ML021920402
| ML021920402 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/03/2002 |
| From: | Barnes G Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EMF-2689, Rev 0 | |
| Download: ML021920402 (138) | |
Text
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Pevis iv Figures 1.1 LaSalle County Nuclear Station Power/ Flow Map.......................................................
1-4 2.1 Flow-Dependent MCPR Limits for Manual Flow Control Mode...................................
2-11 2.2 Flow-Dependent LHGRFAC Multipliers for ATRIUM-10 and ATRIUM-9B F u e l............................................................................................................................
2 -12 3.1 EOC Load Rejection No Bypass at 100/105 -TSSS Key Parameters........................ 3-18 3.2 EOC Load Rejection No Bypass at 100/105 - TSSS Vessel Water Level................... 3-19 3.3 EOC Load Rejection No Bypass at 100/105 - TSSS Dome Pressure........................ 3-20 3.4 EOC Feedwater Controller Failure at 100/105 - TSSS Key Parameters..................... 3-21 3.5 EOC Feedwater Controller Failure at 100/105 - TSSS Vessel Water L e ve l...........................................................................................................................
3 -2 2 3.6 EOC Feedwater Controller Failure at 100/105 - TSSS Dome Pressure..................... 3-23 3.7 Radial Power Distribution for SLMCPR Determination................................................
3-24 3.8 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors A10-4039B 15GV75 With Channel Bow (Assembly Exposure of 1000 MWd/MTU)....................... 3-25 3.9 LaSalle Unit 1 Cycle 10 Safety Limit Local Peaking Factors A10-4037B 16GV75 With Channel Bow (Assembly Exposure of 500 MWd/MTU)......................... 3-26 3.10 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times...............................................................
3-27 3.11 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times...............................................................
3-28 3.12 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times............................
3-29 3.13 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times.............................................................
3-30 3.14 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times...............................................................
3-31 3.15 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times...............................................................
3-32 3.16 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times.............................................................
3-33 3.17 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times.............................................................
3-34 3.18 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times..............................................
3-35 Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page v 3.19 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times..............................................
3-36 3.20 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times............................................
3-37 3.21 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times............................................
3-38 3.22 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times..............................................
3-39 3.23 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times..............................................
3-40 3.24 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times............................................
3-41 3.25 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times............................................
3-42 5.1 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times.....................................................
5-21 5.2 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times..............................................
5-22 5.3 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times....................................................
5-23 5.4 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times..............................................
5-24 5.5 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times...................................................
5-25 5.6 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRI UM-10 Fuel - TSSS Insertion Times............................................
5-26 5.7 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times...................................................
5-27 5.8 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times............................................
5-28 5.9 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times.....................................................
5-29 5.10 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times..............................................
5-30 5.11 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times....................................................
5-31 5.12 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times..............................................
5-32 Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page vi 5.13 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times...................................................
5-33 5.14 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-1 0 Fuel - TSSS Insertion Times............................................
5-34 5.15 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times...................................................
5-35 5.16 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times............................................
5-36 5.17 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times.....................................................
5-37 5.18 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times..............................................
5-38 5.19 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times....................................................
5-39 5.20 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times..............................................
5-40 5.21 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel-TSSS Insertion Times...................................................
5-41 5.22 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-1 0 Fuel - TSSS Insertion Times............................................
5-42 5.23 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times...................................................
5-43 5.24 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times............................................
5-44 5.25 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times.....................................................
5-45 5.26 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times..............................................
5-46 5.27 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times..............................................
5-47 5.28 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times..............................................
5-48 5.29 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times...................................................
5-49 5.30 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times............................................
5-50 5.31 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times...................................................
5-51 5.32 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times............................................
5-52 Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page vii 5.33 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRI UM-10 Fuel - NSS Insertion Times................. 5-53 5.34 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times................. 5-54 5.35 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion T im e s.........................................................................................................................
5 -5 5 5.36 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion T im e s..........................................................................................
5-5 6 5.37 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times................. 5-57 5.38 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times................. 5-58 5.39 15,000 MWd/MTU to EOC 1 TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion T im e s.........................................................................................................................
5-5 9 5.40 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion T im e s.........................................................................................................................
5 -6 0 7.1 Overpressurization Event at 102/105 - MSIV Closure Key Parameters..........................
7-3 7.2 Overpressurization Event at 102/105 - MSIV Closure Vessel Water Level.....................
7-4 7.3 Overpressurization Event at 102/105 - MSIV Closure Lower-Plenum P re ssure......................................................................................................................
7 -5 7.4 Overpressurization Event at 102/105 - MSIV Closure Dome Pressure..........................
7-6 7.5 Overpressurization Event at 102/105 - MSIV Closure Safety/Relief Valve F lo w R ate s..................................................................................................................
7 -7 Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Page viii Nomenclature AOO anticipated operational occurrence CPR critical power ratio EFPH effective full power hours EOC end of cycle EOD extended operating domain EOFP end of full power EOOS equipment out-of-service FFTR final feedwater temperature reduction FHOOS feedwater heater out-of-service FRA-ANP Framatome ANP, Inc.
FWCF feedwater controller failure HFR heat flux ratio ICF increased core flow L1C1O LHGR LHGRFACf LHGRFACp LHGROL LOFH LPRM LRNB MAPFACt MAPFACp MCPR MCPRt MCPRp MELLLA MFC MSIV NSS NRC PAPT RPT LaSalle Unit 1 Cycle 10 linear heat generation rate flow-dependent linear heat generation rate factors power-dependent linear heat generation rate factors linear heat generation rate operating limit loss of feedwater heating local power range monitor generator load rejection with no bypass flow-dependent maximum average planar linear heat generation rate multiplier power-dependent maximum average planar linear heat generation rate multiplier minimum critical power ratio flow-dependent minimum critical power ratio power-dependent minimum critical power ratio maximum extended load line limit analysis manual flow control main steam isolation valve nominal scram speed Nuclear Regulatory Commission, U.S.
protection against power transient recirculation pump trip Frarnatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page ix Nomenclature (Continued)
SLMCPR safety limit MCPR SLO single-loop operation SRV safety/relief valve SRVOOS safety/relief valve out-of-service SSLHGR steady-state LHGR TBVOOS turbine bypass valve out-of-service TCV turbine control valve TIP traversing incore probe TIPOOS tip machine(s) out-of-service TSSS technical specification scram speed TSV turbine stop valve TTNB turbine trip with no bypass ACPR change in critical power ratio Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EvMF-2689 Plant Transient Analysis Page 1-v 1.0 Introduction This report presents results of the plant transient analyses performed by Framatome ANP, Inc.
(FRA-ANP) as part of the reload safety analyses to support LaSalle Unit 1 Cycle 10 (L1 C10) operation. The Cycle 10 core contains 346 fresh ATRIUM TM-10* assemblies, 372 previously loaded ATRIUM-9B assemblies, and 46 previously loaded GE9 assemblies (all in peripheral locations). Those portions of the reload safety analysis for which Exelon has responsibility are presented elsewhere. The scope of the transient analyses performed by FRA-ANP is presented in Reference 1.
The analyses reported in this document were performed using the plant transient analysis methodology approved by the Nuclear Regulatory Commission (NRC) for generic application to boiling-water reactors (Reference 2). The transient analyses were performed in accordance with the NRC technical limitations as stated in the methodology (References 3-7, 12).
Parameters for the transient analyses are documented in Reference 8.
The Cycle 10 transient analysis consists of the calculation of the limiting transients identified in Reference 9 to support base case operationt for the power/flow map presented in Figure 1.1.
Results are also presented to support operation in the extended operating domain (EOD) and equipment out-of-service (EOOS) scenarios identified in Table 1.1. The analysis results are used to establish operating limits to protect against fuel failures. Minimum critical power ratio (MCPR) limits are established to protect the fuel from overheating during normal operation and anticipated operational occurrences (AOOs). Power-dependent MCPR (MCPRp) limits are required in order to provide the necessary protection during operation at reduced power. Flow dependent MCPR (MCPRf) limits provide protection against fuel failures during flow excursions initiated at reduced flow. Cycle 10 power-and flow-dependent MCPR limits are presented to protect both ATRIUM-10 and ATRIUM-9B fuel. Since the GE9 fuel is in low power peripheral locations for LiClO, the ATRIUM-9B MCPR limits can be used for the GE9 fuel. This conclusion is based on a MCPR evaluation of these assemblies in the design-basis step through.
ATRIUM is a trademark of Framatome ANP.
t Base case operation is defined as two-loop operation within the standard operating domain, including the ICF and MELLLA regions, with all equipment in-service.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 1-2 Protection against violating the linear heat generation rate (LHGR) limits at rated and off-rated conditions is provided through the application of power-and flow-dependent LHGR factors (LHGRFACp and LHGRFACf, respectively). These factors or multipliers are applied directly to the steady-state LHGR limit to ensure that the LHGR does not exceed the protection against power transient (PAPT) limit during postulated AQOs. Cycle 10 power-and flow-dependent LHGR multipliers are presented for ATRIUM-10 and ATRIUM-9B fuel. In addition, the GE9 MAPFACf and MAPFACn multipliers used in Cycle 9 remain applicable.
Results of analyses that demonstrate compliance with the ASME Boiler and Pressure Vessel Code overpressurization limit are presented.
The results of the plant transient analyses are used in a subsequent reload analysis report (Reference 15) along with core and accident analysis results to justify plant operating limits and set points.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 1-3 Table 1.1 EOD and EOOS Operating Conditions Extended Operating Domain (EOD) Conditions Increased core flow (ICF)
Maximum extended load line limit analysis (MELLLA)
Coastdown - Currently not supported for Li C1 0 Final feedwater temperature reduction (FFTR) - Currently not supported for L1C10 Combined FFTR/coastdown - Currently not supported for L1C10 Equipment Out-of-Service (EOOS) Conditions*
Feedwater heaters out-of-service (FHOOS)
Single-loop operation (SLO) - recirculation loop out-of-service Turbine bypass valves out-of-service (TBVOOS)
EOC recirculation pump trip out-of-service (no RPT)
Turbine control valve (TCV) slow closure and/or no RPT Safety relief valve out-of-service (SRVOOS)
Up to 2 TIP machines out-of-service or the equivalent number of TIP channels (100% available at startup)
Up to 50% of the LPRMs out-of-service TCV slow closure, FHOOS, and/or no RPT 1 stuck closed turbine control valve EOOS conditions are supported for EOD conditions as well as the standard operating domain. Each EOOS condition combined with 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of channels),
1 stuck closed turbine control valve and/or up to 50% of the LPRMs out-of-service is supported.
Framatome ANP, Inc.
EMF-2689 Revision 0 Paqe 1-4 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 110 100 90 80 a,
0 C
~0 d-70 60 50 40 30 20 10 0
0 10 20 30 40 50 60 70 Percent of Rated Flow Figure 1.1 Framatome ANP, Inc.
80 90 100 110 120 LaSalle County Nuclear Station Power / Flow Map
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 2-1 2.0 Summary The determination of the thermal limits (MCPR limits and LHGRFAC multipliers) for LaSalle Unit 1 Cycle 10 is based on analyses of the limiting operational transients identified in Reference 9. The transients evaluated are the generator load rejection with no bypass (LRNB),
feedwater controller failure to maximum demand (FWCF), control rod withdrawal error (CRWE) and loss of feedwater heating (LOFH). Thermal limits identified for Cycle 10 operation include both MCPR limits and LHGRFAC multipliers. The MCPR operating limits are established so that less than 0.1% of the fuel rods in the core are expected to experience boiling transition during an AOO initiated from rated or off-rated conditions and are based on a two-loop operation MCPR safety limit of 1.11. Even so, the results of the analysis support a two-loop operation MCPR safety limit of 1.09 and a single-loop operation MCPR safety limit of 1.10 for all fuel types in the Cycle 10 core. LHGRFAC multipliers are applied directly to the LHGR limits at reduced power and/or flow conditions to protect against fuel melting and overstraining of the cladding during an AOO. Exposure dependent operating limits are established to support operation from beginning of cycle (BOC) to 15,000 MWd/MTU and from 15,000 MWd/MTU to EOC. EOC for LaSalle Unit 1 Cycle 10 is defined as a core exposure of 31,495.1 MWd/MTU.
Operating limits are established to support both base case operation and the EOOS scenarios presented in Table 1.1. Operating limits are also established for the EOD and combined EOD/EOOS conditions presented in Table 1.1.
Base case MCPRP limits and LHGRFACp multipliers are based on results presented in Section 3.0. Results presented in Sections 4.0-6.0 are used to establish the operating limits for operation in the EOD, EOOS, and combined EOD/EOOS scenarios.
Cycle 10 MCPRP limits and LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel that support base case operation and operation in the EOD, EOOS and combined EOD/EOOS scenarios are presented in Tables 2.1-2.4. Tables 2.1 and 2.2 present the limits and multipliers for nominal scram speed (NSS) insertion times and Technical Specifications scram speed (TSSS) insertion times for the Cycle 10 BOC-1 5,000 MWd/MTU exposure range. Tables 2.3 and 2.4 present the NSS and TSSS limits and multipliers for the Cycle 10 15,000 MWd/MTU EOC exposure range. Operating limits for the EOOS conditions are divided into three different scenarios. EOOS Case 1 limits support operation with FHOOS or with the turbine bypass valves inoperable. Case 1 limits also support operation with FHOOS and 1 stuck closed TCV.
EOOS Case 2 limits support operation with any combination of TCV slow closure, no RPT or Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 2-2 FHOOS. The Case 2 limits also support the same EOOS scenarios in combination with 1 stuck closed TCV. A third set of EOOS limits are provided to support operation with the turbine bypass valves inoperable in conjunction with 1 stuck closed TCV. Limits for single-loop operation with the same EOOS conditions are also provided.
MCPRf limits for both ATRIUM-10 and ATRIUM-9B that protect against fuel failures during a slow flow excursion event in manual flow control are presented in Figure 2.1. Automatic flow control is not supported for L1C10. The MCPRf limits presented are applicable for all EOD and EOOS conditions presented in Table 1.1.
The Cycle 10 LHGRFACf multipliers for ATRIUM-10 and ATRIUM-9B fuel are presented in Figure 2.2 and are applicable in all the EOD and EOOS scenarios presented in Table 1.1.
The power excursion experienced by low-power peripheral fuel assemblies during an anticipated operational occurrence is very mild compared to centrally orificed fuel assemblies.
Since GE9 fuel will only be in peripheral locations, the MCPR safety limit will not be challenged by the GE9 fuel assemblies and using the ATRIUM-9B MCPR limits for the GE9 fuel provides the necessary protection. In addition, the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable. This conclusion is based on an evaluation of these assemblies in the design-basis step-through.
The results of the maximum overpressurization analyses show that the requirements of the ASME code regarding overpressure protection are met for Cycle 10. The analysis shows that the dome pressure limit of 1325 psig is not exceeded and the vessel pressure does not exceed the limit of 1375 psig. The results of the maximum overpressurization analyses are presented in Table 7.1.
Framatome ANP, Inc.
EMF-2689 Revision 0 Page 2-3 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 2.1 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU*t I EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition
(% rated)
MCPRn
- LHGRFAC, MCPRp LHGRFACp 0
2.70 0.75 2.70 0.77 Base
-25 2.20 0.75 2.20 0.77 case 25 2.07 0.75 1.95 0.77 operationt 60 1.52 1.00 1.50 1.00 100 1.43 1.00 1.42 1.00 0
2.86 0.66 2.70 0.69 EOOS 25 2.36 0.66 2.20 0.69 Case 1 25 2.36 0.66 2.15 0.69 (FHOOS* OR 60 1.59 0.94 1.58 0.90 TBVOOS) 80 0.94 0.90 100 1.47 0.95 1.45 0.90 0
2.86 0.65 2.70 0.67 EOOS Case 2O 25 2.36 0.65 2.20 0.67 25 2.36 0.65 2.15 0.67 (Any combination of 80 1.81 0.88 1.86 0.79 TCV slow closure, 80 1.74 0.88 1.67 0.79 no RPT OR FHOOS) 80 1.74 0.88 1.67 0.79 100 1.54 0.89 1.52 0.79 0
2.86 0.66 2.70 0.69 25 2.36 0.66 2.20 0.69 TBVOOS 25 2.36 0.66 2.15 0.69 with I stuck closed TCV 60 1.59 0.77 1.58 0.77 80 0.77 0.77 100 1.47 0.83 1.45 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.
t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.
