ML090920253
| ML090920253 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/31/2009 |
| From: | David Helker Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TS 6.9.1.12 | |
| Download: ML090920253 (15) | |
Text
Exelon Nuclear 200 Exelon Way Kennett Square, PA 19348 March 31, 2009 www.exeloncorp.com Exelon Nuclear TS 6.9.1.12 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Limerick Generating Station, Unit 2 Facility Operating License No. NPF-85 NRC Docket No. 50-353
Subject:
Issuance of the Core Operating Limits Report For Reload 10, Cycle 11, Revision 5 Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station (LGS), Unit 2, Reload 10, Cycle 11, Revision 5. Revision 5 of this report incorporates the revised cycle specific parameters resulting from the new core configuration implemented during the LGS, Unit 2 refueling outage.
This COLR is being submitted to the NRC in accordance with LGS, Unit 2 Technical Specifications (TS) Section 6.9.1.12.
If you have any questions, please do not hesitate to contact us.
Respectfully, David P. Helker Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachment cc:
S. J. Collins, Regional Administrator, Region I, USNRC E. M. DiPaolo, USNRC Senior Resident Inspector, LGS P. Bamford, Project Manager [LGS], USNRC R. R. Janati - Commonwealth of Pennsylvania
Exelon Nudear Fuels Doc ID: COLR Limerick 2, Rev. 5 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STAnON UNIT 2 RELOAD 10, CYCLE 11 (This is a complete rewrite)
Prepared By:
Reviewed By:
Approved By:
22&aL/
~
Gary Becknell Independent Reviewer Date:
Date:
Date:
Slal~onQualjfied*~ ~
Reviewed By: ~~
Robert Potter Station Qualified Reviewer Page 1 0114
Exelon Nuclear Fuels Table of Contents Doc ID: COLR Limerick 2, Rev. 5 Page 1.0 Terms And Defmitions 4
2.0 General Information 5
3.0 MAPLHGRLimits 6
4.0 MCPRLimits 7
5.0 Linear Heat Generation Rate Limits 9
6.0 Control Rod Block Setpoints 11 7.0 Turbine Bypass Valve Parameters 12 8.0 Stability Protection Setpoints 13 9.0 Modes OfOperation 13 10.0 Methodology 14 11.0 References 14 Page 2 of 14
Exelon Nuclear Fuels Iljst of Tables Doc ID: COLR Limerick 2, Rev. 5 Page TABLE 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types 6
TABLE 3-2 MAPLHGR Single Loop Operation (SLO) Reduction Factor 6
TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 7 TABLE 4-2 Power Dependent MCPR Limit Adjustments and Multipliers 8
TABLE 4-3 Flow Dependent MCPR Limits MCPR(F) 8 TABLE 5-1 Linear Heat Generation Rate Limits 9
TABLE 5-2 LHGR Single Loop Operation (SLO) Reduction Factor 9
TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 10 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 10 TABLE 6-1 Rod Block Monitor Setpoints 11 TABLE 6-2 Reactor Coolant System Recirculation Flow Upscale Trip 11 TABLE 7-1 Turbine Bypass System Response Time 12 TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability 12 TABLE 8-1 OPRM PBDA Trip Setpoints 13 TABLE 9-1 Modes OfOperation 13 Page 3 of14
Exelon Nuclear Fuels 1.0 Terms And Definitions Doc ID: COLR Limerick 2, Rev. 5 ARTS APRM, RBM, and Technical Specification Improvement Program BASE CASE DTSP EOOS EOR FFWTR FWHOOS HTSP ICF ITSP LHGR LHGRFAC(F)
LHGRFAC(P)
MCPR(P)
MELLLA OLMCPR OPRMPBDA RPTIS A case analyzed with Turbine Bypass System in service and Recirculation Pump Trip in service and Feedwater Temperature Reduction allowed (FFWTR includes feedwater heater OOS or final feedwater temperature reduction) at any point during the cycle in Dual Loop mode.
