ML16193A595

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Cycle 16, Revision 4 Core Operating Limits Report
ML16193A595
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 07/08/2016
From: Trafton W
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 16-039 COLR LaSalle 2, Rev. 14
Download: ML16193A595 (36)
v • d • e


Text

LaSalle County StaNon C , + (- r- 2601 North 21 Road Marseilles,1L61341 J L]l ll QI UI ic 815-415-2000 Telephone www.exeloncorp.com RA1 6-039 10 CFR 50.4 July 8,2016 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 16 Core Operating Limits Report (COLR)

In accordance with LaSalle County Station (LSCS) Technical Specifications (TS) 5.6.5.d, CORE OPERATING LIMITS REPORT (COLR), attached is a copy of Revision 4 of the COLR for Unit 2. This report was revised for LSCS Unit 2, Cycle 16 to update thermal limits and references to incorporate the mid-cycle TRACG ADO and GS3 analysis.

There are no regulatory commitments contained within this letter.

Should you have any questions concerning this submittal, please contact Mr. Guy V. Ford, Jr.,

Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, William J. rafton Site Vice President LaSalle County Station

Attachment:

Core Operating Limits Report for LaSalle Unit 2 Cycle 16 Revision 4 cc: Regional Administrator NRC Region Ill NRC Senior Resident Inspector LaSalle County Station

COLR LaSalle2 Revision 14 Page 1 of 21 Core Operating Limits Report for LaSalle Unit 2 Cycle 16 Revision 4 LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 2 of 21 Table of Contents Revision History 3 List of Tables 4

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. Scram Time 9 5.3. Recirculation Flow Control Valve Settings 10 5.4. OLMCPR Requirements with Lost Jet Pump Plug Seals 10
6. Linear Heat Generation Rate 14
7. Rod Block Monitor 17
8. Traversing In-Core Probe System 18 8.1. Description 18 8.2. Bases 18
9. Stability Protection Setpoints 19
10. Modes of Operation 20
11. Methodology 21 LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 3 of 21 Revision History Record of LaSalle 2 Cycle 16 COLR Revisions Revision Description 10 Initial issuance for L2C16 11 Add short term operational limits to account for potential peripheral orifice blockage due to lost jet pump plug seals (Appendix A) and longer term operational limit due to potential lower tie plate blockage (reduced MFLCPR limit) 12 Add clarification in Appendix A to add FWHOOS to the list of EDOS that are exempted from the requirement to be in service in the Base Case 13 Remove Appendix A and add this revision list 14 Update thermal limits and References to incorporate the mid-cycle TRACG AOO and GS3 analysis, delete Reference 2 because it is not needed, and add Reference 15.

LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 4 of 21 List of Tables 3-1 Cycle Exposure Range Definitions 7 4-1 MAPLHGR for GNF2 and GNF3 Fuel 8 4-2 MAPLHGR for ATRIUM-b and ATRIUM-1OXM Fuel 8 4-3 MAPLHGR SLO Multiplier for GNF2, GNF3, ATRIUM-i 0, and ATRIUM-i OXM Fuel, BOC to EOC 8 5-I Scram Times Required for Option A and Option B Application at Notch Position 39 10 5-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) for GNF2, GNF3, ATRIUM-i 0, and ATRIUM-1OXM Fuel 11 5-3 Power-Dependent MCPR Multipliers (Kr) for GNF2 and GNF3 Fuel, DLO only, BOC to EOC, Option A and Option B 12 5-4 Power-Dependent MCPR Multipliers (K) for GNF2, GNF3, ATRIUM-I 0, and ATRIUM-I OXM Fuel, DLO and SLO, BOC to EOC, Option A and Option B 12 5-5 DLO Flow-Dependent MCPR Limits (MCPRF) for GNF2, GNF3, ATRIUM-i 0, and ATRIUM-i OXM Fuel, BOC to EOC, All Application Groups, Option A and Option B 13 5-6 SLO Flow-Dependent MCPR Limits (MCPRF) for GNF2, GNF3, ATRIUM-i 0, and ATRIUM-i OXM Fuel, BOC to EOC, All Application Groups, Option A and Option B 13 6-i LHGR Limit for GNF2 and GNF3 Fuel 14 6-2 LHGR Limit for ATRIUM-iO and ATRIUM-1OXM Fuel 14 6-3 Power-Dependent LHGR Multipliers (LHGRFAC) for GNF2, GNF3, ATRIUM-i 0, and ATRIUM-i OXM Fuel, DLO and SLO, BOC to EOC 15 6-4 Flow-Dependent LHGR Multipliers (LHGRFACF) for GNF2, GNF3, ATRIUM-i 0, and ATRIUM-i OXM Fuel, BOC to EOC, Pressurization (1 TCV/TSV Closed or OOS), All Application Groups i6 6-5 Flow-Dependent LHGR Multipliers (LHGRFACF) for GNF2, GNF3, ATRIUM-i 0, and ATRIUM-i OXM Fuel, BOC to EOC, No Pressurization (All TCV/TSV In-Service), All Application Groups 16 7-i Rod Block Monitor Setpoints if 9-I OPRM PBDA Trip Setpoints 19 10-1 Allowed Modes of Operation and EQOS Combinations 20 LaSalle Unit 2 Cycle i6