SWith or without 1 stuck closed TCV.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 2-4 Table 2.1 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times BOC to 15,000 MWd/MTU*, t (Continued)
Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 203F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.
t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.
SWith or without 1 stuck closed TCV.
Framatome ANP, Inc.
EMF-2689 Revision 0 Paae 2-5 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis Table 2.2 Base Case and EOOS MCPRp Limits and LHGRFACP Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTU*, t EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition
(% rated)
MCPRp LHGRFACp MCPRp LHGRFACp 0
2.70 0.74 2.70 0.76 Base 25 2.20 0.74 2.20 0.76 case 25 2.15 0.74 1.96 0.76 operationt 60 1.55 1.00 1.54 1.00 100 1.46 1.00 1.44 1.00 0
2.95 0.64 2.70 0.69 EOOS 25 2.45 0.64 2.20 0.69 Case 1 25 2.45 0.64 2.19 0.69 (FHOOSt OR 60 1.62 0.94 1.62 0.89 TBVOOS) 80 0.94 0.91 100 1.51 0.95 1.48 0.92 0
2.95 0.64 2.70 0.67 EOOS Case 2t 25 2.45 0.64 2.20 0.67 25 2.45 0.64 2.19 0.67 (Any combination of 80 1.82 0.87 1.86 0.76 TCV slow closure, 80 1.74 0.87 1.73 0.76 no RPT OR FHOOS) 100 1.59 0.87 1.59 0.76 0
2.95 0.64 2.70 0.69 25 2.45 0.64 2.20 0.69 TBVOOS 25 2.45 0.64 2.19 0.69 with 1 stuck 40 0.77 0.77 closed TCV 60 1.62 0.77 1.62 0.77 80 0.77 0.77 100 1.51 0.83 1.48 0.80 Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20°F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.
t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.
SWith or without 1 stuck closed TCV.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 2.2 Base Case and EOOS MCPRp Limits and LHGRFACP Multipliers for TSSS Insertion Times BOC to 15,000 MWd/MTU*.t (Continued)
EOOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition
(% rated)
MCPRP LHGRFACP MCPRP T LHGRFACP Single-loop operationt (SLO)
SLO with EOOS Case 1 (FHOOS* OR TBVOOS)
SLO with EOOS Case 21 (Any combination of TCV slow closure, no RPT OR FHOOS)
SLO with TBVOOS AND 1 stuck closed TCV 100 I.
L 0.83 1.49 0.80 0
25 25 60 100 0
25 25 60 80 100 0
25 25 80 80 100 0
25 25 40 60 80 100 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20°F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.
t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.
SWith or without 1 stuck closed TCV.
Framatome ANP, Inc.
EMF-2689 Revision 0 Page 2-6 0.76 I
2.71 2.21 2.16 1.56 1.47 2.96 2.46 2.46 1.63 1.52 2.96 2.46 2.46 1.83 1.75 1.60 2.96 2.46 2.46 1.63 1.52 0.74 0.74 0.74 1.00 1.00 0.64 0.64 0.64 0.94 0.94 0.95 0.64 0.64 0.64 0.87 0.87 0.87 0.64 0.64 0.64 0.77 0.77 0.77 0.83 2.71 2.21 1.97 1.55 1.45 2.71 2.21 2.20 1.63 1.49 2.71 2.21 2.20 1.87 1.74 1.60 2.71 2.21 2.20 1.63 1.49 0.76 0.76 1.00 1.00 0.69 0.69 0.69 0.89 0.91 0.92 0.67 0.67 0.67 0.76 0.76 0.76 0.69 0.69 0.69 0.77 0.77 0.77 0.80
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 2-7 Table 2.3 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC** t EOOS Power ATRIUM-10 Fuel Condition
(% rated)
MCPRp LHGRFAC 0
2.70 0.75 Base 25 2.20 0.75 case 25 2.07 0.75 operation*
60 1.52 1 0n EOOS Case 1 (FHOOS* OR TBVOOS)
EOOS Case 2*
(Any combination of TCV slow closure, no RPT OR FHOOS)
TBVOOS with 1 stuck closed TCV 100 0
25 25 60 80 100 0
25 25 80 80 100 0
25 25 60 80 100 1.47 2.86 2.36 2.36 1.59 1.47 2.86 2.36 2.36 1.81 1.74 1.59 2.86 2.36 2.36 1.59 1.47 1.00 0.66 0.66 0.66 0.94 0.94 0.95 0.65 0.65 0.65 0.84 0.84 0.84 0.65 0.65 0.65 0.77 0.77 0.83 ATRIUM-9B Fuel p
MCPRP LHGRFACP 2.70 0.76 2.20 0.76 1.95 0.76 1.50 1.00 1.43 1.00 2.70 0.69 2.20 0.69 2.15 0.69 1.58 0.90 0.90 1.45 0.90 2.70 0.67 2.20 0.67 2.15 0.67 1.86 0.79 1.67 0.79 1.58 0.79 2.70 0.69 2.20 0.69 2.15 0.69 1.58 0.77 0.77 1.45 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20°F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.
t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.
t With or without 1 stuck closed TCV.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 2-8 Table 2.3 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for NSS Insertion Times 15,000 MWd/MTU to EOC*t (Continued)
EOOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition
(% rated)
MCPRP LHGRFACP MCPRP LHGRFACp 0
2.71 0.75 2.71 0.76 Single-loop 25 2.21 0.75 2.21 0.76 operation 25 2.08 0.75 1.96 0.76 (SLO) 60 1.53 1.00 1.51 1.00 100 1.48 1.00 1.44 1.00 0
2.87 0.66 2.71 0.69 SLO with EOOS 25 2.37 0.66 2.21 0.69 Case 1 25 2.37 0.66 2.16 0.69 (FHOOSt OR 60 1.60 0.94 1.59 0.90 TBVOOS) 80 0.94 0.90 100 1.48 0.95 1.46 0.90 0
2.87 0.65 2.71 0.67 SLO with EOOS 25 2.37 0.65 2.21 0.67 Case 2t 25 2.37 0.65 2.16 0.67 (Any combination of 80 1.82 0.84 1.87 0.79 TCV slow closure, no RPT OR FHOOS) 80 1.75 0.84 1.68 0.79 100 1.60 0.84 1.59 0.79 0
2.87 0.65 2.71 0.69 SLO with 25 2.37 0.65 2.21 0.69 TBVOOS 25 2.37 0.65 2.16 0.69 AND 1 stuck 60 1.60 0.77 1.59 0.77 closed TCV 80 0.77 0.77 100 1.48 0.83 1.46 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.
t GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACP multipliers used in Cycle 9 remain applicable.
S With or without 1 stuck closed TCV.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 2-9 Table 2.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWdlMTU to EOC*- I EQOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition
(% rated)
MCPRp LHGRFACp MCPRP LHGRFACp 0
2.70 0.74 2.70 0.76 Base 25 2.20 0.74 2.20 0.76 case 25 2.15 0.74 1.96 0.76 operation*
60 1.55 1.00 1.54 1.00 100 1.50 1.00 1.44 1.00 0
2.95 0.64 2.70 0.69 EOOS 25 2.45 0.64 2.20 0.69 Case 1 25 2.45 0.64 2.19 0.69 (FHOOS* OR 60 1.62 0.94 1.62 0.89 TBVOOS) 80 0.94 0.91 100 1.51 0.95 1.48 0.92 0
2.95 0.64 2.70 0.67 EOOS Case 2O 25 2.45 0.64 2.20 0.67 25 2.45 0.64 2.19 0.67 (Any combination of 80 1.82 0.82 1.86 0.76 TCV slow closure, 80 1.74 0.82 1.73 0.76 no RPT OR FHOOS) 100 1.64 0.82 1.65 0.76 0
2.95 0.64 2.70 0.69 25 2.45 0.64 2.20 0.69 TBVOOS 25 2.45 0.64 2.19 0.69 with 1 stuck 40 0.77 0.77 closed TCV 60 1.62 0.77 1.62 0.77 80 0.77 0.77 100 1.51 0.83 1.48 0.80 Limits support operation with any combination of 1 SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20°F reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.
GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.
SWith or without 1 stuck closed TCV.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Pane 2-10, Table 2.4 Base Case and EOOS MCPRp Limits and LHGRFACp Multipliers for TSSS Insertion Times 15,000 MWd/MTU to EOC*t (Continued)
EOOS Power ATRIUM-10 Fuel ATRIUM-9B Fuel Condition
(% rated)
MCPRP LHGRFACp MCPRp LHGRFACp 0
2.71 0.74 2.71 0.76 Single-loop 25 2.21 0.74 2.21 0.76 operation*
25 2.16 0.74 1.97 0.76 (SLO) 60 1.56 1.00 1.55 1.00 100 1.51 1.00 1.45 1.00 0
2.96 0.64 2.71 0.69 SLO with EOOS 25 2.46 0.64 2.21 0.69 Case 1 25 2.46 0.64 2.20 0.69 (FHOOS*
60 1.63 0.94 1.63 0.89 ORTBVOOS) 80 0.94 0.91 100 1.52 0.95 1.49 0.92 0
2.96 0.64 2.71 0.67 SLO with EOOS 25 2.46 0.64 2.21 0.67 Case 22 25 2.46 0.64 2.20 0.67 (Any combination of 80 1.83 0.82 1.87 0.76 TCV slow closure, no RPT OR FHOOS) 80 1.75 0.82 1.74 0.76 100 1.65 0.82 1.66 0.76 0
2.96 0.64 2.71 0.69 25 2.46 0.64 2.21 0.69 SLO with 25 2.46 0.64 2.20 0.69 TBVOOS AND 1 stuck 40 0.77 0.77 closed TCV 60 1.63 0.77 1.63 0.77 80 0.77 0.77 100 1.52 0.83 1.49 0.80 Limits support operation with any combination of I SRVOOS, up to 2 TIPOOS (or the equivalent number of TIP channels), up to a 20OF reduction in feedwater temperature (except for conditions with FHOOS), and up to 50% of the LPRMs out of service in the standard, ICF, and MELLLA regions of the power/flow map.
GE9 fuel assemblies will use the ATRIUM-9B MCPR limits and the GE9 MAPFACf and MAPFACp multipliers used in Cycle 9 remain applicable.
With or without 1 stuck closed TCV.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Paae 2-11 0
10 20 30 40 50 60 70 80 90 100 110 Flow (% rated)
Flow MCPRf MCPRf
(% of rated)
ATRIUM-10 ATRIUM-9B*
0 1.63 1.63 30 1.63 1.63 100 1.19 1.19 105 1.11 1.11 Figure 2.1 Flow-Dependent MCPR Limits for Manual Flow Control Mode GE9 fuel assemblies will use the ATRIUM-9B MCPR limits.
Framatome ANP, Inc.
1.65 1.60 1.55 1.50 1.45 1.40
- a.
1.35 1.30 1.25 1.20 1.15 1.10
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.10 1.00 0.90 S0.80 C,
-J 0.70 0.60 0.50 EMF-2689 Revision 0 P
Pn 9-19 PlantTransent Aa-vsi 0
10 20 30 40 50 60 70 80 90 100 110 Flow (% rated)
Flow
(% rated)
LHGRFACf*
0 0.72 30 0.72 68 1.00 105 1.00 Figure 2.2 Flow-Dependent LHGRFAC Multipliers for ATRIUM-10 and ATRIUM-9B Fuel GE9 MAPFACf and MAPFACP multipliers used in Cycle 9 remain applicable.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-1 3.0 Transient Analysis for Thermal Margin - Base Case Operation This section describes the analyses performed to determine the power-and flow-dependent MCPR and LHGR operating limits for base case operation at LaSalle Unit 1 Cycle 10.
COTRANSA2 (Reference 4), XCOBRA-T (Reference 11), XCOBRA (Reference 7), and CASMO-3G/MICROBURN-B (Reference 3) are the major codes used in the thermal limits analyses as described in FRA-ANP's THERMEX methodology report (Reference 7) and neutronics methodology report (Reference 3). COTRANSA2 is a system transient simulation code, which includes an axial one-dimensional neutronics model that captures the effects of axial power shifts associated with the system transients. XCOBRA-T is a transient thermal hydraulics code used in the analysis of thermal margins for the limiting fuel assembly. XCOBRA is used in steady-state analyses. The ANFB critical power correlation (Reference 6) is used to evaluate the thermal margin of the ATRIUM-9B fuel assemblies and the SPCB critical power correlation (Reference 12) is used for the ATRIUM-10 fuel. Fuel pellet-to-cladding gap conductance values are based on RODEX2 (Reference 13) calculations for the LaSalle Unit 1 Cycle 10 core configuration.
3.1 System Transients System transient calculations have been performed to establish thermal limits to support L1C10 operation. Reference 9 identifies the potential limiting events that need to be evaluated on a cycle-specific basis. The potentially limiting transients evaluated for Cycle 10 include the LRNB, FWCF, CRWE, and LOFH events. Other transient events are bound by the consequences of one of the limiting transients.
Reactor plant parameters for the system transient analyses are shown in Table 3.1 for the 100%
power/100% flow conditions. Additional plant parameters used in the analyses are presented in Reference 8. Analyses have been performed to determine power-dependent MCPR and LHGR limits that protect operation throughout the power/flow domain depicted in Figure 1.1. At LaSalle, direct scram and recirculation pump high-to low-speed transfer on turbine stop valve (TSV) and turbine control valve (TCV) position are bypassed at power levels less than 25% of rated. Reference 14 indicates that MCPR and LHGR limits need to be monitored at power levels greater than or equal to 25% of rated. As a result, all analyses used to establish base case MCPRP limits and LHGRFACP multipliers are performed with both direct scram and RPT operable for power levels at or above 25% of rated.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-2 The limiting exposure for rated power pressurization transients is typically at end of full power (EOFP) when the control rods are fully withdrawn. To provide additional margin to the operating limits earlier in the cycle, analyses were also performed to establish operating limits at 15,000 MWd/MTU. Off-rated power analyses were performed at cycle exposures prior to EOC to ensure that the operating limits provide the necessary protection.
All pressurization transients assumed only the 11 highest set point safety relief valves (SRVs) were operable, consistent with the discussion in Section 7.0. In order to support operation with 1 SRV out-of-service, the pressurization transient analyses were performed with the lowest set point SRV out-of-service, which makes a total of 10 SRVs available.
The term, recirculation pump trip (RPT), is used synonymously with recirculation pump high-to low-speed transfer as it applies to pressurization transients. During the high-to low-speed transfer, the recirculation pumps trip off line and coast. When they reach the low-speed setting, the pumps reengage at the low speed. The time it takes for the pumps to coast to the low speed condition is much longer than the duration of the pressurization transients. Therefore, a recirculation pump trip has the same effect on pressurization transients as a recirculation pump high-to low-speed transfer.
Reductions in feedwater temperature of less than 201F from the nominal feedwater temperature are considered base case operation, not an EOOS condition. The reduced feedwater temperature is limiting for FWCF transients. As a result, the base case FWCF results are based on a 20°F reduction in feedwater temperature.