Rod Block Monitor Downscale Trip Setpoint Equipment Out of Service End ofRated, the cycle exposure at which reactor power is equal to 3458 MWth with recirculation system flow equal to 100%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.
Final Feedwater Temperature Reduction Feedwater Heaters Out of Service Rod Block Monitor High Trip Setpoint Increased Core Flow Rod Block Monitor Intermediate Trip Setpoint Linear Heat Generation Rate ARTS LHGR thermal limit flow dependent multipliers ARTS LHGR thermal limit power dependent multipliers Rod Block Monitor Low Trip Setpoint Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio ARTS MCPR flow dependent thermal limit ARTS MCPR power dependent thermal limit Maximum Extended Load Line Limit Analysis Operating Limit Minimum Critical Power Ratio Oscillation Power Range Monitor Period Based Detection Algorithm Recirculation Pump Trip In Service Page 4 of14
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 5 RPTOOS Recirculation Pump Trip Out of Service SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TBVIS Turbine Bypass Valves In Service TBVOOS Turbine Bypass Valves Out of Service 2.0 General Information This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit 2 Cycle 11:
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
Minimum Critical Power Ratio (MCPR)
Single Loop Operation (SLO) MCPR adjustment ARTS MCPR thermal limit adjustments and multipliers (MCPR(P) or MCPR(F))
ARTS LHGR thermal limit multipliers (LHGRFAC(p) or LHGRFAC(F))
Rod Block Monitor (RBM) setpoints MAPLHGR single loop operation reduction factor LHGR single loop operation reduction factor Linear Heat Generation Rate (LHGR)
Turbine Bypass Valve parameters Reactor Coolant System Recirculation Flow Upscale Trips Oscillation Power Range Monitor Period Based Detection Algorithm Trip Setpoints These values have been determined using NRC-approved methodology (Reference 6), and are established such that all applicable limits ofthe plant safety analysis are met.
This report is prepared in accordance with Technical Specification 6.9.1.9 of Reference 1. Preparation of this report was performed in accordance with Exelon Nuclear, Nuclear Fuels T&RM NF-AB-120-3600.
The data presented in this report is valid for all1icensed operating domains on the operating map, including:
Maximum Extended Load Line Limit down to 81% ofrated core flow during full power operation Increased Core Flow (ICF) up to 110% ofrated core flow Final Feedwater Temperature Reduction (FFWTR) up to 105°F during cycle extension operation Feedwater Heater Out of Service (FWHOOS) up to 60°F feedwater temperature reduction at any time during the cycle prior to cycle extension.
Further information on the cycle specific analyses for Limerick 2 Cycle 11 and the associated operating domains discussed above is available in Reference 2.
Page 5 of14
Exelon Nuclear Fuels 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description Doc ID: COLR Limerick 2, Rev. 5 The limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) ofeach fuel type as a function ofaverage planar exposure is given in Table 3-1 (Reference 2). The limiting MAPLHGR value is the same for all fuel types in the Limerick Unit 2 Cycle 11 core. For single loop operation, a reduction factor is used which is shown in Table 3-2 (Reference 2). MAPFAC(P) and MAPFAC(F) are 1.0 for all power and flow conditions. The power and flow dependent multipliers for MAPLHGR have been removed and replaced with LHGRFAC(P) and LHGRFAC(F) (See Reference 3). LHGRFAC(P) andLHGRFAC(F) are addressed in Section 5.0.
TABLE 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types (Reference 2)
Average Planar Exposure MAPLHGR Limit (GWD/STI (kW/ft) 0.0 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 TABLE 3-2 MAPLHGR Single Loop Operation (SLO) Reduction Factor (Reference 2)
SLO Reduction Factor I 0.80 Page 6 of 14
Exelon Nuclear Fuels 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description Doc ID: COLR Limerick 2, Rev. 5 Table 4-1 is derived from the Reference 2 analyses and is valid for all Cycle 11 fuel types and operating domains. Table 4-1 includes treatment ofthese MCPR limits for SLO. Bounding MCPR values are also provided for RPTOOS or TBVOOS. These two options represent the Equipment Out of Service conditions. The cycle exposure that represents EOR is given in the latest verified and approved Cycle Management Report or an associated Engineering Change Request.