COLR LaSalle 2 Revision 14 Page 5 of 21

1. References
1. Exelon Generation Company, LLC Docket No. 50-374 LaSalle County Station, Unit 2, Facility Operating License No. NPF-18.
2. Deleted.
3. Nuclear Fuels Letter NFM:MW:01-0106, from A. Giancatarino to J. Nugent, LaSalle Unit I 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-Al 300384-07-01, 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-Rl, Revision 1, Exelon Nuclear LaSalle Units I and 2 Thermal Power Optimization Task T0201: Operating Power/Flow Map, November 2009.
7. GNF Report GNF-000N9256-SRLR-R0, Revision 0, Supplemental Reload Licensing Report for LaSalle Unit 2 Reload 15 Cycle 16, January 2015.
8. GNF Letter 13-029 from B. R. Moore to Document Control Desk, GNF2 Advantage Generic Compliance with NEDE-24011-P-A(GESTAR II), NEDC-33270P, Revision 5, May2013, MFN 13-029, May24, 2013 (ADAMS Accession No. ML13148A318)
9. AREVA Report ANP-2914(P), Revision 1, Mechanical Design Report for LaSalle Units 1 and 2 MUR ATRIUM-lO Fuel Assemblies, AREVA NP Inc., June 2010.
10. Exelon Transmittal ES1400016, Revision 0, LaSalle 2 Cycle 16 Final Resolved OPL-3 Parameters, September11, 2014.
11. GNF DRF Al 2-00038-3, Vol. 4 from G.A. Watford to Distribution, Scram Times Verses Notch Position, May 22, 1992.
12. GEH Nuclear Energy DRF Section 0000-0151-0765 Rev. 0, Application of SLO MCPR, February 12, 2013.
13. GNF Report GNF-000N9257-FBIR-R0, Revision 0, Fuel Bundle Information Report for LaSalIe Unit 2 Reload 15 Cycle 16, January 2015.
14. Exelon Tech Eval EC 401294-002, Supplemental Evaluation to LaSalle 2 Cycle 16 Lost Parts Eval, March 2015.
15. NRC Letter from D. M. Skay to I. M. Johnson, Issuance of Amendments (TAC NOS. M95156 and M95l57), October 29, 1996.
16. GNF Report 003N400l-R0, LaSalIe County Generating Station Unit 2 Cycle 16 Mid-Cycle TRACG AOO and GS3 Implementation, May 2016.
17. Exelon transmittal ES1600002 Revision 0, Design Input Request for LaSalIe 2 Cycle 16 Mid-Cycle TRACGO4 AOO Implementation, February 8, 2016.
18. Exelon transmittal ES1600004 Revision 0 Design Input Request for LaSalle 2 Cycle 16 GS3 Implementation, February 26, 2016.

LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 6 of 21

2. Terms and Definitions ARTS Average Power Range Monitor, Rod Block Monitor and Technical Specification Improvement Program ATRM1O AREVA ATRIUM-b fuel type ATRM1OXM AREVAATRIUM-1OXM fuel type BOC Beginning of cycle BWR Boiling water reactor COLR Core operating limits report CRD Control rod drive mechanism DLO Dual ioop operation ELLLA Extended load line limit analysis EOC End of cycle EOOS Equipment out of service EOR16 End of rated operation for Cycle 16 FFWTR Final feedwater temperature reduction FWHOOS Feedwater heater out of service GNF Global Nuclear Fuels Americas ICE Increased core flow Power-dependent MCPR Multiplier L2C16 LaSalle Unit 2 Cycle 16 LHGR Linear heat generation rate LHGRFACF Flow-dependent LHGR multiplier LHGRFACP Power-dependent LHGR multiplier LPRM Local power range monitor MAPLHGR Maximum average planar linear heat generation rate MCPR Minimum critical power ratio MCPRF Flow-dependent MCPR MELLLA Maximum extended load line limit analysis MFLCPR Maximum faction of limiting critical power ratio MOC Middle of Cycle Point for Licensing Purposes MSIVOOS Main steam isolation valve out of service OLMCPR Operating limit minimum critical power ratio OOS Out of service OPRM Oscillation power range monitor PBDA Period based detection algorithm PLUOOS Power load unbalance out of service PRODS Pressure regulator out of service RCPR Relative Critical Power Ratio RPTOOS Recirculation pump trip out of service RWE Rod withdrawal error 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 TCVSC Turbine control valve slow closure TIP Traversing in-core probe TIPOOS Traversing in-core probe out of service TSV Turbine stop valve 3DM 3D-MONICORE LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 7 of 21

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/i 00% flow, and normal feedwater temperature.

