Thermal Power (% at rated)

EOOS CombInation 0 , 2S 60 1 80 8....01) 100 LHGRFAC NMltipler 1.00 Base Case 0.67 0.67 1.00 Base Case SLO 0.67 0.67 1.00 1.00 FHOOS 0.64 0.64 0.95 1.00 FHA ' VW WI WVVV LO 064 0.64 0.95 1.00 Combined EOOS 1 0.64. 0.64 0.89 .98 0o.99 Combined EOOS 1 SLO 0.64 0.64 0.89 0.96 0.99ý Combined Eoo$62 0.64 0.64 0.5 0.9 0.99 Combined EOOS 2 SLO 0.64 0.64 0.890 0.96 099 Combined EOOS 3 0.64 0.64 0.89 0195 0.99 Combined EOOS 3 SLO 0.64 0.64 0.89 0.95 0.99 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 27 Table 6-9 LHGRFAC(P) for ATRIUM-10 / ATRIUM 1OXM Fuel Coastdown Operation Technical Specification Scram Speed (TSSS)

(Reference 3)

Core Thermal Power (% of rated)

EOOS Combination 0 25 1 60 80 w I o°w) 100 LUGRFACP Multiplier Bs C06 1.00 Base Case 0.66 0.66 1.00 1.00 Base Case SO 0.63 0.63 1o.9 FHOOS j 0.83 0.63 0.93 1.00 1.00 FHOOS SLO 0.63 0.63 0-93 0.96 CombIned EOOS 1 0.83 0.83

_______ 4. 4. 0.96 0.96 Combined EOOS 1 SLO 0.63 0.63

________ 4 1~ 0.97 Combined EOOS 2 0.64 0.64 0.97

4. 1 0.97 Combined EOOS 2 SLO 0.64 0.64 0.97

________ 4 0.97

.0.97 Combined EOOS 3 0.63 0.83

________ .4 .4 0.97 Combined EOOS 3 SLO 0.63 0.63 0.97

... ... .... . . II I LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 28 Table 6-10 LHGRFAC(P) for GE14 Fuel DLO, All Exposures Nominal Scram Speed (NSS)fTechnical Specification Scram Speed (TSSS)

(Reference 3)

Core Thermal Power (% of rated)

EOOS Combination 0 25 40 60 100 Lk-GRFACp Multiplier_

Base Case 0.52 0.52 01.00 FHOOS 0.48 0.48 X; 0.79 1.00 Combined EOOS 1 0.40 0.40 0.52 VJR 1.00 Combined EOOS 2 0.40 0.40 0.52 1.00 Combined EOOS 3 0.40 0.40 0.52 1.00 Table 6-11 LHGRFAC(P) for GE14 Fuel SLO, All Exposures Nominal Scram Speed (NSS)/Technical Specification Scram Speed (TSSS)

(Reference 3 and 7)

  • CP Is the cutoff power level and equal to 58.70% for Base Case SLO, 58.87% FHOOS SLO; and 72.50% for Combined EOOS 1 SLO, Combined EOOS 2 SLO and Combined EOOS 3 SLO conditions.

LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 29 Table 6-12 LHGRFAC(F) Multipliers for ATRIUM-10/ ATRIUM 1OXM 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) I Multiplier 108.00 1.00 56.00 1.00 30.00 0.85 0.00 0.85 Table 6-13 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 108.00 1.00 83.60 1.00 30.00 0.55 0.00 0.55 Table 6-14 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 108.00 0.78 83.60 0.78 57.40 0.78 30.00 0.55 0.00 0.55 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 30 Table 6-15 LHGRFAC(F) Multipliers for ATRIUM-1 0) ATRIUM 1 OXM Fuel, DLO and SLO Supports Base Case, FHOOS, Combined EOOS 1 with 2 or more TBV Opening via the Pressure Control System (Reference 3)

Flow LHGRFAC(F)

(% rated) Multiplier 108.00 1.00 80.00 1.00 30.00 0.72 0.00 0.72 Table 6-16 LHGRFAC(F) Multipliers for ATRIUM-1 0/ ATRIUM 1OXM 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 LHGRFAC(F)

(% rated) Multiplier 108.00 1.00 96.00 1.00 30.00 0.67 0.00 0.67 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 31 Table 6-17 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 108.00 1.00 100.20 1.00 30.00 0.41 0.00 0.41 Table 6-18 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 (Reference 3 and 7)

Flow LHGRFAC(F)

(% rated) Multiplier 108.00 0.78 100.20 0.78 74.02 0.78 30.00 0.41 0.00 0.41 LaSalle Unit 2 Cycle 13

COLR LaSalle 2 Revision 6 Page 32

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 1 _ __

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.

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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 9).

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).

(8) When there is aprior 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.

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COLR LaSalle 2 Revision 6 Page 34

9. Stability Protection Setpoints The OPRM PBDA Trip Settings (Reference 3):

Corresponding Maximum PBDA Trip Amplitude Setpoint (Sp) 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.

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COLR LaSalle 2 Revision 6 Page 35

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 p1)2)[41 Thermal Limit set Base Case Base Base Case + SLO Base SLO Base Case + feedwater heater out-of-service (FHOOS) (Up to 100 degree F FHOOS reduction) ...

Base Case + TCV slow closure + EOCRPTOOS + PROOS Base Case + TCV slow closure + EOCRPTOOS + 5 turbine bypass valves out of Combined EOOS 1 service (5 TBVOOS) (i.e., base case + 4)

Base Case + TCV slow closure + EOCRPTOOS + FHOOS (Up to 100 degree F reduction)

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 TSV(3) + one MSIVOOS(3) + FHOOS (up to 100 degree reduction) + PROOS + 2 C n O TBVOOS (i.e., base case + 1) + SLO 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. 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 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 -585% of rated.

The one MSIVOOS condition is also supported as long as initial thermal power is maintained s 75% of the rated.

(4) The + sign that is used in the Equipment Out of Service Options descriptions designates an "and/or".

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COLR LaSalle 2 Revision 6 Page 36

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)I.
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.

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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.

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