The results of the system pressurization transients are sensitive to the scram speed used in the calculations. To take advantage of average scram speeds faster than those associated with the Technical Specifications surveillance times, scram speed-dependent MCPRp limits and LHGRFACP multipliers are provided. The NSS insertion times and the average scram speeds associated with the Technical Specifications surveillance times (identified as TSSS times) used in the analyses reported are presented in Reference 8 and reproduced in Table 3.2. The NSS MCPRP limits and LHGRFACp multipliers can only be applied if the scram speed surveillance tests meet the NSS insertion times. System transient analyses were performed to establish MCPRP limits and LHGRFACp multipliers for base case operation for both NSS and TSSS insertion times.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-3*
3.1.1 Load Reiection No Bypass The load rejection causes a fast closure of the turbine control valve. The resulting compression wave travels through the steam lines into the vessel and creates a rapid pressurization. The increase in pressure causes a decrease in core voids, which in turn causes a rapid increase in power. The fast closure of the turbine control valve also causes a reactor scram and a recirculation pump high-to low-speed transfer which helps mitigate the pressurization effects.
Turbine bypass system operation, which also mitigates the consequences of the event, is not credited. The excursion of the core power due to the void collapse is terminated primarily by the reactor scram and revoiding of the core. The analysis assumed single-element feedwater level control; however, three-element feedwater level control will have an insignificant impact on thermal limit or pressure results. For manual feedwater level control, the feedwater control system response is slower than the pressurization event. As a result, using manual feedwater level control will also have an insignificant impact on thermal limit or pressure results.
The generator load rejection without turbine bypass system (LRNB) is a more limiting transient than the turbine trip no bypass (TTNB) transient. The initial position of the TCV is such that it closes faster than the turbine stop valve. This more than makes up for any differences in the scram signal delays between the two events.
LRNB analyses were performed for several power/flow conditions to support generation of the thermal limits. Tables 3.3 and 3.4 present the LRNB transient results for both TSSS and NSS insertion times for Cycle 10. For illustration, Figures 3.1-3.3 are presented to show the responses of various reactor and plant parameters during the LRNB event initiated at 100% of rated power and 105% of rated core flow with TSSS insertion times.
3.1.2 Feedwater Controller Failure The increase in feedwater flow due to a failure of the feedwater control system to maximum demand results in an increase in the water level and a decrease in the coolant temperature at the core inlet. The increase in core inlet subcooling causes an increase in core power. As the feedwater flow continues at maximum demand, the water level continues to rise and eventually reaches the high water level trip set point. The initial water level is conservatively assumed to be at the lower level operating range at 30 inches above instrument zero to delay the high level trip and maximize the core inlet subcooling that results from the FWCF. The high water level trip causes the turbine stop valves to close in order to prevent damage to the turbine from Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-4 excessive liquid inventory in the steam line. The valve closures create a compression wave that travels to the core causing a void collapse and subsequent rapid power excursion. The closure of the turbine valves initiates a reactor scram and a recirculation pump high-to low-speed transfer. In addition, the turbine bypass valves are assumed operable and provide some pressure relief. The core power excursion is mitigated in part by the pressure relief, but the primary mechanisms for termination of the event are reactor scram and revoiding of the core.
FWCF analyses were performed for several power/flow conditions to support generation of the thermal limits. Tables 3.5 and 3.6 present the base case FWCF transient results for both TSSS and NSS insertion times for Cycle 10. For illustration, Figures 3.4-3.6 are presented to show the responses of various reactor and plant parameters during the FWCF event initiated at 100%
of rated power and 105% of rated core flow with TSSS insertion times.
3.1.3 Loss of Feedwater Heatinq During the loss of feedwater heating (LOFH) event, there is an assumed 1450F decrease in the feedwater temperature. The result is an increase in core inlet subcooling, which collapses voids thereby increasing the core power and shifting the axial power distribution toward the bottom of the core. As a result of the axial power shift and increased core power, voids begin to build up at the bottom of the core, acting as negative feedback to the void collapse process. The negative feedback moderates the core power increase. The MICROBURN-B code is used to determine the change in MCPR and LHGR during the event. Analyses were performed for several cycle exposures to ensure that appropriate limits are set. Although there is a substantial increase in core thermal power during the event, the increase in steam flow is much less because a large part of the added power is used to overcome the increase in inlet subcooling.
The increase in steam flow is accommodated by the pressure control system via the TCVs or the turbine bypass valves so no pressurization occurs. The LOFH results are presented in Table 3.7. The PAPT LHGR limit was not exceeded in any of the analyses. PAPT LHGR limits are presented in References 21 and 22.
3.1.4 Control Rod Withdrawal Error The control rod withdrawal error (CRWE) transient is hypothesized as an inadvertent reactor operator initiated withdrawal of a control rod. This withdrawal increases local power and core thermal power. This results in lowering the core MCPR. The CRWE transient is typically terminated by control rod blocks initiated by the rod block monitor, however, in determination of Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Pevisn 0-9 the limiting ACPR for LI C1 0, no credit was taken for the rod block monitor. The limiting CRWE ACPR is 0.19 and the limiting fraction of LHGR is 1.22. A limiting fraction of LHGR less than 1.35 ensures that the PAPT LHGR limits for ATRIUM-10 and ATRIUM-9B fuel are not exceeded.
3.2 MCPR Safety Limit The MCPR safety limit is defined as the minimum value of the critical power ratio at which the fuel can be operated, with the expected number of rods in boiling transition not exceeding 0.1 %
of the fuel rods in the core. The MCPR safety limit for all fuel in the LaSalle Unit 1 Cycle 10 core was determined using the methodology described in Reference 5. The effects of channel bow on core limits are determined using a statistical procedure. The mean channel bow is determined from the exposure of the fuel channels and measured channel bow data.
CASMO-3G is used to determine the effect on the local peaking factor distribution. Once the channel bow effects on the local peaking factors are determined, the impact on the core limits is determined in the MCPR safety limit analysis. Further discussion of how the effects of channel bow are accounted for is presented in Reference 5. The main input parameters and uncertainties used in the safety limit analysis are listed in Table 3.8. The radial power uncertainty includes the effects of up to 2 TIPOOS or the equivalent number (42% of the total number of channels) of TIP channels (100% available at startup), up to 50% of the LPRMs out of-service, and an LPRM calibration interval of 2500 EFPH as discussed in References 16 and
- 19. The channel bow local peaking uncertainty is a function of the nominal and bowed local peaking factors and the standard deviation of the measured bow data.
The determination of the safety limit explicitly includes the effects of channel bow and relies on the following assumptions:
Cycle 10 will not contain channels used for more than one fuel bundle lifetime.
The channel exposure at discharge will not exceed 50,000 MWd/MTU based on the fuel bundle average exposure.
The Cycle 10 core contains all CarTech-supplied channels.
Analyses were performed with input parameters (including the radial power and local peaking factor distributions) consistent with each exposure step in the design-basis step-through. The analysis that produced the highest number of rods in boiling transition corresponds to a Cycle 10 exposure of 500 MWd/MTU. The radial power distribution corresponding to a Cycle 10 Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-6 exposure of 500 MWd/MTU is shown in Figure 3.7. Eight fuel types were represented in the LaSalle Unit 1 Cycle 10 safety limit analysis: two ATRIUM-10 fuel types loaded in Cycle 10 (Al 0-4039B-15GV75 and A10-4037B-16GV75); four ATRIUM-9B fuel types loaded in Cycle 9 (SPCA9-384B-1 1 GZ-80M, SPCA9-393B-1 6GZ-1 0OM, SPCA9-396B-1 2GZB-1 0OM, and SPCA9-396B-12GZC-1OOM); and two GE9 fuel types loaded in Cycle 8 (GE9B-P8CWB343 12GZ-80M-150 and GE9B-P8CWB342-10GZ-80M-150).
The local power peaking factors, including the effects of channel bow, at 70% void and assembly exposures consistent with a Cycle 10 exposure of 500 MWd/MTU are presented in Figures 3.8 and 3.9 for the Cycle 10 ATRIUM-10 fuel. The bowed local peaking factor data used in the MCPR safety limit analysis for fuel type Al 0-4039B-1 5GV75 is at an assembly average exposure of 1000 MWd/MTU. The data for fuel type Al 0-4037B-1 6GV75 is at an assembly average exposure of 500 MWd/MTU.
The results of the analysis support a two-loop operation MCPR safety limit of 1.09 and a single loop operation MCPR safety limit of 1.10 for all fuel types in the Cycle 10 core. However, the TLO and SLO MCPR safety limits used to establish the MCPR operating limits are 1.11 and 1.12 respectively, since they are the values currently in the Technical Specifications. These results are applicable for all EOD and EOOS conditions presented in Table 1.1. A MCPR safety limit of 1.10 is needed to support startup with uncalibrated LPRMs for an exposure range of BOC to 500 MWd/MTU in both TLO and SLO.
3.3 Power-Dependent MCPR and LHGR Limits Figures 3.10 and 3.11 present the base case operation NSS ATRIUM-10 and ATRIUM-9B MCPRp limits for Cycle 10 for the BOC to 15,000 MWd/MTU exposure range. Figures 3.12 and 3.13 present the ATRIUM-10 and ATRIUM-9B MCPRP limits for base case operation with TSSS insertion times for the BOC to 15,000 MWd/MTU exposure range. The 15,000 MWd/MTU to EOC MCPRp for ATRIUM-10 and ATRIUM-9B fuel are presented in Figures 3.14 and 3.15 for NSS insertion times and Figures 3.16 and 3.17 for TSSS insertion times. The limits are based on the ACPR results from the limiting system transient analyses discussed above and a MCPR safety limit of 1.11.
The pressurization transient analyses provide the necessary information to determine appropriate multipliers on the fuel design LHGR limit for ATRIUM-10 and ATRIUM-9B fuel to support off-rated power operation. Application of the LHGRFACp multipliers to the steady-state Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-7 LHGR limit ensures that the LHGR during AQOs initiated at reduced power does not exceed the PAPT limits. The method used to calculate the LHGRFACp multipliers is presented in Appendix A. The results of the LRNB and FWCF analyses discussed above were used to determine the base case LHGRFACp multipliers. The base.case ATRIUM-10 and ATRIUM-9B LHGRFACP multipliers for BOC to 15,000 MWd/MTU are presented in Figures 3.18 and 3.19 for NSS insertion times and Figures 3.20 and 3.21 for TSSS insertion times. The 15,000 MWd/MTU to EOC LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel are presented in Figures 3.22 and 3.23 for NSS insertion times and Figures 3.24 and 3.25 for TSSS insertion times.
In order to support operation of POWERPLEXk-II CMSS* below 25% core thermal power, representative limits are provided and have no impact on licensing since there is no requirement to monitor limits below 25% power.
3.4 Flow-Dependent MCPR and LHGR Limits Flow-dependent MCPR and LHGR limits are established to support operation at off-rated core flow conditions. The limits are based on the CPR and heat flux changes experienced by the fuel during slow flow excursions. The slow flow excursion event assumes a failure of the recirculation flow control system such that the core flow increases slowly to the maximum flow physically attainable by the equipment. An uncontrolled increase in flow creates the potential for a significant increase in core power and heat flux. A conservatively steep flow run-up path was determined starting at a low-power/low-flow state point of 56.2%P/30%F increasing to the high-power/high-flow state point of 124.2%P/105%F.
MCPRf limits are determined for the manual flow control (MFC) mode of operation for both ATRIUM-10 and ATRIUM-9B fuel. XCOBRA is used to calculate the change in critical power ratio during a two-loop flow run-up to the maximum flow rate. The MCPRf limit is set so that the increase in core power resulting from the maximum increase in core flow is such that the MCPR safety limit of 1.11 is not violated. Calculations were performed for several initial flow rates to determine the corresponding MCPR values that put the limiting assembly on the MCPR safety limit at the high-flow condition at the end of the flow excursion.
POWERPLEX is a trademark of Framatome ANP registered in the United States and various other countries.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 3-8 Results of the MFC flow run-up analysis are presented in Table 3.9 for both ATRIUM-10 and ATRIUM-9B fuel. MCPRf limits that provide the required protection during MFC operation are presented in Figure 2.1. The Cycle 10 MCPRf limits were established such that they support base case operation and operation in the EOD, EOOS, and combined EOD/EOOS scenarios.
The MCPRf limits are valid for all exposure conditions during Cycle 10. Since a low-to high speed pump upshift is required to attain high-flow rates, for initial core flows less than 30% of rated, the limit is conservatively set equal to the 30% flow value.
FRA-ANP has performed LHGRFACf analyses with the CASMO-3G/MICROBURN-B core simulator codes. The analysis assumes that the recirculation flow increases slowly along the limiting rod line to the maximum flow physically attainable by the equipment. A series of flow excursion analyses were performed at several exposures throughout the cycle starting from different initial power/flow conditions. Xenon is assumed to remain constant during the event.
The LHGRFACf multipliers were established to ensure that the LHGR during the flow run-up does not violate the PAPT LHGR limit. Since a low-to high-speed pump upshift is required to attain high-flow rates, for initial core flows less than 30% of rated, the LHGRFACf multiplier is conservatively set equal to the 30% flow value. The LHGRFACf values as a function of core flow for the ATRIUM-10 and ATRIUM-9B fuel are presented in Figure 2.2. The Cycle 10 LHGRFACf multipliers were established to support base case operation and operation in the EOD, EOOS, and combined EOD/EOOS scenarios for all Cycle 10 exposure conditions.
3.5 Nuclear Instrument Response The impact of loading ATRIUM-10 fuel into the LaSalle core will not affect the nuclear instrument response. The neutron lifetime is an important parameter affecting the time response of the incore detectors. The neutron lifetime is a function of the nuclear and mechanical design of the fuel assembly, the in-channel void fraction, and the fuel exposure.
The neutron lifetimes are similar for the FRA-ANP fuel types with typical values of 39(10-) to 40(10-6) seconds for the ATRI UM-9B lattices and 37(106) to 43(10"6) seconds for the ATRIUM-10 bottom and top lattices, respectively, as calculated with the CASMO-3G code.
Therefore, the neutron lifetimes are essentially equivalent as the core transitions to ATRIUM-10 fuel.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 3.1 LaSalle Unit I Plant Parameters for the System Transient Analyses at Rated Power and Flow Reactor thermal power (MWt) 3489 Total core flow (Mlbm/hr) 108.5 Core active flow*
94.8 Core bypass flow*' t 13.7 Core inlet enthalpy*
(Btu/Ibm) 523.9 Vessel pressures (psia)
Steam dome 1001 Core exit (upper-plenum)*
1013 Lower-plenum*
1038 Turbine pressure (psia) 957 Feedwater/steam flow (Mlbm/hr) 15.145 Feedwater enthalpy*
(Btu/Ibm) 406.6 Recirculating pump flow (per pump)
(Mlbm/hr) 15.83 Core average gap coefficient (EOC)*
(Btu/hr-ft2-F) 1959 Framatome ANP, Inc.
EMF-2689 Revision 0 Paae 3-9 t
Calculated values.
Includes water channel flow.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 r-age.-
10L Table 3.2 Scram Speed Insertion Times Control Rod TSSS NSS Position Time Time (notch)
(sec)
(sec) 48 (full-out) 0.00 0.00 48*
0.20*
0.20*
45 0.53 0.38 39 0.85 0.68 25 1.90 1.68 5
3.45 2.68 0 (full-in) 7.00 7.00 As indicated in Reference 8, the delay between scram signal and control rod motion is conservatively modeled. Sensitivity analyses indicate that using no delay provides slightly conservative results.
Framatome ANP, Inc.