The term (EOR 2288 MWd/ST) means the EOR exposure minus 2288 MWd/ST of exposure. The value of the EOR 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 2288 MWd/ST exposure will be reached. For cycle exposure dependent limits at the exact MOC exposure, the more limiting of the BOO to MOO and the MOO to EOO limits should be used. This can be achieved by applying the MOO to EOO limits to the MOO point as all cycle exposure dependent limits in the MOO to EQO limit sets are the same as, or more limiting than, those in the BOO to MOO limit sets.

A mid-cycle analysis was performed to support implementation of TRAOG AOO and GS3 methodologies (References 16, 17, and 18). The TRAOG AOO analysis provides updated OLMOPR values and K values for the Base Oase DLO application group for GNF2 and GNF3 fuel only. The OLMOPR values for ATRIUM-b and ATRIUM-i OXM fuel for all application conditions and the GNF2 and GNF3 fuel for all EOOS conditions are unchanged and are based on the original transient analysis. The GS3 methodology is applicable to all fuel types in the core and was used to confirm that both OPRM set-points given in Section 9 are applicable.

Table 3-i Cycle Exposure Range Definitions (Reference 7)

Nomenclature Cycle Exposure Range BOO to MOO B00i6 to (EORI6 2288 MWd/ST)

MOO to EOO (EOR16 2288 MWd/ST) to EOOi6 BOO to EOO BOO16 to EOCI6 LaSalle Unit 2 Oycle 16

COLR LaSalle 2 Revision 14 Page 8 of 21

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 are given 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-I MAPLHGR for GNF2 and GNF3 Fuel (Reference 7)

Avg. Planar MAPLHGR Exposure (kWIFT)

(GWdIST) 0.00 13.78 17.15 13.78 60.78 6.87 63.50 5.50 Table 4-2 MAPLHGR for ATRIUM-lO and ATRIUM-I OXM Fuel (Reference 7)

Avg. Planar MAPLHGR Exposure (kWIFT)

(GWdIST) 0 12.81 21.41 12.81 55.42 9.10 63.86 7.30 Table 4-3 MAPLHGR SLO Multiplier for GNF2, GNF3, ATRIUM-JO, and ATRIUM-I OXM Fuel, BOC to EOC (Reference 7)

SLO Fuel Type MAPLHGR Multiplier GNF2 0.78 GNF3 0.78 ATRIUM-iD 0.78 ATRIUM-1OXM 0.78 LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 9 of 21

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 and non-pressurization events, and they are determined based on the cycle-specific fuel reload analyses in References 7 and 16. Table 5-2 is used in conjunction with the ARTS-based power (Kp) and flow (MCPRF) dependencies presented in Tables 5-3, 5-4, 5-5, and 5-6 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, K, is determined from Table 5-3 or Table 5-4 and is dependent only on the power level and the Application Group (EOOS). The product of the steady state OLMCPR and the proper K provides the power-dependent OLMCPR.

5.1.2. Flow-Dependent MCPR Tables 5-5 and 5-6 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.

lithe 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).

LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 10 of 21 Table 5-1 Scram Times Required for Option A and Option B Application at Notch Position 39 (References 10 and 11)

Notch Scram Time Required for Option A Scram Time Required for Option B Position* Application 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.

5.4. OLMCPR Requirements with Lost Jet Pump Plug Seals To account for the lost jet pump plug seals, an RCPR value was determined to generically apply to the applicable OLMCPR limits discussed in Section 5.1. A maximum allowable MFLCPR value of 0.97 will ensure that the OLMCPR limits discussed in Section 5.1 are bounded with the lost jet pump plug seal RCPR value applied. (Reference 14)

LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 11 of 21 Table 5-2 Operating Limit Minimum Critical Power Ratio (OLMCPR) for GNF2, GNF3, ATRIUM-b, and ATRIUM-I OXM Fuel (References 7 and 16)

Option A Option B DLOI Exposure Application Group ATRMIOI ATRMIOI SLO Range GNF2 GNF3 GNF2 GNF3 ATRMIOXM ATRMJOXM BOC-MOC 1.44 1.46 1.51 1.40 1.42 1.51 Base Case DLO MOC-EOC 1.46 1.48 1.53 1.42 1.44 1.51 BOC-MOC 1.59 1.59 1.51 1.59 1.59 1.51 Base Case SLO MOC-EOC 1.66 1.67 1.56 1.61 1.62 1.53 BOC-MOC 1.61 1.62 1.59 1.51 1.52 1.51 Base Case + TCVSC DLO

