ML060800362
| ML060800362 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/20/2006 |
| From: | David Helker Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML060800362 (16) | |
Text
Exelon Nuclear www exeloncorp corn Nuclear 2 0 0 Exelon Way Kennett Square, PA 19348 TS 6.9.1.12 March 20,2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Limerick Generating Station, Unit 1 Facility Operating License No. NPF-39 NRC: Dwket No. Fj9-352
Subject:
Issuance of the Core Operating Limits Report For Reload 1 1, Cycle 12, Revision 5
Dear Sir/Madam:
Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 1, Reload 1 1, Cycle 12, Revision 5. Revision 5 of this report incorporates the revised cycle specific parameters resulting from the new core configuration implemented during the LGS, Unit 1 (1 Rll) refueling outage.
This COLR is being submitted to the NRC in accordance with LGS, Unit 1 Technical Specifications (TS) Section 6.9.1.12.
If you have any questions, please do not hesitate to contact us.
Very truly yours, David P. Helker Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC Enclosure cc:
S. J. Collins, Regional Administrator, Region I, USNRC S. Hansell, USNRC Senior Resident Inspector, LGS T. Valentine, Project Manager [LGS], USNRC
Exekon Nuclear Fuels Doe ID: COLR Limerick 1, Rev. 5 CORE OPERATING LIMITS REPORT FOR LfhiPlERIGK GENERATING STATION LWIT 1 RELOAD 11 CYCLE 12 (This is a compkte rewrite)
Approved By:
Date: _3//3/og, Page 1
Exelon Nuclear Fuels 1.o 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9D 10.0 11.0 Terms and Definitions General lnformrrlion MAPLHGR Limits MCPR Limits Linear Heat Generation Rate Limits Control Rod Block Setpoints Turbine Bypass VaIve Parameters Stability Protection Setpoints Modes of Operation Methodology References Page 2 Doc ID: COLH Limerick I, Rev. 5 Page 4
5 6
7 9
12 13 14 14 14 15
Exelan Nuclear Fuels Doc ID: COLR Limerick 1. Rev.
Table 3-1 MAPLHGR Versus Averag Planar Exposure All Fuef Types Table 3-2 MAPLUGR Single Loop Operation (SLO) Reduction Factor Tabfe 4-I Operating Limit Minimum Criticat Power Ratio (0LAMCPR)
Table 4-2 Power Dependent MCPR Limit Adjustments and Multipliers Table 4-3 Flow Dependent MCPR Limits MCPR(F)
Table 5-1 Linear Heat Generation Rate Limits - U02 Table 5-2 Linear Heat Generation Rate Limits -Gad Rods AII Fuel Types except GE!4-P10CNAB403-16GZ-lOOT-1SO-T6-39S6 Table 5-3 Linear Heat Generation Rate Limits - Gad Rods For Fuel Type GEI 4-P I OCNAB403-I6GZ-1 0OT-1 50-T6-395G Table 5-4 LI-IGR Single Loop Operation @LO) Reduction Factor Table 5-S Table 5-6 Table 6-1 Table 6-2 Power Dependent LHGR Multiplier LHGRFACP)
Flow Dependent LHGR Multiplier LHGRFACCF)
Rod Block Monitor Setpoints Reactor Coolant System Recirculation Flow Upscale Trip Table 7-1 Turbine Bypass System Response Time Table 7-2 Table 8-1 Table 9-I Minimum Required Bypass Valves To Maintain System Operability OPRM PBDA Trip Setpoints Modes of Operation Page Page 3
Exelon Nuclear Fuels Doc II): CQLR Limerick 1, Rev. 5 1.0 Terms and Definitions ARTS APRM and RBM Technical Specification Analysis EASE CASE A case analyzed with Turbine Bypass System in service and Recirculation Pump Trip in service and Feedwater Temperature Reduction allowed (FFWTR includes feedwater heater 00s or final feedwater temperature reduction) at any p i n t in the cycte operation in Dual Loop mode.
DTSP EOOS EOR F'FWTR FWHOUS HTSP ICF ITSP LHGR LHCRFAC(F)
?vlCPRt F)
MCPR(P1 MELLLA OLMCPR RPTOOS Rod Block Monitor Downscale Trip Setpoitit Equipment Out of Service End of Rated, The cycle exposure at which reactor power is equal to 3458 MWth with recirculation system flow equal to 100% all control rods fully withdrawn, afl feedwater heating in service and equilibrium Xenon.