ARTS provides for power and flow dependent thermal limit adjustments and multipliers, which allow for a more reliable administration of the MCPR thermal limit.
The flow-dependent adjustment MCPR(F) is sufficiently generic to apply to all fuel types and operating domains (Reference 2). In addition, there are four sets of power-dependent MCPR multipliers for use with the TBVIS, TBVOOS, RPTIS and RPTOOS conditions (References 2, 3 and 9). Section 7.0 contains the conditions for Turbine Bypass Valve Operability.
These adjustments are provided in Table 4-2 and 4-3.
The OLMCPR is determined for a given power and flow condition by evaluating the power-dependent MCPR and the flow-dependent MCPR and selecting the greater of the two. The MCPR(P) values are independent ofrecirculation pump trip operability (Reference 3).
TABLE 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)l (Reference 2)
SCRAM Cvcle EXDosure Time
< EOR-2700 2: EOR-2700 EOOS Combination Option 2
MWd/ST MWd/ST B
1.34 1.39 BASE A
1.37 1.42 B
1.44(3) 1.44(3)
BASE SLO A
1.44(3) 1.44 B
1.37 1.43 TBVOOS A
1.40 1.46 B
1.44(3) 1.45 TBVOOSSLO A
1.44(3) 1.48 B
1.40 1.47 RPTOOS A
1.51 1.64 B
1.44(3) 1.49 RPTOOS SLO A
1.53 1.66 1 This table is valid for all Cycle 11 fuel types.
2 When Tau does not equal 0 or 1, detennine OLMCPR via linear interpolation.
3 OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure (Reference 2)
Page 7 of14
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 5 TABLE 4-2 Power Dependent MCPR Limit Adjustments And Multipliers (References 2, 3 and 9)
Core Core Thermal Power (% of Rated)
EOOS Flow 0
25
<30
>30 45 60 100 Combination (0/0 of Operating Limit MCPR rated)
MCPR(P)
Multiolier. Ko Base
<60 2.66 2.66 2.44 1.481 1.280 1.150 1.000
>60 3.39 3.39 2.93 Base SLO
<60 2.68 2.68 2.46 1.481 1.280 1.150 1.000
>60 3.41 3.41 2.95 RPTOOS
<60 2.66 2.66 2.44 1.481 1.280 1.150 1.000
>60 3.39 3.39 2.93 RPTOOS
<60 2.68 2.68 2.46 1.481 1.280 1.150 1.000 SLO
>60 3.41 3.41 2.95 TBVOOS
<60 3.07 3.07 2.63 1.481 1.280 1.150 1.000
>60 4.54 4.54 3.77 TBVOOS
<60 3.09 3.09 2.65 1.481 1.280 1.150 1.000 SLO
>60 4.56 4.56 3.79 TABLE 4-3 Flow Dependent MCPR Limits MCPR(F)
(Reference 2)
Flow MCPR(F)
(0/0 rated)
Limit 30.0 1.53 79.0 1.25 110.0 1.25 Page 8 of14
Exelon Nuclear Fuels 5.0 Linear Heat Generation Rate Limits 5.1 Technical Specification Section 3.2.4 5.2 Description Doc ID: COLR Limerick 2, Rev. 5 The LHGR is an exposure dependent value. Due to the proprietary nature ofthese values only the maximum U02 LHGR for each fuel type is listed in Table 5-1. For single loop operation, a reduction factor is used which is shown in Table 5-2 (Reference 2).
ARTS provides for power-and flow-dependent thermal limit multipliers, which allow for a more reliable administration ofthe LHGR thermal limits. There are two sets of flow-dependent LGHR multipliers for dual-loop and single-loop operation (References 2 and 5). In addition, there are four sets ofpower-dependent LHGR multipliers for use with the TBVIS, TBVOOS, RPTIS and RPTOOS conditions (References 2,3 and 9). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. The LHGR multipliers are shown in Tables 5-3 through 5-4.