+ RPTOOS + PRODS MOC-EOC 1.70 1.72 1.72 1.60 1.62 1.55 BOC-MOC 1.64 1.65 1.62 1.59 1.59 1.51 Base Case + TCVSC SLO

+ RPTOOS + PRODS MOC-EOC 1.73 1.75 1.75 1.63 1.65 1.58 BOC-MOC 1.57 1.58 1.51 1.52 1.53 1.51 Base Case ÷ TCVSC +

DLO TBVOOS (all 5 valves)

MOC-EOC 1.66 1.68 1.57 1.61 1.63 1.54 BOC-MOC 1.60 1.61 1.54 1.59 1.59 1.51 Base Case + TCVSC +

SLO TBVOOS (all 5 valves)

MOC-EOC 1.69 1.71 1.60 1.64 1.66 1.57 Base Case + TCVSC ÷ BOC-MOC 1.65 1.66 1.62 1.55 1.56 1.51 TBVOOS (all 5 valves) + DLO RPTOOS ÷ PRODS MDC-EOC 1.75 1.76 1.75 1.65 1.66 1.58 Base Case + TCVSC + BOC-MOC 1.68 1.69 1.65 1.59 1.59 1.54 TBVOOS (all 5 valves) + SLO RPTODS + PRODS MOC-EDC 1.78 1.79 1.78 1.68 1.69 1.61 LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 12 of 21 Table 5-3 Power-Dependent MCPR Multipliers (Ks) for GNF2 and GNF3 Fuel, DLO only, BOG to EOC, Option A and Option B (Reference 16)

K, MCPR Limit Multiplier (as a function of % rated power)

Application Group 0% P 25% P 45% P 60% P 85% P 85.O1%P 100% P Base Case 1156 1.156 1.156 1.156 1.045 1.045 1.000 Table 54 Power-Dependent MCPR Multipliers (Ks) for GNF2, GNF3, ATRIUM-JO, and ATRIUM-I OXM Fuel, DLO and SLO, BOC to EOC, Option A and Option B (For GNF2 and GNF3 fuel, Base Case K values apply for SLO only)

(References 7 and 16)

K, MCPR Limit Multiplier (as a function of % rated power)

Application Group 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 1207 1.097 1097 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 LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 13 of 21 Table 5-5 DLO Flow-Dependent MCPR Limits (MCPRF) for GNF2, GNF3, ATRIUM-f 0, and ATRIUM-f OXM I Fuel, BOC to EOC, All Application Groups, Option A and Option B (References 7 and 16) I Flow MCPRF

(% Rated) 0.0 1.91 30.0 1.72 105.0 1.25 Table 5-6 SLO Flow-Dependent MCPR Limits (MCPRF) for GNF2, GNF3, ATRIUM-f 0, and ATRIUM-f OXM Fuel, BOC to EOC, All Application Groups, Option A and Option B (References 7, 12 and 16)

Flow MCPRF

(% Rated) 0.0 1.94 30.0 1.75 105.0 1.28 LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 14 of 21

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 LHGRFAC 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, GNF3, ATRIUM-i 0, and ATRIUM-i OXM fuel.

Table 6-I LHGR Limit for GNF2 and GNF3 Fuel (References 8 and 13)

Peak Pellet Exposure U02 LHGR Limit See Table B-i of Reference 8 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit See Table B-2 of Reference 8 Table 6-2 LHGR Limit for ATRIUM-JO and ATRIUM-I OXM Fuel (Reference 9)

Peak Pellet Exposure LHGR Limit (GWd/ST) (kWlft) 0.0 13.4 16.06 13.4 55.43 9.1 63.87 7.3 LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 15 of 21 Table 6-3 Power-Dependent LHGR Multipliers (LHGRFAC) for GNF2, GNF3, ATRIUM-JO, and ATRIUM-I OXM Fuel, OLO and SLO, BOC to EOC (References 7 and 16) I LHGRFACP (as a function of % rated power)

Application Group 0% P 25% P 45% P 60% P 85% P 100% P Base Case 0.608 0.608 0.713 0.791 0.922 1.000 Base Case + TCVSC

+ RPTOOS + 0.608 0.608 0.713 0.761 0.831 1.000 PROOS Base Case ÷ TCVSC

+ TBVOOS (all 5 0.608 0.608 0.713 0.791 0.922 1.000 valves)

Base Case ÷ TCVSC

+TBVQQS(all5 0.608 0.608 0.713 0.761 0.822 1.000 valves) +

RPTOOS + PROOS LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 16 of 21 Table 6-4 Flow-Dependent LHGR Multipliers (LHGRFACF) for GNF2, GNF3, ATRIUM-I 0, and ATRIUM-I OXM Fuel, BOG to EOC, Pressurization (I TCVITSV Closed or 005), All Application Groups (References 7 and 16) I Flow DLO LHGRFACF SLO LHGRFACF

(% Rated) 0.0 0.110 0.110 30.0 0.410 0.410 67.0 0.780 0.780 89.0 1.000 0.780 105.0 1.000 0.780 Table 6-5 Flow-Dependent LHGR Multipliers (LHGRFACF) for GNF2, GNF3, ATRIUM-JO, and ATRIUM-IOXM Fuel, BOC to EOC, No Pressurization (All TCVITSV In-Service), All Application Groups (References 7 and 16)