EMF-2689 Revision 0 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis Table 3.3 15,000 MWdlMTU Base Case LRNB Transient Results Peak Peak Power/
ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR LHGRFACp
(% rated)
(% rated)
TSSS Insertion Times 100/105 0.35 1.03 0.33 1.00 415 122 100/100 0.34 1.02 0.33 1.00 390 122 100/81 0.35 1.03 0.31 1.00 318 121 80/105 0.35 1.04 0.34 1.00 335 97 80 /57.2 0.37 1.07 0.32 1.00 217 95 60/105 0.32 1.07 0.33 1.00 219 72 60/35.1 0.18 1.16 0.23 1.11 108 66 40/105 0.25 1.14 0.26 1.08 99 46 25/105 0.19 1.22 0.18 1.19 42 27 NSS Insertion Times 100/105 0.32 1.03 0.31 1.00 306 120 100/100 0.31 1.02 0.30 1.00 323 120 100/81 0.29 1.03 0.23 1.00 308 117 80/105 0.32 1.06 0.30 1.00 284 94 80/57.2 0.25 1.12 0.18 1.06 169 89 60/105 0.30 1.08 0.30 1.00 195 70 60/35.1 0.09 1.23 0.10 1.20 79 61 40/105 0.24 1.15 0.24 1.10 94 45 25/105 0.18 1.22 0.17 1.20 41 27 Framatome ANP, Inc.
Pa e 3-11
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3I-12 Table 3.4 EOC Base Case LRNB Transient Results Peak Peak Power!
ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR LHGRFACp
(% rated)
(% rated)
TSSS Insertion Times 100/105 0.35*
1.00 0.33 1.00 415*
122*
100/100 0.34 1.00 0.33 1.00 460 132 100/81 0.39 1.00 0.33 1.00 516 135 80 /105 0.35*
1.02 0.34*
1.00 335*
97*
80/57.2 0.39 1.00 0.36 1.00 313 105 60 / 105 0.32*
1.06 0.33*
1.00 219*
72*
60/35.1 0.34 1.06 0.31 1.07 163 74 40/105 0.25*
1.14*
0.26*
1.08*
99*
46*
25/105 0.20 1.22*
0.18*
1.19" 42 28 NSS Insertion Times 100/105 0.33 1.00 0.32 1.00 435 128 100/100 0.34 1.00 0.32 1.00 439 129 100/81 0.36 1.00 0.32 1.00 513 132 80/105 0.32*
1.03 0.30*
1.00 284*
94*
80/57.2 0.34 1.03 0.30 1.00 277 101 60/105 0.30*
1.07 0.30*
1.00*
195*
70*
60/35.1 0.27 1.09 0.23 1.09 138 70 40/105 0.24*
1.15*
0.24*
1.10*
94*
45*
25/105 0.18*
1.22*
0.17*
1.20*
41" 27*
The analysis results are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 3-13 Table 3.5 15,000 MWd/MTU Base Case FWCF Transient Results Peak Peak Power/
ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFACp ACPR LHGRFACp
(% rated)
(% rated)
TSSS Insertion Times 100/105 0.33 1.06 0.30 1.00 342 122 100/100 0.32 1.07 0.29 1.00 321 121 100/81 0.31 1.09 0.27 1.03 221 117 80/105 0.37 1.03 0.35 1.00 268 101 80/57.2 0.32 1.13 0.24 1.09 149 92 60/105 0.44 1.00 0.43 1.00 184 80 60/35.1 0.12 1.20 0.16 1.18 85 65 40/105 0.60*
0.91*
0.57 0.88 88*
57*
25/105 1.04*
0.74*
0.85 0.76 59*
44*
NSS Insertion Times 100/105 0.29 1.09 0.25 1.03 266 117 100/100 0.28 1.09 0.24 1.03 245 116 100/81 0.25 1.10 0.20 1.03 209 113 80 /105 0.34 1.05 0.31 1.00 226 98 80/57.2 0.20 1.16 0.17 1.15 118 87 60/105 0.41 1.01 0.39 1.00 165 78 60/35.1 0.12 1.23 0.12 1.22 65 63 40 / 105 0.56 0.93 0.55 0.89 101 59 25 / 105 0.96*
0.75*
0.84 0.77 55*
43*
The analysis results are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0 Pn a "qIA Pý~2..I Table 3.6 EOC Base Case FWCF Transient Results Peak Peak Power/
ATRIUM-10 ATRIUM-10 ATRIUM-9B ATRIUM-9B Neutron Flux Heat Flux Flow ACPR LHGRFAC)
ACPR LHGRFACp
(% rated)
(% rated)
TSSS Insertion Times 100/105 0.33*
1.05 0.30*
1.00*
342*
122*
100/100 0.32*
1.06 0.29*
1.00*
321*
121*
100/81 0.31*
1.05 0.27*
1.03 221*
117*
80/105 0.37*
1.03*
0.35*
1.00*
268*
101*
80/57.2 0.34 1.08 0.30 1.07 217 100 60/105 0.44*
1.00*
0.43*
1.00 184*
80*
40 / 105 0.60*
0.91*
0.57*
0.88*
88*
57*
25/105 1.04*
0.74*
0.85*
0.76*
59*
44*
NSS Insertion Times 100/105 0.29 1.06 0.27 1.03 366 126 100/100 0.29 1.06 0.26 1.03 345 125 100/81 0.28 1.05 0.24 1.03 273 123 80/105 0.34*
1.05 0.31*
1.00*
226*
98*
80/57.2 0.29 1.10 0.25 1.08 192 97 60/105 0.41" 1.01*
0.39*
1.00*
165*
78*
40/105 0.56*
0.93*
0.55*
0.89*
101*
59*
25 / 105 0.96*
0.75*
0.84*
0.77*
55*
43*
The analysis results are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-15 Table 3.7 Loss of Feedwater Heating Base Case Transient Analysis Results Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Pck a"1-1r P ý2.
Table 3.8 Input for MCPR Safety Limit Analysis Source Statistical Parameter Document Treatment Critical power correlation*
ATRIUM-10 Reference 12 Convoluted ATRIUM-9B Reference 17 Convoluted Radial power References 10 and 16 Convoluted Local peaking factor Reference 5 Convoluted Assembly flow rate (mixed core)
Reference 5 Convoluted Channel bow local peaking Function of nominal and bowed local Convoluted peaking and standard deviation of bow data (see Reference 18)
Nominal Values and Plant Measurement Uncertainties Uncertainty (%)
Statistical Parameter Value (Reference 8)
Treatment Feedwater flow ratet (Mlbm/hr) 23.6 1.76 Convoluted Feedwater temperature (OF) 426.5 0.76 Convoluted Core pressure (psia) 1031.35 0.50 Convoluted Total core flow (Mlbm/hr) 113.9 2.50 Convoluted Core powert (MWth) 5446.6 Additive constant uncertainties values are used.
Feedwater flow rate and core power were increased above design values to attain desired core MCPR for safety limit evaluation consistent with Reference 5 methodology.
Framatome ANP, Inc.
Fuel-Related Uncertainties t
EMF-2689 Revision 0 Page 3-17 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 3.9 Flow-Dependent MCPR Results Core 105%
Flow Maximum Core Flow
(% rated)
ATRIUM-10 ATRIUM-9B 30 1.58 1.58 40 1.52 1.51 50 1.46 1.46 60 1.40 1.41 70 1.34 1.35 80 1.27 1.28 90 1.22 1.22 100 1.17 1.15 105 1.11 1.11 Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-18 500.0 CORE POWER HEAT FLUX 4oo~o
-CORE FLOW.
400.0-
-C 0W--
STEAM FLOW ooFEED FLOW
.300.0 C
U 0
200.0 z
w 100.0 -
.0
-100.0
.0 1.0 2.0 3.0 4.0 5.0 6.0
- TIME, SECONDS LSA CYCLE 10 100/105 TSSS LRNB 10/11/01 07:46:04 NOS 10079.
JOB ID=08112 Figure 3.1 EOC Load Rejection No Bypass at 100/105 - TSSS Key Parameters Framatome ANP, Inc.
EMF-2689 Revision 0 Paae 3-19 LaSalle Unit 1 Cycle 10 Plant Transient Analysis 40.0 0
Ld N
F U) z LUI 0 Z m
z
-i LU LLU F
I-"
-.J U)
U)
LUJ 3.0 TIME, SECONDS LSA CYCLE 10 100/105 TSSS LRNB 10/11/01 07:46:04 NOS-10079, JOB 10-08112 Figure 3.2 EOC Load Rejection No Bypass at 100/105 - TSSS Vessel Water Level Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-20*
a_
Li U]
0 0
LSA CYCLE 10 100/105 TSSS LRNB 10/11/01 07:46:04 NOS=10079, JOB ID-08112 Figure 3.3 EOC Load Rejection No Bypass at 100/105-TSSS Dome Pressure Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis CORE POWER HEAT FLUX CORE FLOW STEAM FLOW FEED FLOW 200.0-100.0 -------
5.0 10.0 15.0 TIME, SECONDS LSA CYCLE 10 100/105 TSSS FWCF 10/11/01 09:41:45 NOS=10115, JOB 10==08156 Figure 3.4 EOC Feedwater Controller Failure at 1001105 - TSSS Key Parameters Framatome ANP, Inc.
EMF-2689 Revision 0 Pra - '-91 300.0-0 U
0 z ILl 0~
.0
-100.0
.0 26.0 25.0 4L=U.I.;
100.0 I
I I
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 0
LU N
1-V) z Ld 0
m z
-j LU LUd
-,J Ix I"-
_J UL (61 C,)
uJ TIME, SECONDS LSA CYCLE 10 100/105 TSSS FWCF 10/11/01 09:41:45 NOS=10115, JOB C-08156 Figure 3.5 EOC Feedwater Controller Failure at 100/105-TSSS Vessel Water Level Framatome ANP, Inc.
EMF-2689 Revision 0 0
- 1) 13' alJu
LaSalle Unit 1 Cycle 10 Plant Transient Analysis CL 1z SJ" Ir h-i (n
- b 0~
0 EMF-2689 Revision 0 Paqe 3-23 TIME, SECONDS LSA CYCLE 10 100/105 TSSS FWCF 10/11/01 09:41:45 NOS'=10115, JOB D-08156 Figure 3.6 EOC Feedwater Controller Failure at 100/105 - TSSS Dome Pressure Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis
_0 C
"4 0
-o E
-z 200 175 150 125 100 75 50 25 0
.0
.1
.2
.3
.4
.5
.6
.7
.8
.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 Radial Power Peaking Figure 3.7 Radial Power Distribution for SLMCPR Determination Framatome ANP, Inc.
EMF-2689 Revision 0 Pane 3-24
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 3-25 CONTROL ROD CORNER 0
N T
1.057 1.212 1.130 1.268 1.225 1.252 1.226 1.234 1.172 1.013 R
0 L
1.212 0.000 0.540 1.036 0.000 0.512 0.971 0.536 0.000 1.156 R
0 D
1.130 0.540 0.901 0.904 0.499 0.892 0.948 0.920 0.538 1.214 C
0 R
1.268 1.036 0.904 0.924 1.058 1.151 1.121 1.003 0.999 1.134 N
E R
1.225 0.000 0.499 1.058 1.114 0.529 1.248 Internal 1.252 0.512 0.892 1.151 Water 1.203 0.000 1.152 Channel 1.226 0.971 0.948 1.121 1.066 0.541 1.167 1.234 0.536 0.920 1.003 1.114 1.203 1.066 0.534 1.162 1.151 1.172 0.000 0.538 0.999 0.529 0.000 0.541 1.162 0.000 1.084 1.013 1.156 1.214 1.134 1.248 1.152 1.167 1.151 1.084 1.022 Figure 3.8 LaSalle Unit I Cycle 10 Safety Limit Local Peaking Factors AIO-4039B-15GV75 With Channel Bow (Assembly Exposure of 1000 MWd/MTU)
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis CONTROL ROD CORNER 0
N T
R 0
L R
0 D
C 0
R N
E R
Figure 3.9 LaSalle Unit I Cycle 10 Safety Limit Local Peaking Factors AIO-4037B-16GV75 With Channel Bow (Assembly Exposure of 500 MWd/MTU)
Framatome ANP, Inc.
EMF-2689 Revision 0 Page 3-26 1.061 1.225 1.141 1.282 1.240 1.271 1.246 1.255 1.191 1.021 1.225 0.000 0.526 1.030
.000 0.504 0.983 0.528 0.000 1.176 1.141 0.526 0.868 0.844 0.487 0.891 0.955 0.928 0.530 1.238 1.282 1.030 0.844 0.482 1.003 1.143 1.127 1.014 1.013 1.155 1.240 0.000 0.487 1.003 1.126 0.522 1.273 Internal 1.271 0.504 0.891 1.143 Water 1.217 0.000 1.173 Channel 1.246 0.983 0.955 1.127 1.076 0.533 1.189 1.255 0.528 0.928 1.014 1.126 1.217 1.076 0.527 1.183 1.173 1.191 0.000 0.530 1.013 0.522 0.000 0.533 1.183 0.000 1.103 1.021 1.176 1.238 1.155 1.273 1.173 1.189 1.173 1.103 1.033
LaSalle Unit 1 Cycle 10 Plant Transient Analysis C.
W.
2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Page 3-27 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRp
(%)
Limit 100 1.43 60 1.52 25 2.07 25 2.20 0
2.70 Figure 3.10 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0
10 20 30 40 50 60 Power (% rated)
Power MCPRP
(%)
Limit 100 1.42 60 1.50 25 1.95 25 2.20 0
2.70 70 80 90 100 110 Figure 3.11 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Page 3-28
- 0.
a.
LRNB
- FWCF x CRWE x
-OLMCPR xU a
Ix
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 0.
EMF-2689 Revision 0 Page 3-29 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRp
(%)
Limit 100 1.46 60 1.55 25 2.15 25 2.20 0
2.70 Figure 3.12 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis I.
2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Pane 3-30 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRp
(%)
Limit 100 1.44 60 1.54 25 1.96 25 2.20 0
2.70 Figure 3.13 BOC to 15,000 MWd/MTU Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 285 2.75 2.65 2.55 2.45 2.35 225 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Paqe 3-31 10 20 30 40 50 60 70 80 90 100 110 Power (% Mted)
Power MCPRp
(%)
Limit 100 1.47 60 1.52 25 2.07 25 2.20 0
2.70 Figure 3.14 15,000 MWdlMTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0 0
1ý -2 Plant Tr--'sient Aa
.j]-v 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Figure 3.15 15,000 MWdlMTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
- 1.
- E Power MCPRp M%
Limit 100 1.43 60 1.50 25 1.°95 25 2.20 0
2.70
LaSalle Unit I Cycle 10 Plant Transient Analysis 0.
2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Page 3-33 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRp
(%)
Limit 100 1.50 60 1.55 25 2.15 25 2.20 0
2.70 Figure 3.16 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis
- 0.
I.
CL 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0
- 2i ~A 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRp
(%)
Limit 100 1.44 60 1.54 25 1.96 25 2.20 0
2.70 Figure 3.17 15,000 MWd/MTU to EOC Base Case Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis
- a.
.IL EMF-2689 Revision 0 PaQe 3-35 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 1.00 60 1.00 25 0.75 0
0.75 Figure 3.18 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.400 1.350 1.300 1.250 1.200 1.150 1.050
-1.000 0.950 0.900 0.850 0.800 0.750 0.700 0
10 20 30 40 50 60 Power (% rated) 70 80 90 100 110 Figure 3.19 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 O~n* n '*r, Uri T
LRNB m FWCF o
FWCF w/TCV Stuck, LHGRFACp S.U Power LHGRFACp
(%)
Multiplier 100 1.00 60 1.00 25 0.77 0
0.77
LaSalle Unit 1 Cycle 10 Plant Transient Analysis
- 0.