Thermal limit monitoring must be performed with the more limiting LHGR limit resulting from the power-and flow-biased calculation. The LHGRFAC(P) values are independent of recirculation pump trip operability (Reference 3).
TABLE 5-1 Linear Heat Generation Rate Limits (Reference 8)
FUEL TYPE GE14 MAXIMUM VALUE 13.4 kW/ft TABLE 5-2 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 2)
SLO Reduction Factor' I 0.80 1 Applied through Table 5-4 Page 9 of14
Exelon Nuclear Fuels Doc ID: COLR Limerick 2, Rev. 5 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(p)
(References 2, 3 and 9)
Core Core Thermal Power (0/0 of rated)
EOOS Flow Combination
(%
of 0
25
<30
>30 100 rated)
LHGRFAC(P) Multiplier Base
<60 0.485 0.485 0.490 0.634 1.000
>60 0.434 0.434 0.473 Base SLO
<60 0.485 0.485 0.490 0.634 1.000
>60 0.434 0.434 0.473 RPTOOS
<60 0.485 0.485 0.490 0.634 1.000
>60 0.434 0.434 0.473 RPTOOSSLO
<60 0.485 0.485 0.490 0.634 1.000
>60 0.434 0.434 0.473 TBVOOS
<60 0.463 0.463 0.490 0.634 1.000
>60 0.352 0.352 0.386 TBVOOSSLO
<60 0.463 0.463 0.490 0.634 1.000
>60 0.352 0.352 0.386 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)
(References 2, 3 and 5)
Core Flow (% of rated)
EOOS Combination o
70 80 110 1.00 0.80 1.00 0.80 0.80 0.9732 LHGRFAC(F) Multiplier 0.5055 0.5055 Dual Loop Single Loop Page 10 of14
Exelon Nuclear Fuels 6.0 Control Rod Block Setpoints 6.1 Technical Specification Section 3.3.6 6.2 Description Doc ID: COLR Limerick 2, Rev. 5 Technical Specification 3.3.6 states control rod block instrumentation channels shall be OPERABLE with their trip setpoints consistent with the values shown in the Trip Setpoint column ofTechnical Specification Table 3.3.6-2. The Reactor Coolant System Recirculation Flow Upscale Trip is a cycle-specific value and as such is found in Table 6-2 of this COLR. Table 6-2 lists the Nominal Trip Setpoint and Allowable Value.
These setpoints are set high enough to allow full utilization of the enhanced rCF domain up to 110% of rated core flow. Additionally, the ARTS Rod Block Monitor provides for power-dependent RBM trips. The trip setpoints/allowable values and applicable RBM signal filter time constant data are shown in Table 6-1. These values are for use with Technical Specification 3.3.6.
TABLE 6-1 Rod Block Monitor Setpoints1 (References 2 and 7)
Nominal Trip Setpoint Allowable Value LTSP 121.5%
121.5%
ITSP 116.5%
116.5%
HTSP 111.0%
111.7%
DTSP 5.0%
2.0%
TABLE 6-2 Reactor Coolant System Recirculation Flow Upscale Trip (Reference 7)
Nominal Trip Setpoint Allowable Value 113.4%
115.6%
I These setpoints (with Rod Block Monitor filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit of 1.30, which is less than or equal to the minimum cycle OLMCPR (see COLR References 2 and 7).
Page 11 of14
Exelon Nuclear Fuels 7.0 Turbine Bypass Valve Parameters 7.1 Technical Specification Section 3.7.8 and 4.7.8.C 7.2 Description Doc ID: COLR Limerick 2, Rev. 5 The operability requirements for the steam bypass system for use in Technical Specifications 3.7.8 and 4.7.8.C are found in Tables 7-1 and 7-2. If these requirements cannot be met, the MCPR, MCPR(P) and LHGRFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service, must be used.