Flow DLO LHGRFACF SLO LHGRFACF

(% Rated) 0.0 0.250 0.250 30.0 0.550 0.550 53.0 0.780 0.780 75.0 1.000 0.780 105.0 1.000 0.780 LaSalle Unit 2 Cycle 16

COLR LaSalle2 Revision 14 Page 17of21

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-f Rod Block Monitor Setpoints Rod Block Monitor Upscale Trip Function Allowable Value Two Recirculation Loop 0.66 Wa ÷ 54.0%

Operation Single Recirculation Loop 0.66 Wa ÷ 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 (We) of 100%.

W percent of recirculation loop drive flow required to produce a rated core flow of 108.5 Mlbm/hr.

LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 18 of 21

8. Traversing In-Core Probe System (Reference 15) 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.

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.

LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 19of21

9. Stability Protection Setpoints Technical Specification Section 3.3.1.3 Table 9-1 OPRM PBDA Trip Setpoints (Reference 16)

Corresponding Maximum PBDA Trip Amplitude Setpoint (Sp)

Confirmation Count Setpoint (Np) 1.11 14 1.15 16 Both OPRM PBDA trip settings provided in Table 9-1 were confirmed.

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 and flow dependent MCPR limits. Any change to the OLMCPR values and/or the power and flow dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA trip settings.

The OPRM PBDA trip settings are applicable when the OPRM system is declared operable, and the associated Technical Specifications are implemented.

LaSalle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 20 of 21 JO. 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 (References 4, 7 and 16)

(1) (2) (4) (5)

. Equipment Out of Service Options Short Name (3) Base Base Case (Option A or B)

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 I 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 Combined EOOS 3 (Option A or B)

Base Case ÷ TCVSC + TBVOOS (all 5 valves) + RPTOOS + PROOS + SLO Combined EOOS 3 SLO (Option A or B)

(1) Base case includes 1 SRVOOS + 1 TCV/TSV OOS + FWHOOS/FFWTR + 1 MSIVOOS +2 TBVOOS + PLUOOS (References 7 and 16). All Modes of Operation and EOOS Combinations allow 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 (Reference 4). The FWHOOS/FFWTR analyses cover a maximum reduction of 100°F for the feedwater temperature. A nominal LPRM calibration interval of 2000 EFPH (2500 EFPH maximum) is supported for L2C16.

(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 TBV5 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) (Reference 10). The MCFL is currently set at 126.6 and will only allow opening of TBVs #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 TCV/TSV In-Service, the Base Case should be used with the LHGRFACF values from Table 6-5 (References 7 and 16). 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 level 85% of rated. The one MSIVOOS condition is also supported as long as thermal power is maintained 75% of the rated (Reference 7 Appendix D).

(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, ICE 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).

LaSaIle Unit 2 Cycle 16

COLR LaSalle 2 Revision 14 Page 21 of 21

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 I and 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. NEDE-24011-P-A-20 (Revision 20), General Electric Standard Application for Reactor Fuel, December2013 and the U.S. Supplement NEDE-2401 1-P-A-20-US, December 2013.
6. NEDC-33106P-A Revision 2, GEXL9Z Correlation for ATRIUM-b Fuel, June 2004.
7. Deleted.
8. NEDE-24011-P-A-22 (Revision 22), General Electric Standard Application for Reactor Fuel, November2015 and the U.S. Supplement NEDE-2401 1-P-A-22-US, November 2015.

LaSalle Unit 2 Cycle 16

bcc: Joshua Shea (wlo attachment)

Eric Stein (wlo attachment)

P. Weggeman (NFM) (w/o attachment)

NRC Project Manager NRR (Bhalchandra Vaidya)

DOD Licensing (hard copy and electronic)

LS-AA-i 17-7002 Exeton Ger ration Revision 4 Page 1 of 1 TYPICAL LICENSING AND REGULATORY AFFAiRS CORRESPONDENCE CONCURRENCE FORM Station(s): LaSalle Correspondence No.: RAY6-039 Subject/Document:. Submittal of Unit 2 Cycle 16 COLR (Rev. 4) to NRC Document Prepared by: D. Murray Location: LaSalle Extension: 2814 Required Review and Disciplines Assigned by: Guy Ford / RAM Title Type of Review Required: LI Technical Verification Team Review (Reference LS-AA-1 17) X Individual or Series Review LI No Technical Review Note: lithe subject document falls within the scope of AD-AA-1 02, Station Qualified Review, one of the reviewers must be a Station Qualified Reviewer.