-I 1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 EMF-2689 Revision 0 P~ri. *-.*7 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFAC0
(%)
Multiplier 100 1.00 60 1.00 25 0.74 0
0.74 Figure 3.20 BOC to 15,000 MWd/MTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
rle 3-37
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.400 1.350 1.300 1.250 1.200 1.150 C' 1.100
, 1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 1.00 60 1.00 25 0.76 0
0.76 70 80 90 100 110 Figure 3.21 BOC to 15,000 MWdlMTU Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Page 3-38 LRNB FWCF o
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.400
- a.
IL
- z
.. I EMF-2689 Revision 0 Pacie 3-39 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 1.00 60 1.00 25 0.75 0
0.75 Figure 3.22 15,000 MWdlMTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Pace 3-40 1.400 1.350 1.300 1.250 1.200 1.150 o.1.100 S1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power
- LHGRFAC,
(%)
Multiplier 100 1.00 60 1.00 25 0.76 0
0.76 Figure 3.23 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.400 1.350 1.300 1.250 1.200 1.150
- 0. 1.100
,)
L 1.050 3j 1.000 0.950 0.900 0.850 0.800 0.750 0.700 EMF-2689 Revision 0 Page 3-41 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power
- LHGRFAC,
(%)
Multiplier 100 1.00 60 1.00 25 0.74 0
0.74 Figure 3.24 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.400 1.350 1.300 1.250 1.200 1.150 CL 1.100
-l 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 1.00 60 1.00 25 0.76 0
0.76 70 80 90 100 110 Figure 3.25 15,000 MWd/MTU to EOC Base Case Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Page 3-42 LRNB FWCF o
EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 4-1 4.0 Transient Analysis for Thermal Margin - Extended Operating Domain This section describes the development of the MCPR and LHGR limits to support operation in the following extended operating domains:
Increased core flow (ICF) to 105% of rated flow.
MELLLA power operation (refer to Figure 1.1).
Coastdown is currently not supported for LaSalle Unit 1 Cycle 10.
Final feedwater temperature reduction (FFTR) is currently not supported for LaSalle Unit 1 Cycle 10.
Results of the limiting transient analyses are used to determine appropriate MCPRp limits and LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel to support operation in the EOD scenarios. MCPRp limits and LHGRFACp multipliers are established for both ATRIUM-10 and ATRIUM-9B.
As presented in Reference 9, the MCPR safety limit analysis for the base case remains valid for operation in the EODs discussed below. Also, the flow-dependent MCPR and LHGR analyses described in Section 3.4 were performed such that the results are applicable for all the EODs.
4.1 Increased Core Flow The base case analyses presented in Section 3.0 were performed to support operation in the power/flow domain presented in Figure 1.1, which includes operation in the ICF region. As a result, the analyses performed for the base case support operation in the ICF extended operating domain.
4.2 MELLLA Operations The base case analyses presented in Section 3.0 were performed to support operation in the power/flow domain presented in Figure 1.1, which includes operation in the MELLLA region. As a result, the analyses performed for the base case support operation in the MELLLA operating domain.
4.3 Coastdown Analysis Coastdown operation is currently not supported for LaSalle Unit 1 Cycle 10.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 4-2 4.4 Combined Final Feedwater Temperature ReductionlCoastdown Combined FFTR/coastdown operation is currently not supported for LaSalle Unit 1 Cycle 10.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-1 5.0 Transient Analysis for Thermal Margin - Equipment Out-of-Service This section describes the development of the MCPR and LHGR operating limits to support operation in the following EOOS scenarios:
Feedwater heaters out-of-service (FHOOS) - 1 00°F feedwater temperature reduction.
0 Turbine bypass system out-of-service (TBVOOS).
0 Recirculation pump trip out-of-service (no RPT).
Slow closure of I or more turbine control valves.
1 stuck closed TCV.
1 recirculation pump loop (SLO).
Operation with 1 SRV out-of-service, up to 2 TIPOOS (or the equivalent number of TIP channels) and up to 50% of the LPRMs out-of-service is supported by the base case thermal limits presented in Section 3.0. No further discussion for these EOOS scenarios is presented in this section. The EOOS analyses presented in this section also include the same EOOS scenarios protected by the base case limits.
The base case MCPR safety limit for two-loop operation remains applicable for operation in the EOOS scenarios discussed below with the exception of single-loop operation. Also, the flow dependent MCPR and LHGR analyses described in Section 3.4 were performed such that the results are applicable in all the EOOS scenarios.
Most of the equipment out of service scenarios are divided into two cases. The limits provided for EOOS Case 1 are applicable for operation with FHOOS or TBVOOS. The limits for EOOS Case 2 support operation with any combination of TCV slow closure, no RPT or FHOOS.
Analyses for the limiting events and EOOS conditions for the two cases were performed to ensure that the limits provide the necessary protection. One TCV stuck closed is supported in combination with the other EOOS scenarios and is discussed separately. SLO with and without the other EOOS conditions is also discussed separately.
Results of the limiting transient analyses are used to establish appropriate MCPRp limits and LHGRFACP multipliers to support operation in the EOOS scenarios. All EOOS analyses were performed with both NSS and TSSS insertion times.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-2 5.1 EOOS Case 1 The EOOS Case 1 limits are applicable for operation with FHOOS or TBVOOS. The limits also support operation with FHOOS combined with 1 TCV stuck closed (See Section 5.4). The MCPRp limits and LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel for the EOOS Case 1 scenarios are presented in Figures 5.1-5.8 for 15,000 MWd/MTU and Figures 5.9-5.16 for EOC.
5.1.1 Feedwater Heaters Out-of-Service (FHOOS)
The FHOOS scenario assumes a 1 00°F reduction in the feedwater temperature. Operation with FHOOS is similar to operation with FFTR except that the reduction in feedwater temperature due to FHOOS can occur at any time during the cycle. The effect of the reduced feedwater temperature is an increase in the core subcooling which can change the power shape and core void fraction. Previous analysis (Reference 23) has verified that the LRNB event is less severe with FHOOS due to the decrease in steam flow and is nonlimiting. However, the FWCF event can get worse due to the increase in core inlet subcooling. FWCF analyses were performed for Cycle 10 to determine thermal limits to support operation with FHOOS. The ACPR and LHGRFACP results used to develop the 15,000 MWd/MTU operating limits with FHOOS are presented in Table 5.1. The ACPR and LHGRFACP results used to develop the EOC operating limits with FHOOS are presented in Table 5.2.
5.1.2 Turbine Bypass Valves Out-of-Service (TBVOOS)
The effect of operation with TBVOOS is a reduction in the system pressure relief capacity, which makes the pressurization events more severe. While the base case LRNB event is analyzed assuming the turbine bypass system out-of-service, operation with TBVOOS has an effect on the FWCF event. The FWCF event was evaluated for LaSalle Unit 1 Cycle 10 to support operation with TBVOOS. The ACPR and LHGRFACP results used to develop the 15,000 MWd/MTU operating limits with TBVOOS are presented in Table 5.1. The ACPR and LHGRFACp results used to develop the EOC operating limits with TBVOOS are presented in Table 5.2.
The TBVOOS condition can also affect the response of the loss of feedwater heating event.
During the event, the colder feedwater results in an increase in the inlet subcooling as well as an increase in the thermal power. Although there is a substantial increase in core thermal Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-3 "power, the increase in steam flow is much less because a large part of the added power is used to overcome the increase in inlet subcooling. However, there can be a small increase in steam flow. The turbine control valves will open to accommodate any increase in steam flow. If the steam flow increases beyond the total capacity of the turbine control valves, the turbine bypass valves open to provide pressure relief. With the turbine bypass valves inoperable, the system would pressurize if the steam flow were to increase above the total capacity of the TCVs. A review of the maximum steam flow obtained in the base case LOFH analyses showed that in some of the rated power cases, the steam flow did increase above the TCV total capacity. As a result, LOFH analyses were performed using the transient methodology (COTRANSA2
/XCOBRAT) to account for the effects of pressurization. Analyses were performed only at high power levels (100% and 80% of rated) since at lower power levels, the TCVs have sufficient capacity to accommodate the increase in steam flow. The LOFH ACPR and LHGRFACp results used to develop the 15,000 MWd/MTU operating limits with TBVOOS are presented in Table 5.1. Since the limiting exposure for the LOFH event is early in the cycle, the same results were used to develop the EOC operating limits with TBVOOS.
5.2 EOOS Case 2 The EOOS Case 2 limits are applicable for operation with any combination of TCV slow closure, no RPT or FHOOS. The limits also support operation with the same EOOS conditions combined with 1 TCV stuck closed (See Section 5.4). The spectrum of power/flow points and events performed to establish the EOOS Case 2 limits is based on previous analyses (Reference 20). The MCPRp limits and LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel for the EOOS Case 2 scenarios are presented in Figures 5.17-5.24 for 15,000 MWd/MTU and Figures 5.25-5.32 for EOC.
5.2.1 Recirculation Pump Trip Out-of-Service (No RPT)
This section summarizes the development of the thermal limits to support operation with the EOC RPT inoperable. When RPT is inoperable, no credit for tripping the recirculation pump on TSV position or TCV fast closure is assumed. The function of the RPT feature is to reduce the severity of the core power excursion caused by the pressurization transient. The RPT accomplishes this by helping revoid the core, thereby reducing the magnitude of the reactivity insertion resulting from the pressurization transient. Failure of the RPT feature can result in Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-4 higher operating limits because of the higher positive reactivity in the core at the time of control rod insertion.
Analyses were performed for LRNB and FWCF events assuming no RPT. The ACPR and LHGRFACP results used to develop the 15,000 MWd/MTU operating limits with no RPT are presented in Table 5.3. The ACPR and LHGRFACp results used to develop the EOC operating limits to support no RPT operation are presented in Table 5.4.
5.2.2 Slow Closure of the Turbine Control Valve LRNB analyses were performed to evaluate the impact of a TCV slow closure. Analyses were performed closing 3 valves in the normal fast closure mode and 1 valve in 2.0 seconds. Results provided in Reference 20 demonstrate that performing the analyses with 1 TCV closing in 2.0 seconds protects operation with up to 4 TCVs closing slowly. Sensitivity analyses below 80% power have shown that the pressure relief provided by all 4 TCVs closing slowly can be sufficient to preclude the high-flux scram set point from being exceeded. Therefore, credit for high-flux scram is not taken for analyses at 80% power and below. The 80% power TCV slow closure analyses were performed both with and without high-flux scram credited. The ACPR and LHGRFACP TCV slow closure analysis results used to establish the EOOS Case 2 operating limits at 15,000 MWd/MTU and EOC are presented in Tables 5.3 and 5.4, respectively.
The MCPRp limits are established with a step change at 80% power. At 80% power, the lower bound MCPRP limits are based on the analyses which credit high-flux scram; the upper-bound MCPRP limits are based on analyses which do not credit high-flux scram. The EOOS Case 2 limits protect the scenario of all 4 TCVs closing slowly.
5.2.3 Combined FHOOS/TCV Slow Closure and/or No RPT The EOOS Case 2 limits were established to support operation with any combination of FHOOS, TCV slow closure or no RPT. The TCV slow closure ACPR and LHGRFACP results with FHOOS become less limiting than the TCV slow closure event with nominal feedwater temperature since the initial steam flow with FHOOS is lower and produces a less severe pressurization event. Subsequently, no TCV slow closure with FHOOS analyses were performed. Analyses were performed for the FWCF event with FHOOS and no RPT as the analysis results are potentially limiting, especially at low power levels. The ACPR and Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-5 LHGRFACp FWCF with FHOOS and no RPT analysis results used to establish the EOOS Case 2 operating limits at 15,000 MWd/MTU and EOC are presented in Tables 5.3 and 5.4, respectively.
5.3 Single-Loop Operation (SLO)
The impact of SLO at LaSalle on MCPR limits and LHGRFACp multipliers was presented in Reference 9. The base case ACPRs and LHGRFACp multipliers remain applicable. The only impact is on the MCPR safety limit. As presented in Section 3.2, the single-loop operation safety limit is 0.01 greater than the two-loop operating limit (1.12 compared to 1.11). The net result is an increase to the base case MCPRp limits of 0.01 as a result of the increase in the MCPR safety limit. The same situation is true for the EOOS scenarios. Adding 0.01 to the corresponding TLO EOOS MCPR limits results in SLO MCPR limits for the EOOS conditions.
The TLO EOOS LHGRFACp multipliers remain applicable in SLO.
5.4 1 Stuck Closed Turbine Control Valve With 1 of the turbine control valves assumed stuck closed, the other 3 TCVs will be further open when operating at a given power level. In addition, the highest attainable power is decreased because of the decreased steam flow capacity of the TCVs. With the valves further open, TCV closure events such as the LRNB and slow closure events, are less severe than with the valves further closed because the pressurization occurs over a longer time. While the FWCF event is not impacted during the turbine stop valve closure portion of the event, it may be impacted during the overcooling phase. At some power level between 80% and 100% of rated, the TCVs will be in the full open position with no ability to accommodate an increase in steam flow during the overcooling phase. The result is an increase in pressure prior to the turbine stop valve closure and a more severe event. Operation of the turbine bypass valves during the overcooling phase is not credited. Operation with 1 stuck closed TCV is supported in conjunction with the other EOOS conditions. As a result, FWCF analyses with 1 stuck TCV were performed for base case operation and the EOOS conditions where the FWCF is the limiting event (i.e. FHOOS, TBVOOS, no RPT and FHOOS with no RPT). Analyses are only performed at 80% and 100% power since at lower power levels, the initial TCV position is such that there is enough capacity left to accommodate the increase in steam flow during the overcooling phase. The ACPR and LHGRFACp analysis results for the FWCF with 1 stuck TCV Framatome ANP, Inc.
EMF-2689 LaSalle Unit I Cycle 10 Revision 0 Plant Transient Analysis Page 5-6 closed for base case and the EOOS conditions at 15,000 MWd/MTU and EOC are presented in Tables 5.5 and 5.6, respectively.
The 1 stuck closed turbine control valve condition may also impact the loss of feedwater heating event when combined with the TBVOOS condition. Any increase in steam flow causes the system to pressurize making the event more severe. LOFH analyses were performed to support operation with 1 TCV stuck closed and TBVOOS for 80% and 100% of rated power.
Analyses are only performed at 80% and 100% power since at lower power levels, the initial TCV position is such that there is enough capacity left to accommodate the increase in steam flow. The ACPR and LHGRFACp LOFH with 1 stuck TCV closed and TBVOOS analysis at 15,000 MWd/MTU and EOC are presented in Tables 5.5 and 5.6, respectively.