Final Feedwater Temperature Reduction Feedwater Heaters Out of Service Rod Bfock Monitor Nigh Trip Setpoint increased Core Flow Rod Block Monitor Intermediate Trip Setpoint Linear Heat Generation Rate ARTS LNGR thermal limit flow dependent adjustments and multipliers ARTS LHGR thermaf limit power dependent adjustments and muitipliers Rod Block Monitor Low Trip Setpoint Maximum Average Pfannr Linear Heat Generation Rate Minimum Critical Power Ratia ARTS MCPR thermal limit flow dependent adjustments and multipliers ARTS MXCPR themiat lin& power dependent adjustments and multtplitrs Maximum Extended Load Line Limit Analysis Opersting Limit Minimum Criticaf Power Ratio Recirculation Pump Trip Out of Service Page 4
Exelon Nuclear Fueis Doc ID: COLR Limerick 1, Rev. 5 SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TBVOOS Turbine Bypass Valves Out of Service 2.0 General Information This report is prepared in accordance with Technical Specification 6.9.1.9 of Reference 1. Power and flow dependent limits are Iisted for various power and flow levels. Linear interpolation is to be used to find intermediate values.
The data presented in this repon is valid for ail licensed operating domains on the operating map, including:
0 0
Maximum Extended Load Line Limit down to 815% of rated core flow during full power operat ion Increased Care Flow (ICF) up to 1 10% of rated care flow Final Feedwater Temperature Reduction (FEWTR) up to 10S°F during cycle extension operation Feedwater Heater Out of Service (FWHOOS) ttp to 60°F feedwater temperature reduction at any time during the cycle prior to cycle extension.
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Exeion Nudear Fuels Doc 11): COLR Limerick 1, Rev. 5 3.0 MAPLHGR Limits 3.1 Technical Specification Section 3.2.1 3.2 Description The MAPLWGR value of each fuel type as a function of average planar exposure is given in Table 3-1. The limiting MMLHGR value is the same for all fuel types in Limerick Unit 1 Cycle
- 12. For single loop operation, a reduction factor is used which is shown in Table 3-2, Table 3-1 MAPLHGR Versus Average Planar Exposure All Fuel Types (Reference 2 and 12)
Average Planar Expsure MAPLHGR Limit Table 3-2 W L H G R Single Loop Operation (SLO) Reduction Factor (Referenee 2 and 12)
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Exeion Xuclear Fuels Doc ID: COLR Limerick 1, Rev. 5 4.0 MCPR Limits 4.1 Technical Specification Section 3.2.3 4.2 Description Table 4-1 is derived from the Reference 2 analyses and is valid for alI Cycle 12 fuel types and operating domains. Table 4-1 includes treatment of these MCPR limits for all conditions listed in Section 9.0, Mode of Operations. The cycle exposure that represents EOR is given in the latest verified and approved Cycle Management Reprt or an associated Engineering Change Request, ARTS provides for power-and flow-dependent thermal limit adjustments and muttipkts, which altow for a more reliable administration of the MCPR thermal limit. The flow-dependent adjustment MCPR(F) md power-dependent adjustment MCPR(P) are sufficiently generic to apply to all fuel types and operating domains. The MGPR(P) curves are independent of rwirctilation pump trip operability (Rekrence 8 and I I).
MCPR(F) and MCPRIP) are independent of Scram Time Option. These adjustments are provided in Tabfe 4-2 and 4-3. The OLMCPR is determined for a given power and flow condition by evaluating the power-dependent MCPR and the flaw-dependent MCPR and selecting the greater of the two.
When the actual Scram speed falls between Option B (Tau = 0) and Option A (Tau = I), linear interpolation shall be used to determine h4CPR limits.
Tabfe 4-1 Operating Limit blinimum CritieaI Power Ratio (OLMCPR)
All Fuel Types (Reference 2)
ULMCPR Iirnit set by the OPRM PBDA setpoints (Reference 2 and CULR Section 8.0).
OLMCPR limit set by the Single Loop Operation Recircuiation Pump Seimre AnalyG.; (Reference 21.
i '
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Exelon Nuelear Fuets Doc Ilk COLR Limerick 1, Rev. 5 TABLE 4-2 Power Dependent,MCPR Limit Adjustments And Multipliers (References 2,5,8, and 11 1 I core i Core Thermal Power (91c of Rated) i 6 0 1 3.07 I 3.07 2.63
>60 4.54 1 4.54 3.77 TBVOOS 1.563 rBVOOS SLO
- er=sclr, 1.347 1.347 -
1.347
~
1.347 Limit MCPR Multiplier, Rp TABLE 3-3 Flow Dependent MCPR Limits MCPR(F)
(References 2,3 and 5) 1.ooo -
1,000 t==c=
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Exehon Nuclear Fuels Doc I D COLR Limerick I, Rev. 5 5.0 Linear Heat Generation Rate Limits 5.1 Technical Specification Section 3.2.4 5.2 Description The LHGR is an exposure dependent value, Table S-1 provides the exposure dependent LHGR limit for all U02 pins for all bundles in the Cycle 12 core. Tables 5-2 and 5-3 provide the exposure dependent LHGR limit for Gad pins in the Cycle 12 core based upon fuel type. The SLO MAPLHGR multiplier is shown in Table 54.