Disciplines Required:

LI Maintenance LI Radiation Protection LI Chemistry LI Training X Operations LI Engineering I&C LI Radwaste X Rx Engineering LI Reg Assurance / Licensing LI Design Engineering LI Engr Mech Systems LI Programs Engineering LI Nuclear Fuels LI Work Management LI Engr Elect Systems LI Other:

Review Concurrence: Signature indicates that the individual has reviewed the subject document and concurs that the content is factual and accurate. Concurrence via e-mail shall be provided using the declaration provided in LS-AA-117.

Print Jjame I Signature Discipline Dpte E. Stein/ Rx Engineering J. Shea! Z4& Rx Engineering J. Operations J2i4i ti, Does this letter contain commitments? LI Yes X No If yes, corporate or site commitment coordinator has been notified: Date:

Required Reviews and Signatures (check as appropriate):

X Station Qualified Review Required: (RA16-038, TRM App J ChanQe) Date:

LI PORC Approval Required: PORC Meeting No. iL&

X Corporate Licensing Concurrence Required: SeE t Date: z/ctj(,

X Site Regulatory Assurance Concurrence Requ

/t huYk i Ir ...( Date: ()-O I(-

X Station Manager Approval Required:

4 VV V

I/ ( ] Date:

X Site Vice President Approval Required: See Letter Date:

SRRS Record ID: 5A.113 (Destroy at Option (DAO))

IRM TRM Control Program Appendix K ATTACHMENT A TECHNICAL REQUIREMENTS MANUAL CHANGE REQUEST FORM

1. Change Request#: RA16-038
2. Affected TRM Section(s): Appendix J
3. Description of changes: Revised U2 COLR to update thermal limits and References to incorporate the mid-cycle TRACG AOO and GS3 analysis.
4. Reason for changes (attach all supporting documentation): Thermal limit improvements through the use of TRACG AOO and GS3 analysis.
5. Schedule Requirements: Outage Related (check one) (x) No Yes, Outage #

( )

Other (explain)

6. Implementation Requirements (attach additional pages, as necessary):

Identify the impact of the changes on the following:

Affected N/A (x) ( ) UFSAR LUCR-374

( ) (x) TS/TS Bases________________________________________________________

(x)

NRC Safety Evaluation (x) Fire Protection Report (x) NRC Commitments fx) Vendor Documentation

) (x) Special Permits/Licenses

( ) (x) Procedures (x) Environmental Qualification (x) Design Basis Documentation (x) Engineering Calculations (x) Drawings/Prints

( ) (X) PRA Information (x) Programs (x) Reportability Manual (x) QA Topical Report (x) Passport______________________________________________________________

(x) Pre-Implementation Training Required Maintenance Rule (x)

(x) Offsite Dose Calculation Manual (x) Other

7. Check one:

(X) 10 CFR 50.59 REVIEW Attached, 10 CFR 50.59 REVIEW#: L16-108 NRC SE Attached, Changes consistent with and entirely bounded by NRC SE EDITORIAl..CHAI9,_No 10 CFR 50.59 REVIEW required

8. Requestor: E / 6/17/16 / Ops Rx Eng (Signature) .n ate) (Department)
9. Regulatory Assurance Approval: / // 7//a iire) (Date)
10. PORC Approval Required: ( ) Yes
11. Licensing Engineer Review: 7iuf.U1,L.d /  ;/1? /t(o (1gnature) (Date)

LaSalle County Units 1 & 2 10 of 14 Revision 3 Technical Requirements Manual

REGULATORY ASSURANCE STATION QUALITY REVIEW FORM Date Assignment Made: 6/17/2016 SQR Review Number: RA16-038 Document(s) Reviewed:Revision to TRM Appendix J (include document number and revision, if applicable)

Subject of Review:

Unit 2 Core Operating Limits Report (COLR) is being revised to update thermal limits and references to incorporate the midcycle TRACG AOO and G$3 analysis.

PORC Approval Required? LI Yes No NRSB Required? Yes No If yes, reviewed by PORC number/date if yes, reviewed by NSRB (location /date)

Disciplines/Participants Designated:

LI Maintenance LI Radiation Protection LI Chemistry LI Training Operations LI Engr I&C Systems LI Radwaste LI Reg Assurance I Licensing Rx Engineering LI Design Engineering LI Engr Mech Systems

- LI Programs Engineering LI Nuclear Fuels LI Work Management LI Engr Elect Systems LI Other:

%7f Date: 4i//7Jflo egula y Assurance Manager Reviewers:

Print Name / Signature Discipline Date Josh Sheaf 2A-_- i__ Rx Engineering (Sizfi (.c John Operations tn ilk, Document any applicable Action Tracking Number(s) (e.g., implementation activities): None Approval: Date:

/ Station Quality Review Authorization: 1 Date:

cMw. l-- 761 4 Regulatory Assurance Manager!

Station Manager (if PORC required)

Kusumawatimurray, Putri:(GenCo-Nuc)

From: Simpson, Lisa A.:(GenCo-Nuc)

Sent: Tuesday, July 05, 2016 12:19 PM To: Kusumawatimurray, Putri:(GenCo-Nuc)

Subject:

RE: Concurrence for Unit 2 COLR Revision 4 for Cycle 16.