In most cases, the results in Tables 5.5 and 5.6 were used in establishing the base case, EOOS Case 1 and EOOS Case 2 operating limits. The inclusion of the 1 TCV stuck closed condition with other limits has little or no impact, with one exception being the combined 1 TCV stuck closed and TBVOOS scenario. Results for 1 TCV stuck closed are included with the base case limits presented in Figures 3.10-3.25. Results for EOOS Case 1 with 1 TCV stuck closed are presented in Figures 5.1-5.16. Results for EOOS Case 2 with 1 TCV stuck closed are presented in Figures 5.17-5.32. The EOOS Case 1 MCPRp limits protect the combined 1 TCV stuck closed with TBVOOS MCPR results. However, the LHGRFACp results for the combined 1 TCV stuck closed and TBVOOS are much lower than the TBVOOS results. Therefore, separate sets of operating limits were established. The LHGRFACp multipliers for ATRIUM-10 and ATRIUM-9B fuel for the I TCV stuck closed with TBVOOS condition are presented in Figures 5.33-5.36 for 15,000 MWd/MTU and Figures 5.37-5.40 for EOC.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 01 fn -r nci
+ Anni ici EMF-2689 Revision 0 Paqe 5-7 Table 5.1 EOOS Case I Analysis Results - 15,000 MWd/MTU Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated I
I % rated)
ACPR LHGRFACp ACPR LHGRFACp FHOOS With NSS Insertion Times FHOOS With TSSS Insertion Times TBVOOS With NSS Insertion Times 100/105 0.34 1.03 0.33 0.93 100/81 0.33 1.00 0.28 0.90 FWCF 80/105 0.40 1.01 0.38 0.94 80/57.2 0.28 1.10 0.22 1.04 60/105 0.48 0.97 0.47 0.91 25/105 0.92 0.77 0.92 0.74 The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
0" 1 U"O
ý"
Z--
LaSalle Unit 1 Cycle 10 EMF-2689 Revision 0 Paae 5-8 Table 5.1 EOOS Case I Analysis Results - 15,000 MWd/MTU (Continued)
Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated
/ % rated)
ACPR LHGRFACp ACPR LHGRFACp TBVOOS With TSSS Insertion Times The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
Plant Transient Analvsis
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Plant...,,_._
raI*
T e
lo-Table 5.2 EOOS Case I Analysis Results - EOC Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated
/ % rated)
ACPR LHGRFACP ACPR LHGRFACp FHOOS With NSS Insertion Times 100/105 0.30 1.06 0.28 1.01*
100/81 0.28 1.09 0.25 1.06 80/105 0.37*
1.02*
0.34*
0.97*
FWCF 80/ 57.2 0.30 1.09*
0.26 1.08*
60 / 105 0.47*
0.96*
0.45*
0.92*
40/105 0.69*
0.86*
0.66*
0.83*
25/105 1.25*
0.66*
1.04*
0.69*
FHOOS With TSSS Insertion Times 100 / 105 0.34*
1.04*
0.31*
0.97*
100/81 0.32*
1.08*
0.28*
1.03*
80/105 0.40*
1.00*
0.37*
0.95*
FWCF 80/57.2 0.35*
1.09" 0.30 1.07 60 / 105 0.49*
0.95*
0.48*
0.91" 40 / 105 0.76*
0.83*
0.69*
0.82*
25 / 105 1.34*
0.64*
1.08*
0.69*
TBVOOS With NSS Insertion Times 100/105 0.34 1.00 0.33 0.93*
100 / 81 0.36 0.95 0.33 0.90*
FWCF 80 / 105 0.40*
1.00 0.38*
0.94*
80/57.2 0.38 1.00 0.34 0.99 60 / 105 0.48*
0.97*
0.47 0.91*
The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
LaSalle Unit I Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Paae 5-10 Table 5.2 EOOS Case I Analysis Results - EOC (Continued)
Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated
/ % rated)
ACPR LHGRFACp ACPR LHGRFACp TBVOOS With TSSS Insertion Times 100/105 0.38*
1.00 0.36*
0.93*
100/81 0.39 0.95 0.34 0.92*
FWCF 80/105 0.43*
0.99*
0.42*
0.91*
80/57.2 0.43 1.00 0.39 0.98 60/105 0.51*
0.95*
0.51*
0.89*
100/105 0.23*
1.01*
0.22*
1.01*
LOFH 100/81 0.23*
0.95*
0.23*
0.95*
80 / 105 0.25*
1.05*
0.24*
1.05*
1 80 / 57.2 0.28*
0.94*
0.27*
0.94*
The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACP results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 P~ip. FR-1 1 Table 5.3 EOOS Case 2 Analysis Results - 15,000 MWd/MTU Power I Flow ATRIUM-10 ATRIUM-9B Event
(% rated
/ % rated)
ACPR LHGRFACp ACPR LHGRFACp TCV Slow Closure With NSS Insertion Times 100 / 105t 0.43 0.90 0.41 0.81 100 / loot 0.42 0.89 0.40 0.80 100 / 81t 0.39 0.91 0.41 0.82 80 / 105t 0.39 0.95 0.41 0.88 80 / 57.2t 0.63*
0.98 0.56 0.90 LRNB 80 / 105t 0.59*
0.88*
0.62 0.82 80/ 57.21 0.70*
0.91 0.75 0.83 60 / 105t 0.68 0.84 0.71 0.79 60 / 35.1 t 0.59 0.93 0.69 0.88 40 / 105t 0.84 0.77 0.84 0.75 25 /105t 1.19*
0.67*
1.02 0.69 TCV Slow Closure With TSSS Insertion Times 100 / 105t 0.48 0.88 0.48 0.78 100 / loot 0.48 0.87 0.48 0.77 100 / 81 0.43 0.87 0.45 0.76 80 / 105t 0.45 0.93 0.44 0.85 80 / 57.2t 0.63*
0.97 0.62 0.88 LRNB 80 / 105t 0.59*
0.88 0.62 0.82 80 / 57.2*
0.71*
0.90 0.75 0.83 60 / 105*
0.69 0.84 0.71 0.79 60/35.11 0.64 0.90 0.75 0.86 40 / 105t 0.85 0.77 0.86 0.74 25/105$
1.19*
0.67*
1.03 0.68 The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
t Scram initiated on high neutron flux.
"t Scram initiated on high dome pressure.
Framatome ANP, Inc.
Plant Transient Analvsis Parte 5-11
EMF-2689 Revision 0 Pace 5-12 LaSalle Unit 1 Cycle 10 Pl~nnf Trnn.*i*nt Annlvs*is Table 5.3 EOOS Case 2 Analysis Results - 15,000 MWd/MTU (Continued)
Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated
/ % rated)
ACPR LHGRFACp ACPR LHGRFACp No RPT With NSS Insertion Times 100/105 0.37 0.95 0.39 0.84 LRNB 100/81 0.30 0.91 0.34 0.79 80 /105 0.35 0.99 0.37 0.89 80 / 57.2 0.24 1.05 0.22 0.97 FWCF 100/105 0.32 1.01 0.32 0.92 No RPT With TSSS Insertion Times 100 /105 0.41 0.89 0.40 0.81 LRNB 100/81 0.35 0.93 0.36 0.81 80/105 0.39 0.95 0.40 0.87 80/57.2 0.37 1.01 0.35 0.93 FWCF 100/105 0.37 0.96 0.36 0.90 FHOOS/No RPT With NSS Insertion Times 100 / 105 0.33 1.01 0.32 0.93 FWCF 80/105 0.39 0.97 0.38 0.91 25/105 1.22*
0.65*
1.04 0.67 FHOOS/No RPT With TSSS Insertion Times 0.37 0.97 0.36 0.90 0.42 0.95 0.42 0.88 1.26*
0.64*
1.06 0.67 The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
Pln Tranien A, na...... tvsi
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Pane 5-13 Table 5.4 EOOS Case 2 Analysis Results - EOC Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated I % rated)
ACPR LHGRFACp ACPR LHGRFACp TCV Slow Closure With NSS Insertion Times 100 / 105t 0.48 0.90*
0.47 0.81*
100 / 81t 0.47 0.84 0.42 0.81 80 / 105t 0.45 0.94 0.43 0.88*
80 / 57.2' 0.63*
0.92 0.56 0.90*
LRNB 80 / 105' 0.59*
0.88*
0.62*
0.82*
80 / 57.2' 0.70*
0.86 0.75*
0.83*
60 / 105' 0.68*
0.84*
0.71*
0.79*
60 / 35.1 t 0.59*
0.93*
0.69*
0.88*
40/ 105t 0.84*
0.77*
0.84*
0.75*
25 / 105*
1.19*
0.67*
1.02*
0.69*
TCV Slow Closure With TSSS Insertion Times 100 / 105t 0.50 0.88*
0.49 0.78*
100 / 81t 0.47 0.84 0.45 0.76*
80 / 105t 0.46 0.93*
0.45 0.85*
80 / 57.2t 0.63*
0.94 0.62*
0.88*
80 / 105*
0.59*
0.88*
0.62*
0.82*
LRNB 80 / 57.2*
0.71*
0.86 0.75*
0.83*
60/ 1051 0.69*
0.84*
0.71*
0.79*
60 / 35.1t 0.64*
0.90*
0.75*
0.86*
40 / 105t 0.85*
0.77*
0.86*
0.74*
25 / 105t 1.19*
0.67*
1.03*
0.68*
The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACP results are conservatively used to establish the thermal limits.
t Scram initiated on high neutron flux.
"" Scram initiated on high dome pressure.
Frarnatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 5-14 Table 5.4 EOOS Case 2 Analysis Results - EOC (Continued)
Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated
/ % rated)
ACPR LHGRFACp ACPR LHGRFACp No RPT With NSS Insertion Times 100 /105 0.48 0.87 0.47 0.84*
LRNB 100/81 0.41 0.84 0.41 0.79*
80 /105 0.43 0.91 0.42 0.89*
80 / 57.2 0.35 0.93 0.30 0.90 FWCF 100 / 105 0.38 0.93 0.34 0.91 No RPT With TSSS Insertion Times 100 / 105 0.53 0.84 0.54 0.81*
LRNB 100 / 81 0.49 0.82 0.42 0.80 80 / 105 0.47 0.89 0.48 0.87 80 / 57.2 0.39 0.92 0.35 0.90 FWCF 100 / 105 0.43 0.90 0.42 0.88 FHOOS/No RPT With NSS Insertion Times 100 / 105 0.37 0.93 0.35 0.92 FWCF 80 /105 0.39*
0.97*
0.39 0.91 25/105 1.22*
0.65*
1.04*
0.67 FHOOS/No RPT With TSSS Insertion Times 0.41 0.92 0.42*
0.95*
1.26*
0.64*
The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACP results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
EMF-2689 Revision 0 Page 5-15 LaSalle Unit I Cycle 10 Plant Transient Analysis Table 5.5 1 TCV Stuck Closed Analysis Results - 15,000 MWd/MTU Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated
/ % rated)
ACPR LHGRFACp ACPR LHGRFACp Base CaselI TCV Stuck Closed With°NSS Insertion Times 100/105 0.30 1.08 0.27 1.02 FWCF 80/105 0.35 1.04 0.32 1.00 Base Casell TCV Stuck Closed With TSSS Insertion Times 100/105 0.34 1.05 0.31 1.00 100/81 0.31 1.08 I
0.27 1.03 80/105 0.39 1.02 0.36 1.00 80/57.2 0.32 1.13 0.24 1.09 FHOOSII TCV Stuck Closed With NSS Insertion Times 100/105 0.33 1.05 0.29 1.00 100/81 0.26 1.10 0.24 1.06 FWCF 80 / 105 0.39 1.00 0.36 0.95 80/57.2 0.26 1.15 0.21 1.12 FHOOSI1 TCV Stuck Closed With TSSS Insertion Times 100 / 105 0.36 1.02 0.33 0.96 100/81 0.33 1.06 0.29 1.01 FWCF 80 /105 0.42 0.98 0.39 0.93 80/57.2 0.36 1.09 0.28 1.05 Framatome ANP, Inc.
EMF-2689 Revision 0 Page 5-16 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis Table 5.5 1 TCV Stuck Closed Analysis Results - 15,000 MWdlMTU (Continued)
Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated I % rated)
ACPR LHGRFACp ACPR LHGRFACp TBVOOSI1 TCV Stuck Closed With NSS Insertion Times 100/105 0.36 1.02 0.34 0.93 100/81 0.33 1.00 0.28 0.90 FWCF 80/105 0.41 1.00 0.39 0.93 80/57.2 0.29 1.10 0.22 1.04 LOFH 80 / 57.2 0.42*
0.90*
0.35*
0.91*
TBVOOSI1 TCV Stuck Closed With TSSS Insertion Times 100/105 0.40 1.01 0.37 0.93 100/81 0.39 1.01 0.34 0.92 FWCF 80 / 105 0.45 0.98 0.43 0.90 80/57.2 0.41 1.06 0.35 0.99 100/105 0.36*
0.95*
0.32*
0.95*
100/81 0.36*
0.83 0.31 0.80 LOFH 80 / 105 0.42*
0.93*
0.38*
0.93*
80 / 57.2 0.44*
0.77 0.37*
0.77 No RPTI1 TCV Stuck Closed With NSS Insertion Times 100/105 0.34 1.01 0.33 0.93 80/105 0.38 0.99 0.38 0.91 No RPT11 TCV Stuck Closed With TSSS Insertion Times 100/105 0.38 0.98 0.37 0.89 80 / 105 0.42 0.96 0.42 0.88 The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Pl~nf Trnnsient Annlvi*
EMF-2689 Revision 0 Paae 5-17 Table 5.5 1 TCV Stuck Closed Analysis Results - 15,000 MWd/MTU (Continued)
Power ! Flow ATRIUM-10 ATRIUM-9B Event
(% rated I % rated)
ACPR LHGRFACp ACPR LHGRFACp FHOOSINo RPTI1 TCV Stuck Closed With NSS Insertion Times 100/105 0.35 0.99 0.34 0.92 80/105 0.41 0.95 0.41 0.89 FHOOSINo RPT/1 TCV Stuck Closed With TSSS Insertion Times 100/105 0.39 0.97 0.38 0.88 FWCF 80 /105 0.44 0.93 0.44 0.87 Framatome ANP, Inc.
Pinnt T nciant Anal sis L
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 P~na r-1 A
p ki, !;
I
% ~
Table 5.6 1 TCV Stuck Closed Analysis Results - EOC Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated
/ % rated)
ACPR LHGRFACp ACPR LHGRFACp Base Case/I TCV Stuck Closed With NSS Insertion Times FWCF 100/105 0.30 1.05 0.28 1.02" 80 / 105 0.35*
1.04*
0.32*
1.00*
Base Case/I TC V Stuck Closed With TSSS Insertion Times 100/105 0.34*
1.04 0.31*
1.00" FWF 100 /81 0.31 1.05 0.27*
1.03" 80/105 0.39*
1.02*
0.36*
1.00" 80/57.2 0.34 1.08 0.30 1.07 FHOOS/I TCV Stuck Closed With NSS Insertion Times 100/105 0.33*
1.05*
0.30 1.00" F100/81 0.29 1.08 0.27 1.05 80 / 105 0.39*
1.00*
0.36*
0.95*
80/57.2 0.31 1.11 0.27 1.08 FHOOS/1 TCV Stuck Closed With TSSS Insertion Times 100/105 0.36*
1.02*
0.33*
0.96*
FWCF 100/81 0.33*
1.06*
0.29*
1.01*
80/105 0.42*
0.98*
0.39*
0.93*
80/57.2 0.36*
1.09*
0.30 1.05*
The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
EMF-2689 Revision 0 Page 5-19 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 5.6 1 TCV Stuck Closed Analysis Results - EOC (Continued)
Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated I % rated)
ACPR LHGRFACP ACPR LHGRFACp TBVOOS/I1 TCV Stuck Closed With NSS Insertion Times 100/105 0.36*
1.00 0.34*
0.93*
100 / 81 0.36 0.95 0.33 0.90*
FWCF 80/105 0.41*
1.00*
0.39*
0.93*
80/57.2 0.38 1.02 0.34 1.00 TBVOOSI1 TCV Stuck Closed With TSSS Insertion Times 100/ 105 0.40*
1.01*
0.37*
0.93*
FWCF 100/81 0.39 0.95 0.34 0.92*
80/105 0.45*
0.98*
0.43*
0.90*
80/ 57.2 0.43 1.00 0.39 0.99*
100 / 105 0.36*
0.95*
0.32*
0.95*
LOFH 100 / 81 0.36*
0.83*
0.31*
0.80*
80 /105 0.42*
0.93*
0.38*
0.93*
80 / 57.2 0.44*
0.77*
0.37*
0.77*
No RPTII TCV Stuck Closed With NSS Insertion Times FWCF 100 / 105 0.38 0.93 0.35 0.91 80 / 105 0.38*
0.97 0.39 0.91*
No RPT/1 TCV Stuck Closed With TSSS Insertion Times FWCF 100 /105 0.43 0.90 0.43 0.88 80/105 0.42*
0.95 0.42*
0.88*
The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
EMF-2689 Revision 0 Paae 5-20 LaSalle Unit 1 Cycle 10 Plant Transient Analvsis Table 5.6 1 TCV Stuck Closed Analysis Results - EOC (Continued)
Power / Flow ATRIUM-10 ATRIUM-9B Event
(% rated
/ % rated)
ACPR LHGRFACp ACPR LHGRFACp FHOOSINo RPTI1 TCV Stuck Closed With NSS Insertion Times FWCF 100 / 105 0.38 0.93 0.36 0.91 80 /105 0.41 0.95*
0.41*
0.89*
FHOOS/No RPT11 TCV Stuck Closed With TSSS Insertion Times 100/105 0.42 0.92 0.41 0.88*
FWCF 100/81 0.35 0.95 0.31 0.93 80/105 0.44*
0.93*
0.44*
0.87*
1 80/ 57.2 0.33 1.05 0.29 1.03 The analysis results presented are from an earlier exposure in this cycle. The ACPR and LHGRFACp results are conservatively used to establish the thermal limits.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 C.