TABLE 7-1 Turbine Bypass System Response Time (Reference 4)
Maximum delay time before start ofbypass valve opening following generation ofthe turbine bypass valve flow signal 0.11 sec Maximum time after generation ofa turbine bypass valve flow signal for bypass valve position to reach 80% offull flow 0.31 sec (includes the above delay time)
TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (Reference 4)
Reactor Power P 2:: 25%
No. ofValves in Service 7
Page 12 of14
Exelon Nuclear Fuels 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1.2.F 8.2 Description Doc ID: COLR Limerick 2, Rev. 5 The Limerick 2 Cycle 11 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technical Specification 2.2.1 are found in Table 8-1. These values are based on the cycle specific analysis documented in Reference 2. The setpoints provided in Table 8-1 are bounding for all modes ofoperation shown in Table 9-1.
TABLE 8-1 OPRM PBDA Trip Setpoints1 (Reference 2)
PBDA Trip Amplitude
~ 1.14 9.0 Modes Of Operation Corresponding Maximum Confirmation Count Trin Settinl!
~ 16 TABLE 9-1 Modes OfOperation (References 2, 3 and 5)
EOOS Ontions Oneratint! Ret!ion2 Base Ontion A or B Yes Base SLO. Ootion A or B Yes TBVOOS Ontion A or B Yes TBVOOS SLO Ontion A or B Yes RPTOOS Ontion A or B Yes RPTOOS SLO. Ootion A or B Yes TBVOOS and RPTOOS. Ootion A or B No TBVOOS and RPTOOS SLO Ontion A or B No 1 The station has conservatively decided to maintain the PDBA Trip Amplitude at 1.12 with a Corresponding Maximum Count Trip Setting of 14 until such time where these changes do not introduce a Unit difference at Limerick. This decision was agreed upon by Operations and Site Engineering.
2 Operating Region refers to operation on the Power to Flow map with or without FFWTR.
Page 13 of14
Exelon Nuclear Fuels 10.0 Methodology Doc ID: COLR Limerick 2, Rev. 5 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:
1.
"General Electric Standard Application for Reactor Fuel", GNF Document, NEDE-24011-P-A-16, October 2007 and u.S. Supplement NEDE-24011-P-A-16-US, Revision 16, October 2007.
2.
"Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications",
GENE Document, NEDO-32465-A, Rev. 0, August 1996.
11.0 References I.
"Technical Specifications and Bases for Limerick Generating Station Unit 2", Docket No. 50-353, License No. NPF-85, ExelonDocument.
2.
"Supplemental Reload Licensing Report for Limerick Generating Station Unit 2 Reload 10 Cycle II",
Global Nuclear Fuel Document No. 0000-0087-4784-SRLR, Revision 0, February 2009.
3.
"GEI4 Fuel Design Cycle-Independent Analyses for Limerick Generating Station Units I and 2", GENE Document, GE-NE-LI2-00884-00-0IP Revision 0, March 2001.
4.
"OPL-3 Parameters for Limerick 2 Cycle II", TOD!: ES0800031 Rev. 0, November 2008, Exelon Document.
5.
"ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station", GENE DocumentNEDC-32847P, June 1998.
6.
"General Electric Standard Application for Reactor Fuel", GNF Document, NEDE-24011-P-A-16, October 2007 and U.S. Supplement NEDE-24011-P-A-16-US, Revision 16, October 2007.
7.
"Power Range Neutron Monitoring System Setpoint Calculations Limerick Generating Station, Units I & 2 Mod. No. P00224", LE-OI07, Rev. 0 (including minor revision OOC), April 2008, Exe10n Document.
8.
"Fuel Bundle Information Report for Limerick Generating Station Unit 2 Reload 10 Cycle 11", Global Nuclear Fuel Document No. 0000-0087-4784-FBIR, Revision 0, February 2009.
9.
"Limerick Units I and 2 Off-Rated Analysis Below PLU Power Level With Credit for Backup Trip",
GENE Document, GE-NE-0000-0053-9467-RI, August 2006.
Page 14 of14