Attachments: Important message from Exelon.pdl; EW: Revised Writers Guide Attached are my comments on the transmittal letter for the COLR. I limited my review to the letter since the COLR revision has already been issued. Also attached is the revised Exelon Nuclear Licensing Writers Guide.

In accordance with LS-AA-1 17, I have reviewed and concur with the subject regulatory correspondence (with the attached comments).

Lisa A. Simpson Exelon Corporate Licensing 630-657-2815 lisa.simpson @ exeloncorp.com From: Kusumawatimurray, Putri :(GenCo-Nuc)

Sent: Wednesday, June 29, 2016 4:08 PM To: Simpson, Lisa A. :(GenCo-Nuc)

Subject:

Concurrence for Unit 2 COLR Revision 4 for Cycle 16.

Lisa, Please see the attached RA16-039 for your review and concurrence regarding NRC submittal of Unit 2 COLR Revision 4 for Cycle 16. We have updated TRM Appendix J to implement Revision 4 of the COLR for Cycle 16 on 6/20/16. The submittal has gone through Rx Engineering and Ops concurrence review. Do you think youll be able to provide your concurrence by COB Friday, 7/1/16? Please let me know of any questions or concerns.

Thank you for your support as always, Dwi Murray Principal Regulatory Engineer Regulatory Assurance LaSalle County Station 815-415-2814 Putri. Kusu mawatim urray@exeloncorp.com 1

C NUCLEAR FUELS TRANSMITTAL OF DESIGN INFORMATION SAFETY RELATED Originating Organization NF ID# NF150845 E NON-SAFETY RELATED Nuclear Fuels Revision# 5 D REGULATORY RELATED U Other (specify) SRRS # 3A.130 Page 1 of 2 (Coversheet)

Station: LaSalle Unit: 2 Cycle: 16 Generic: N/A

Subject:

COLR LaSalle 2 Revision 14 To: Joshua Shea (LaSafle, Reactor Engineering Manager) ECIECR#: 401347

,/,> ,/

-i,,

7 Digitally signed by Thomas, Michael D.

Date: 2016-06-16 13:53-05:00 Michael D. Thomas Prepared by Signature Date Digitally signed by Peter A Peter A. VVeggeman Za 4i, /

Weggeman -

Date. 2016.06.t6 14.15.56 0500 Verified by Signature Date fl - Digitally signed by Douglas Wise Doug J. Wise Date: 2016.06.16 77:01:27 -0500 Approved by Signature Date Status of Information: Verified LI Unverified LI Engineering Judgment Action Tracking # for Method and Schedule of Verification for Unverified DESIGN INFORMATION: N/A Description of Information: Rev. 5: Reissued COLR incorporating administrative comments from Reg Assurance. The 21 page COLR (Revision 14) is attached to this transmittal.

Rev. 4: Revise COLR to Revision 14 to update thermal limits and References to incorporate the mid-cycle TRACG AOO and GS3 analysis, delete Reference 2 because it is not needed, and add Reference 15.

Rev. 3: Remove Appendix A as it no longer applies and add revision history information. The 21 page L2C16 COLR (Revision 13) is attached to this one page transmittal coversheet.

Rev. 2: Revise COLR to add FWHOOS as exempt from all equipment in service requirement in Appendix A. The 21 page L2C16 COLR (Revision 12) is attached to this one page transmittal coversheet.

Rev. 1: Revised COLR to incorporate limits for lost jet pump plug seals mitigation plan and subsequent operation. The 21 page L2C16 COLR (Revision 11) is attached to this one page transmittal covetsheet.

Rev. 0: Original issue of the LaSalle Unit 2 Cycle 16 (L2C16) COLR with all thermal/operating limits as identified and required by Technical Specifications.

The 20 page L2C16 COLR (Revision 10) is attached to this one page transmittal cover sheet.

Purpose of Information: Provide L2C16 COLR for Station Qualified Review (SQR) and Station PORC review (as necessary) and implementation.

0 0 TODI NF15O$45 Rev. 5 Page 2 of 2 Source of Information: See COLR References and Methodology Sections.

Supplemental Distribution: E Mail:

Hard Copy:

Eric Stein (LS) LaSalle Records Management

a Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annua] Radiological Environmental Operating Report (continued)

(ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

5.6.3 Radioactive Effluent Release Report NOTE A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the stati on.

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effl uents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CER 50, Appendix I,Section IV.B.1.

5.6.4 (Deleted) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the fol lowing:
1. The APLHGR for Specification 3.2.1.
2. The NICPR for Specification 3.2.2.
3. The LHGR for Specification 3.2.3.