- 0.
C.,
2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 -
0 10 20 30 40 50 60 Power (% rated) 70 80 90 100 110 Power MCPRp
(%)
Limit 100 1.47 60 1.59 25 2.36 25 2.36 0
2.86 Figure 5.1 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Paae 5-21 18 FWCF No Bypass
+ FWCF FHOOS o FWCF No Bypass w/ TCV Stuck x FWCF FHOOS w/ TCV Stuck LOFH No Bypass LOFH No Bypass w/ TCV Stuck
-OLMCPR 1.15 Plant Transient Analvsis
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 0
u=
0.900 0.850 0.800 0.750 0.700 0.650 0.600 EMF-2689 Revision 0 Paae 5-22 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.95 80 0.94 60 0.94 25 0.66 25 0.66 0
0.66 Figure 5.2 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
Pane 5-22
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0
10 20 30 40 50 60 Power (% rated)
Power MCPRp
(%)
Limit 100 1.45 60 1.58 25 2.15 25 2.20 0
2.70 70 80 90 100 110 Figure 5.3 BOC to 15,000 MWd/MTU EOOS Case I Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Paae 5-23 FWCF No Bypass
+
FWCF No Bypass w/ TCV Stuck K FWCF FHOOS w/ TCV Stuck LOFH No Bypass LOFH No Bypass W/ TCV Stuck
-OLMCPR A
LaSalle Unit 1 Cycle 10 Plant Transient Analysis
- 0.
-z 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0.650 0.600 EMF-2689 Revision 0 Paoe 5-24 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.90 60 0.90 25 0.69 25 0.69 0
0.69 Figure 5.4 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
Pane 5-24
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 3.05 2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Pn a R.99 k2~ ~~~
0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRp
(%)
Limit 100 1.51 60 1.62 25 2.45 25 2.45 0
2.95 Figure 5.5 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis EMF-2689 Revision 0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.95 80 0.94 60 0.94 25 0.64 25 0.64 0
0.64 Figure 5.6 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
1.300 I t
%JAJ CL
,IL 0
- 9
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.85 2.75 2.65 255 2-45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Paqe 5-27 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRP
(%)
Limit 100 1.48 60 1.62 25 2.19 25 2.20 0
2.70 Figure 5.7 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 FWCF No Bypass
+
- =
FWCF FHOOS w/ TCV Stuck 1.150 A LOFH No Bypass
-LHGRFACp 1.100 1.050 C. 1.000 a: 0.950
,- na3 anj 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Figure 5.8 BOC to 15,000 MWd/MTU EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Pý2~5:~
Power LHGRFACp
(%)
Multiplier 100 0.92 80 0.91 60 0.89 25 0.69 25 0.69 0
0.69
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.95 285 2.75 2.65 2.55 245 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0
10 20 30 40 50 60 Power (% rated)
Power MCPRp
(%)
Limit 100 1.47 60 1.59 25 2.36 25 2.36 0
2.86 70 80 90 100 110 Figure 5.9 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 PaQe 5-29 SFWCFNo Bypass
+ FWCF FHOOS o FWCF No Bypass w TCV Stuck FWCF FHOOS w/ TCV Stuck LOFH No Bypass LOFH No Bypass w/ TCV Stuck OLMCPR
LaSalle Unit 1 Cycle 10 Plant Transient Analysis
- 0.
C,,
-J EMF-2689 Revision 0 Paqe 5-30 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.95 80 0.94 60 0.94 25 0.66 25 0.66 0
0.66 Figure 5.10 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis
- 0.
- 0.
C.,
2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Pane~ 5-31 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRp
(%)
Limit 100 1.45 60 1.58 25 2.15 25 2.20 0
2.70 Figure 5.11 15,000 MWdlMTU to EOC EOOS Case I Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.90 80 0.90 60 0.90 25 0.69 25 0.69 0
0.69 70 80 90 100 110 Figure 5.12 15,000 MWd/MTU to EOC EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Paqe 5-32 C-1.300 1.250 1.200 1.150 1.100 1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0.650 0.600 FWCF No Bypass
+
FWCFFHOOS o
FWCF No Bypass w/TCV Stuck x
FWCF FHOOS w/ TCV Stuck LHGRFACp 0 oo 00
+
0 o
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 3.05 2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 EMF-2689 Revision 0 Page 5-33 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRp
(%)
Limit 100 1.51 60 1.62 25 2.45 25 2.45 0
2.95 Figure 5.13 15,000 MWdlMTU to EOC EOOS Case I Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Pacqe 5-34 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 S0.950 C,
-J 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.95 80 0.94 60 0.94 25 0.64 25 0.64 0
0.64 70 80 90 100 110 Figure 5.14 15,000 MWdlMTU to EOC EOOS Case I Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
FWCF No Bypass
+
FWCF FHOOS W/ TCV Stuck A LOFH No Bypass
-LHGRFACp
+
Ax
+
I
++
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0
10 20 30 40 50 60 Power (9/ rated Power MCPRp
(%)
Limit 100 1.48 60 1.62 25 2.19 25 2.20 0
2.70 70 80 90 100 110 Figure 5.15 15,000 MWdlMTU to EOC EOOS Case I Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Page 5-35 0
FWCF No Bypass
+ FWCF FHOOS o FWCF No Bypass wY TCV Stuck K FWCF FHOOS w/ TCV Stuck LOFH No Bypass o
LOFH No Bypass w/ TCV Stuck OLvCPR
+
A
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050
,- 1.000
, 0.950 S 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0
10 20 30 40 50 60 Power (% rated) 70 80 90 100 110 Power LHGRFACp
(%)
Multiplier 100 0.92 80 0.91 60 0.89 25 0.69 25 0.69 0
0.69 Figure 5.16 15,000 MWd/MTU to EOC EOOS Case 1 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Page 5-36 FWCF No Bypass
+
LOFH No Bypass LHGRFACp
++
+
LaSalle Unit 1 Cycle 10 Plant Transient Anafysis EMF-2689 Revision 0 Paae 5-37 SlowTCV
+ FWCF FHOOS LRNB No RPT FWCF No RPT c3 FWCF FHOOS No RPT FWCF No RPT W TCV Stuck FWCF FHOOS No RPT W TCV Stuck OLMCPR
+
A
+
0 10 20 30 40 50 60 Power (% rated)
Power MCPRp
(%)
Limit 100 1.54 80 1.74 80 1.81 25 2.36 25 2.36 0
2.86 70 80 90 100 110 Figure 5.17 BOC to 15,000 MWdlMTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.300 1.250 1.200 1.150 1.100 1.050 C' 1.000 IrU.H S0.950
" 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.89 60 0.88 25 0.65 25 0.65 0
0.65 70 80 90 100 110 Figure 5.18 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Plant Transient A,,.,c-0,.0 A Slow TCV
+
FWCF FHOOS LRNBNoRPT m FWCF No RPT o
FWCF FHOOS No RPT FWCF No RPT W/ TCV Stuck FWCF FHOOS No RPT wI TCV Stuck
+
+
LHGRFACp
+
+
a3
+
AI AA A
LaSalle Unit 1 Cycle 10 Plant Transient Analysis
- SqowTCV
+ FWCF FHOOS LRNB No RPT FWCF No RPT o
FWCF FHOOS No RPT FWCF No RPT w/ TCV Stuck FWCF FHOOS No RPT W/ TCV Stuck OLMCPR A
2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0
10 20 30 40 50 60 Power % rated) a
+
+
70 80 90 100 110 Power MCPRp
(%)
Limit 100 1.52 80 1.67 80 1.86 25 2.15 25 2.20 0
2.70 Figure 5.19 BOC to 15,000 MWdlMTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Page 5-39
+
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.300 1.250 1.200 1.150 1.100 1.050 4 n
-n C,
S0.950 0
-J 0.900 0.850 0.800 0.750 0.700 0.650 0.600 EMF-2689 Revision 0 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.79 80 0.79 25 0.67 25 0.67 0
0.67 Figure 5.20 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
A Slow TCV
+
FWCF FHOOS LRNBNoRPT E FWCF No RPT FWCF FHOOS No RPT 0
FWCF No RPT w/ TCV Stuck A. FWCF FHOOS No RPT w/TCV Stuck
+
LHGRFACp
+
+
+
""A
.. 1-A cage;i-to
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 5-41 3.05 A Sow TCV 2.85
+ FWCF FHOOS 2.75 LRNB No RPT 2.65 a
FWCF FHOOS NO RPT 2-55 FWCF No RPT W TCV Stuck 2.45 L
FWCF FHOOS No RPT Yd TCV Stuck 2.35
_OLMCPR 2.25
- 2.15 S205 1.95 1.85
+
1.75 A
A 1.65 A
1.55
+
1.45 1.35 1.25 1.15 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Figure 5.21 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 IL S0.950
-j 0.900 0.850 0.800 0.750 0.700 0.650 0.600 EMF-2689 Revision 0 13m a r,.A*:
kiu ~~
0 10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.87 80 0.87 25 0.64 25 0.64 0
0.64 Figure 5.22 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
A Slow TCV
+ FWCF FHOOS LRNB No RPT m FWCF NoRPT a FWCF FHOOS No RPT o
FWCF No RPT w/ TCV Stuck A FWCF FHOOS No RPT W/ TCV Stuck LHGRFACp
+
A+
++
+
A At
LaSalle Unit 1 Cycle 10 Plant Transient Analysis A Slow TCV
+ FWCF FHOOS LRNB No RPT m FWCF No RPT o
FWCF No RPT w/ TCV Stuck A FWCF FHOOS No RPT w/ TCV Stuck OLMCPR
+
2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15
-I 0
10 20 30 40 50 60 Power (% rated) 70 80 90 100 110 Power MCPRp
(%)
Limit 100 1.59 80 1.73 80 1.86 25 2.19 25 2.20 0
2.70 Figure 5.23 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Paqe 5-43 Q,
1z
+
+
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050
- a. 1.000 0.950
"- 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.76 80 0.76 25 0.67 25 0.67 0
0.67 70 80 90 100 110 Figure 5.24 BOC to 15,000 MWd/MTU EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Parne 5-44 A
Slow TCV
+
& FWCF FHOOS No RPT w/ TCV Stuck LHGRFACp
+
t
+
t S
A A---
LaSalle Unit 1 Cycle 10 Plant Transient Analysis EMF-2689 Revision 0 Page 5-45 A Slow TCV
+ FWCF FHOOS LRNB No RPT a FWCF No RPT o FWCF FHOOS No RPT o FWCF No RPT wI TCV Stuck a FWCF FHOOS No RPT OLMCPR
+ A
+
0 10 20 30 40 50 60 Power (% rated)
Power MCPRp
(%)
Limit 100 1.59 80 1.74 80 1.81 25 2.36 25 2.36 0
2.86 70 80 90 100 110 Figure 5.25 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
C.
M.
CL 2.95 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 5-46 1.300 1.250 A Slow TCV
+
FWCF FHOOS 1.200 LRNB No RPT a
FWCF No RPT FWCF FHOOS No RPT 1.100 o
FWCF No RPTw/TCV Stuck a FWCF FHOOS No RPT
+
1.050 I
LHGRFACp
+
C. 1.000
,r 0.950 -
+
C, A
-J.9 00" "0.900 0.850 -+
A
- 0. 800 0.750 0.650 0.600 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.84 80 0.84 25 0.65 25 0.65 0
0.65 Figure 5.26 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0
10 20 30 40 50 60 Power (% rated)
Power MCPRP
(%)
Limit 100 1.58 80 1.67 80 1.86 25 2.15 25 2.20 0
2.70 70 80 90 100 110 Figure 5.27 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Paae 5-47 C.,
W A Slow TCV
FWCF FHOOS No RPT o FWCF No RPT W/ TCV Stuck FWCF FHOOS No RPT w/ TCV Stuck
-OLMCPR
+
4-
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0.950
-J 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.79 80 0.79 25 0.67 25 0.67 0
0.67 70 80 90 100 110 Figure 5.28 15,000 MWdlMTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Page 5-48 A
Slow TCV
+
FWCF No RPT o3 FWCF FHOOS No RPT FWCF No RPT W/ TCV Stuck A FWCF FHOOS No RPT w/ TCV Stuck
+
+
-LHGRFACp
+
A+
+
A AA AA A
- 4
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 5-49 3.05 2.95 A Slow TCV 2.85
+ FWCF FHOOS LRNB No RPT 2.75 n
FWCF FHOOS No RPT 2.55 FWCF No RPTw/ TCV Stuck 2.45
& FWCF FHOOS No RPT w/ TCV Stuck
-OLMCPR 2.35 2.25 it 2.15 S2.05 1.95 A
1.85
+
A 1.75 A
1.65
+t 1.55 1.45-4 1.35 1.25 1.15 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRP
(%)
Limit 100 1.64 80 1.74 80 1.82 25 2.45 25 2.45 0
2.95 Figure 5.29 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 5-50 1.300 1.250 A
Slow TCV
+
FWCF FHOOS 1.200 LRNB No RPT n FWCF No RPT 1.150 0
FWCF FHOOS No RPT 1.100 FWCF No RPT w/TCV Stuck z
FWCF FHOOS No RPT w/ TCV Stuck
+
1.050 LHGRFACp
+
+
C. 1.000
+
u
+
0.950
+
"-'0.900 A
A A
A 0.850 A
+
A 0.800 0.750 -
A 0.700 0.650 0.600 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.82 80 0.82 25 0.64 25 0.64 0
0.64 Figure 5.30 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Revisio-n Q.
- 0.
M.
2.85 2.75 2.65 2.55 2.45 2.35 2.25 2.15 2.05 1.95 1.85 1.75 1.65 1.55 1.45 1.35 1.25 1.15 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power MCPRP
(%)
Limit 100 1.65 80 1.73 80 1.86 25 2.19 25 2.20 0
2.70 Figure 5.31 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent MCPR Limits for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 5-52*
1.300 1.250 A Slow TCV
+
FWCF FHOOS 1.200 LRNB No RPT a FWCF No RPT 1.150 0 o FWCF FHOOS No RPT 1.100 o
& FWCF FHOOS No RPT w/ TCV Stuck 1.050 LHGRFACp
+
1.000 A
+
L W 0.950 C,
-z
+
UZUU
+
0.850 -
0.800 0.750
+
A t
A A
A 0
0 0.700 0.650 0.600 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Figure 5.32 15,000 MWd/MTU to EOC EOOS Case 2 Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
C.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0.650 FWCF No Bypass w/ TCV Stuck o
LOFH No Bypass w/ TCV Stuck LHGRFACp 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.83 80 0.77 40 0.77 25 0.66 25 0.66 0
0.66 70 80 90 100 110 Figure 5.33 BOC to 15,000 MWd/MTU I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Page 5-53 XI LL.