(continued)

LaSalle 1 and 2 5.6-2 Amendment No. 173/159

C a Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

4. The Rod Block Monitor Upscale Instrumentation Setpoint for the Rod Block MonitorUpscale Function Allowable Value for Specification 3.3.2.1.
5. The OPRM setpoints for the trip function for SR 3.3.1.3.3.
b. 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. ANF-524(P)(A), ANF Critical Power Methodology for Boiling Water Reactors.
2. ANF-913(P)(A), COTRANSA 2: A Computer Program for Boiling Water Reactor Transient Analysis.
3. ANF-CC-33(P)(A), HUXY: A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option.
4. XN-NF-8O-19(P)(A), Advanced Nuclear Fuel Methodology for Boiling Water Reactors.
5. XN-NF-85-67(P)(A), Generic Mechanical Design for Exxon Nucl ear Jet Pump BWR Reload Fuel .
6. EMFCC-O74(P)(A), Volume 4 - BWR Stability Analysis:

Assessment of STAIF with input from MICROBURN-B2.

7. XN-NF-81-58(P)(A), RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model.
8. XN-NF-84-105(P)(A), XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis.

(continued)

LaSalle 1 and 2 5.6-3 Amendment No. 194/181

0 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

9. EMF-22O9(P)(A), SPCB Critical Power Correlation. I
10. ANF-89-98(P)(A), Genetic Mechanical Design Criteria I for BWR Fuel Designs.
11. NEDE-24O11-P-A, General Electric Standard Application I for Reactor Fuel
12. NFSR-O091, Benchmark of CASMO/MICROBURN BWR Nuclear I Design Methods.
13. EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal Mechani cal Eval uati on Model .
14. EMF-2158(P)(A), Siemens Power Corporation Methodology I for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2.
15. NEDC-33106P, GEXL97 Correlation for Atrium-lO Fuel.
16. EMF-2245(P)(A), Application of Siemens Power I Corporations Critical Power Correlations to Co Resident Fuel
17. EMF-2361(P)(A), EXEM BWR-2000 ECCS Evaluation Model I
18. NEDO-32465-A, BWR Owners Group Reactor Stability I Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications, August 1996.
19. ANF-1358(P)(A), The Loss of Feedwater Heating Transient in Boiling Water Reactors.

(continued)

LaSalle 1 and 2 5.6-4 Amendment No. 181/168

0 o Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by Condition B or F of LCO 3.3.3.1, Post Accident Monitoring (PAM) Instrumentation, a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

LaSalle 1 and 2 5.6-5 Amendment No. 177/163

Sorn, Denise M:(GenCo-Nuc)

From: mshd.resource@nrc.gov Sent: Friday, July 08, 2016 12:28 PM To: Sorn, Denise M:(GenCo-Nuc)

Subject:

[EXTERNAL] General Form Submission Received The NRC received your General Form submission on: 07/08/2016 at 01:27 PM. It is being tracked as submission ID#

10688.

If it is a Publicly Available submission after 6 work days from today the submissions attached document(s) will be available for viewing and download from the Agencys Public Web Based ADAMS website (http://adams.nrc.gov/wba) by searching for the following document accession number(s): [ML16190A257J. If this is a Non-Public submission the submissions attachment(s) will be retained in NRCs document management system (ADAMS) and will not be published to the public website.

Should you have questions about this submission please contact our Help Desk by phone at 866-672-7640 or by e-mail at mshd.resource@nrc.gov. When doing so, please refer to the Submission lD# shown above.

Note: The Help Desk is staffed daily from 9:00AM to 7:00PM Eastern Time Monday through Friday (except for Federal holidays) 1

Sorn, Denise M:(GenCo-Nuc)

From: Sorn, Denise M:(GenCo-Nuc)

Sent: Friday, July 08, 2016 12:38 PM To: Shea, Joshua M.:(GenCo-Nuc); Stein, Eric Jordan:(GenCo-Nuc); Weggeman, Peter A:(GenCo-Nuc)

Cc: Kusumawatimurray, Putri:(GenCo-Nuc); Lanc, Terry L:(GenCo-Nuc)

Subject:

LaSalle NRC Correspondence RA16-039 Unit 2 Cycle 16 Core Operating Limits Report (COLR)

Attachments: NRC RA16-039.pdf See Attached Electronically submitted to the NRC on 7/11/16

))-:::-. .. ))

f(,. Denise Sorn::--::

-:  :- ((.. LaSalle Station, Reg Assurance 815-415-2801 1

Sorn, Denise M:(GenCo-Nuc)

To: DCD-Licensing

Subject:

LaSalle NRC Correspondence RA16-039 Unit 2 Cycle 16 Core Operating Limits Report (COLR)

Attachments: NRC RA16-039 Unit 2 Cycle 16 Revision 4 of COLR.pdf See Attached Electronically submitted to the NRC on 7/11/16

))::.. ..))

((.* Denise Sorn -:

-: :- (( LaSalle Station, Reg Assurance 815-415-2801

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