.-J 0
0 0
0
__z
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.300 1.250 1.200 1.150 1.100 U.
,i La..
-I
.J 1.050 1.000 0.950 0.850 0.800 0.750 0.700 0.650 0.600 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0
0.69 70 80 90 100 110 Figure 5.34 BOC to 15,000 MWd/MTU I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Priam !R-54 I
o FWCF No Bypass w/ TCV Stuck LOFH No Bypass w/TCV Stuck LHGRFACp 0
o 0
0 0
r
,Pane 5-54
SEMF-2689 LaSalle Unit 1 Cycle 10 evison9 Plant Transient Analysis Page 5-55 1.300 1.250 o
LOFH No Bypass w/TCV Stuck 1.200 SLHGRFACp 1.150 1.100 1.050 0
C. 1.000 0
0 0o0 uI.v 0
- 0.
x 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Figure 5.35 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
Power LHGRFACp
(%)
Multiplier 100 0.83 80 0.77 40 0.77 25 0.64 25 0.64 0
0.64
LaSalle Unit 1 Cycle 10 EM F-2689 Plant Transient Analysis Revision 0 Page 5-56 1.300 1.250 o FWCF No Bypass w/ TCV Stuck 1.200 0
LOFH No Bypass w/ TCV Stuck 1.150 LHGRFACp 1.100 1.050
- 0. 1.000 0
L,, 0.950 0
C,=
0
,- l flAr 0
10 20 30 40 50 60 70 80 90 100 110 Power (% rated)
Power
(%)
100 80 40 25 25 0
LHGRFACP Multiplier 0.80 0.77 0.77 0.69 0.69 0.69 Figure 5.36 BOC to 15,000 MWd/MTU 1 TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.300 1.250 1.200 1.150 1.100 1.050 C. 1.000 S0.950 0
-l0.900-0.850 0.800 0.*750 0.700 0.650 0.600 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.83 80 0.77 40 0.77 25 0.65 25 0.65 0
0.65 70 80 90 100 110 Figure 5.37 15,000 MWdlMTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Pn*
n 1-17 U
n,,
o FWCF No Bypass w/ TCV Stuck o
LOFH No Bypass w/ TCV Stuck LHGRFACp 0
0 0
0
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis 1.300 1.250 1.200 1.150 1.100 1.050 CL 1.000 S0.950 S0.900 0.850 0.800 0.750 0.700 0.650 0.600 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0
0.69 70 80 90 100 110 Figure 5.38 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - NSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0
£o I
..r.jo o
FWCF No Bypass w/ TCV Stuck LOFH No Bypass w/ Stuck TCV LHGRFACp 0
o 0
o0
)
LaSalle Unit 1 Cycle 10 Plant Transient Analvsis o FWCF No Bypass w/ TCV Stuck o
LOFH No Bypass w/ TCV Stuck LHGRFACp 1.100 1.050-
- a. 1.000
, 0.950 z
0.900 0.850 0.800 0.750 0.700 0.650-0 10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.83 80 0.77 40 0.77 25 0.64 25 0.64 0
0.64 70 80 90 100 110 Figure 5.39 15,000 MWdlMTU to EOC 1 TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-10 Fuel - TSSS Insertion Times Framatome ANP, Inc.
EMF-2689 Revision 0 Pn n
_-R U~i-~~
-vauL I 1.250 1.200 1.150 0
0 O
0 0
I.OUU
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0.950 0.900 0.850 0.800 0.750 0.700 0.650 0.600 0
10 20 30 40 50 60 Power (% rated)
Power LHGRFACp
(%)
Multiplier 100 0.80 80 0.77 40 0.77 25 0.69 25 0.69 0
0.69 70 80 90 100 110 Figure 5.40 15,000 MWd/MTU to EOC I TCV Stuck Closed With TBVOOS Power-Dependent LHGR Multipliers for ATRIUM-9B Fuel - TSSS Insertion Times Frarnatome ANP, Inc.
EMF-2689 Revision 0 Pane
- v-60 U.
o FWCF No Bypass w/ TCV Stuck I
o LOFH No Bypass wI TCV Stuck LHGRFACp 0
0 0
0B o0
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 6-1 6.0 Transient Analysis for Thermal Margin - EOD/EOOS Combinations The limits presented in Section 5.0 support operation with ICF in conjunction with the EOOS scenarios presented in Table 1.1. Operation in the other EOD conditions (i.e. coastdown and FFTR/coastdown) is currently not supported for LaSalle Unit 1 Cycle 10.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 7-1 7.0 Maximum Overpressurization Analysis This section describes the maximum overpressurization analyses performed to demonstrate compliance with the ASME Boiler and Pressure Vessel Code. The analysis shows that the safety/relief valves at LaSalle Unit 1 have sufficient capacity and performance to prevent the pressure from reaching the pressure safety limit of 110% of the design pressure.
7.1 Design Basis The MSIV closure analysis was performed with the FRA-ANP plant simulator code COTRANSA2 (Reference 4) at a power/flow state point of 102% of rated power/105% flow. As indicated in Reference 1, the overpressurization analysis was performed at a cycle exposure of EOC + 1000 MWd/MTU. The following assumptions were made in the analysis.
The most critical active component (direct scram on valve position) was assumed to fail.
However, scram on high-neutron flux and high-dome pressure is available.
At Exelon's request, analyses were performed to determine the minimum number of the highest set-point SRVs required to meet the ASME and Technical Specification pressure limits. It was determined that having the 10 highest set-point SRVs operable will meet the ASME and Technical Specification pressure limits. In order to support operation with 1 SRV out-of-service, the plant configuration needs to include at least 11 SRVs. As per ASME requirements, the SRVs are assumed to operate in the safety mode.
TSSS insertion times were used.
The initial dome pressure was set at the maximum allowed by the Technical Specifications (1035 psia).
An MSIV closure time of 1.1 seconds was assumed in the analysis.
EOC RPT is assumed inoperable; ATWS (high-dome pressure) RPT is available.
7.2 Pressurization Transients Results of analysis for the MSIV closure event initiated at 102% power/1 05% flow are presented in Table 7.1. Figures 7.1-7.5 show the response of various reactor plant parameters to the MSIV closure event. The maximum pressure of 1346 psig occurs in the lower plenum at approximately 4.3 seconds. The maximum dome pressure of 1321 psig occurs at 4.4 seconds.
The results demonstrate that the maximum vessel pressure limit of 1375 psig and dome pressure limit of 1325 psig are not exceeded.
Framatome ANP, Inc.
EMF-2689 Revision 0 Page 7-2 LaSalle Unit 1 Cycle 10 Plant Transient Analysis Table 7.1 ASME Overpressurization Analysis Results 102%P/105%F Peak Peak Maximum Maximum Neutron Heat Vessel Pressure Dome Flux Flux Lower-Plenum Pressure Event
(% rated)
(% rated)
(psig)
(psig)
MSIV closure 340 138 1346 1321 Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis 1.0 2.0 3.0 4.0 TIME, SECONDS 11/01/01 09:3503 LSA CYCLE 10 MSIV CLOSURE NQS-11894, JOB ID-19393 Figure 7.1 Overpressurization Event at 102/105 MSIV Closure Key Parameters Framatome ANP, Inc.
EMF-2689 Revision 0 Page (-3 300.0-0 LdJ z
a._
(C_
200.0 100.0-CORE POWER HEAT FLUX CORE FLOWi
__STEAM FLOW FEED FLOW
.0o-V I V
/
I iI
-100.0
.0 5.0 6.0 I
7.0 4000
LaSalle Unit I Cycle 10 Plant Transient Analysis 1.0 2.0 LSA CYCLE 10 MSIV CLOSURE 11/01/01 09:35:03 NQS-11894, JOB ID-19393 Figure 7.2 Overpressurization Event at 102/105 MSIV Closure Vessel Water Level Framatome ANP, Inc.
EMF-2689 Revision 0 Paae 7-4 0
LUj N
Li z
1.1
-j Li LI
-j Of Li
-j LI U._
I,
.0 3.0 4.0
- TIME, SECONDS 5.0 6.0 7.0
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page 7-5 1400.0 1350.0
(/)
1300.0 iL (V')
1250.0 LLJ Of Z
1200.0
-j Of LJ
- 1150.0 1100.0 1050.0
.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 TIME, SECONDS LSA CYCLE 10 MSIV CLOSURE 11/01/01 09:35:03 NQS,11894, JOB ID-19393 Figure 7.3 Overpressurization Event at 1021105 MSIV Closure Lower-Plenum Pressure Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 Plant Transient Analysis
<)
C Lj Of (n
1200.0 w
L*J 0
0 EMF-2689 Revision 0 Page 7-6 3.0 4.0 TIME, SECONDS 11/01/01 09:35:03 LSA CYCLE 10 MSIV CLOSURE NOS-11894, JOB ID-19393 Figure 7.4 Overpressurization Event at 102/105 MSIV Closure Dome Pressure Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Revision 0 Plant Transient Analysis Peiio 7-7 2000.0 SRV BANK 1 SRV BANK 2 SRV BANK,3 S...-3;---
-fi SRV BANK 5 1500.0 C9 m
._J S1000.0
> -x 1:n C.,')
6.0 7.0 11/01/01 09:35:03 LSA CYCLE 10 MSIV CLOSURE NQS-11894, JOB ID-19393 Number Opening of Pressure Bank SRVs (psia) 1 0
NA 2
2 1235.3 3
4 1245.6 4
4 1255.9 5
0 NA Figure 7.5 Overpressurization Event at 102/105 MSIV Closure Safety/Relief Valve Flow Rates Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Pevsn 8-1 8.0 References
- 1.
Letter, D. E. Garber (FRA-ANP) to R. J. Chin (Exelon), "LaSalle Unit 1 Cycle 10 Calculation Plan," DEG:01:084, June 6, 2001.
- 2.
XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.
- 3.
XN-NF-80-19(P)(A) Volume 1 Supplement 3, Supplement 3 Appendix F, and Supplement 4, Advanced Nuclear Fuels Methodology for Boiling Water Reactors:
Benchmark Results for the CASMO-3GIMICROBURN-B Calculation Methodology, Advanced Nuclear Fuels Corporation, November 1990.
- 4.
ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.
- 5.
ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.
- 6.
ANF-1 125(P)(A) and Supplement 1 and 2, ANFB Critical Power Correlation, Advanced Nuclear Fuels Corporation, April 1990.
- 7.
XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.
- 8.
EMF-2533 Revision 0, LaSalle Unit I Cycle 10 Principal Transient Analysis Parameters, Framatome ANP Richland, Inc., April 2001.
- 9.
Letter, D. E. Garber (FRA-ANP) to F. W. Trikur (Exelon), "Disposition of Events Summary for the Introduction of ATRIUMTM-10 Fuel at LaSalle County Station,"
DEG:01:179, October 30, 2001.
- 10.
Letter, D. E. Garber (SPC) to R. J. Chin (ComEd), "Description of Measured Power Uncertainty for POWERPLEX Operation Without Calibrated LPRMs," DEG:00:061, March 7, 2000.
- 11.
XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.
- 12.
EMF-2209(P)(A) Revision 1, SPCB Critical Power Correlation, Siemens Power Corporation, July 2000.
- 13.
XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Revision 0 Page 8-2 8.0 References (Continued)
- 14.
LaSalle County Nuclear Station Units 1 and 2 Improved Technical Specifications, as amended.
- 15.
EMF-2690 Revision 0, LaSalle Unit I Cycle 10 Reload Analysis, Framatome ANP, Inc.,
January 2002.
- 16.
EMF-1 903(P) Revision 3, Impact of Failed/Bypassed LPRMs and TIPs and Extended LPRM Calibration Interval on Radial Bundle Power Uncertainty, Siemens Power Corporation, March 2000.
- 17.
ANF-1 125(P)(A) Supplement 1 Appendix E, ANFB Critical Power Correlation Determination of A TRIUMTM -9B Additive Constant Uncertainties, Siemens Power Corporation, September 1998.
- 18.
ANF-1 373(P), Procedure Guide for SAFLIM2, Siemens Power Corporation, February 1991.
- 19.
Letter, D. E. Garber (SPC) to R. J. Chin (ComEd), "Extension of LPRM Calibration Interval to 2500 EFPH," DEG:00:088, April 17, 2000.
- 20.
EMF-2277 Revision 1, LaSalle Unit 1 Cycle 9 Plant Transient Analysis, Siemens Power Corporation, October 1999.
- 21.
EMF-2589(P) Revision 0, Mechanical and Thermal-Hydraulic Design Report for LaSalle Units I and 2 ATRIUMT -10 Fuel Assemblies, Framatome ANP Richland, Inc., July 2001.
- 22.
EMF-2563(P) Revision 1, Fuel Mechanical Design Report Exposure Extension for A TRIUMTm-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units, Framatome ANP Richland, Inc., August 2001.
- 23.
EMF-95-205(P) Revision 2, LaSalle Extended Operating Domain (EOD) and Equipment Out of Service (EQOS) Safety Analysis for ATRIUM TM -9B Fuel, Siemens Power Corporation, June 1996.
Framatome ANP, Inc.
LaSalle Unit 1 Cycle 10 EMF-2689 Plant Transient Analysis Page A-1 Appendix A Power-Dependent LHGR Limit Generation The linear heat generation rate (LHGR) operating limit is established to ensure that the steady state LHGR (SSLHGR) limit is protected during normal operation and that the protection against power transient (PAPT) LHGR limit is protected during an anticipated operational occurrence (AOO). To ensure that the LHGR operating limit provides the necessary protection during operation at off-rated conditions, adjustments to the SSLHGR limits may be necessary. These adjustments are made by applying power and flow-dependent LHGR multipliers (LHGRFACp and LHGRFACf, respectively) to the SSLHGR limit. The LHGR operating limit (LHGROL) for a given operating condition is determined as follows:
LHGROL = min [LHGRFACp x SSLHGR, LHGRFACf x SSLHGR]
The power-dependent LHGR multipliers (LHGRFACp) are determined using the heat flux excursion experienced by the fuel during AOOs. The heat flux ratio (HFR) is defined as the ratio of the maximum nodal transient heat flux over the maximum nodal heat flux at the initiation of the transient. The HFR provides a measure of the LHGR excursion during the transient. The PAPT limit divided by the SSLHGR limit provides an upper limit for the HFR to ensure that the PAPT LHGR limit is not violated during an AOO. LHGRFACp is set equal to the minimum of the PAPT/SSLHGR ratio over HFR, or 1.0. Based on the ATRIUM-10 LHGR limits presented in Reference A.1 and the ATRIUM-9B LHGR limits presented in Reference A.2, LHGRFACp is established as follows:
RAPT
= 1.35 SSLHGR HFR Qmaxt emaxO LHGRFACp = min [F.35* 1.0 In some cases, the established MCPR limit precludes operation at the SSLHGR limit. This allows for a larger LHGR excursion during the transient without violating the PAPT LHGR limit.
Framatome ANP, Inc.
EMF-2689 LaSalle Unit 1 Cycle 10 Revision 0 Plant Transient Analysis Page A-2 References A. 1 EMF-2589(P) Revision 0, Mechanical and Thermal-Hydraulic Design Report for LaSalle Units I and 2 A TRIUMTM-1O Fuel Assemblies, Framatome ANP Richland, Inc., July 2001.
A.2 EMF-2563(P) Revision 1, Fuel Mechanical Design Report Exposure Extension for A TRIUM Tm-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units, Framatome ANP Richland, Inc., August 2001.
Framatome ANP, Inc.