ARTS provides for power-and flow-dependent thermal limit multipliers, which allow for a more reiiabte administration of the LWER thermal Iimits, There are two sets of flow-dependent LGHR mulripliers for dual-Ioop and single-loop operation (References 2. 3, and 5).
In addition, there are also two sets of power-dependent LHGR multipliers for use with the Turbine Bypass Valves in service and TBVUOS conditions (Reference 8 and 11). Section 7.0 contains the conditions for Turbine Bypass Valve Operability. Thermal limit monitoring must be performed with the more limiting LWGR limit resulting from the power-and flow-biased calculation. The LHGRFAC(P) curves are independent of recirculation pump trip operability (Reference 8 and 11).
TABLE 5-1 Linear Heat Generation Rate Limib - U02 All Fuel Types (Reference 9 and 10)
TABLE 5-2 Linear Heat Generation Rate Limits: - Gad Rods 411 Fuel Types except GELQP10CNAB~~3-16GZ-100T-I5O-T6-3956 (Reference 10)
LHGR Limit Page 9 I
Exelon Nuclear Fuels Doc I D COLR Limerick 1, Rev. 5 TABLE 5-3 Linear Heat Generation Rate Limits - Gad Rods Fur Fuel Type GF,L4-P10CNAB403-~6GZ-lOOT-150-T6-395fi (Reference 9)
TABLE 5-4 LHGR Single Loop Operation (SLO) Reduction Factor (Reference 2)
SLO Reduction Factor' 0.80 TABLE 5-5 Power Dependent LHGR Multiplier LHCRFAC(P}
(References 2,s and 8)
I LHGRFACfP) Multiplier TBVUOS SLO Page 10
Exelon Kuclear Fuels Doc ID: COLR Limerick 1, Rev. 5 TABLE 5-6 How Dependent LHGR Multiplier LHCRFACCF)
(References 2,3 and 5)
EOQS Combination Page 11
Exelon Nuclear FueIs 6.0 Control Rod Block Setpoints Dm u): COLR Limerick 1, Rev. 5 6.1 Technical Specification Section 3.3.6 6.2 Description Technical Specification Limiting Condition for Operation number 3.3.6 requires controt rod block instrumentation chnmels shall be OPERABLE with their trip setpoinfs consistent with the values shown in the Trip Setpoint column of Technical Specification Table 3.3.6-2. The Reactor Coolant System Recirculation Flow Upscale Trip is a cycle-specific vafue 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 ailow fuff utilization of the enhanced ICF domain up to 110% of rated core flow. Additionally, the ARTS Rod Block IVonitor provides for power-dependent RBM trips. The trip setpaintsfallowabbte values and applicabte RBM signal filter time constant data are chown in Table 6-1.
TABLE 6-1 Rod Block Monitor Setpoints' (References 2 and 7)
TABLE 6-2 Reactor Coolant Sysfem Recirculation Flow Upscale Trip (Reference 7)
Nominal Trip Setpoint Based on a cycle-specific rated RWE MCPR h i t less than or equal to the minimum cyccie OLMCPR. The values I
provided asmne the Rod Btmk Monitor filter time constant heween 0.
I secmids and 0.153 secilrtds is used.
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Exelon Nuclear Fuels Doc ID: COLR Limerick 1, Rev. 5 7.0 Turbine Bypass Valve Parameters 7.1 Technical Specification Section 3.7.8 and 4.7.g.C 7.2 Description The operability requirements for the steam bypass system are found in Tables 7-1 and 7-2 (Reference 4 and 8).
If these requirements cannot be met, the MCPR. MCPR(P) and LHGRFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Our Of Senice (TSVOOS). must be used.
TABLE 7-1 Turbine Bypass System Response Time (Reference 4)
TABLE 7-2 Minimum Required Bypass Valves To LMaintaain System Operability (Reference 8)
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Exeion Nuclear Fuels Doc ID: GOLR Limerick 1, Rev, 5 8.0 Stability Protection Setpoints 8.1 Technical Specification Section 2.2.1.2.F 8.2 Description The Limerick 1 Cycle 12 OPRM Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System are found in Tabte 8-1. These values are based on the cycle specific analysis documented in Reference 2. The Cycle I2 OPRM PBDA trip setpoints specified in Table 8-1 require a minimum OLPVICPR wlue of I.33 (See Section 4.0 MCPR Limits). The setpoints provided in Table 8-1 are bounding for a11 modes of operation shown in Table 3-1.
TABLE 8=1 OPRM PBDA Trip Setpoints (Reference 2) 9.0 Modes Of Operation TABLE 9-1 Modes of Operatiun
{Reference 2,3 and 5)
The anatyrical methods used to determine the cure operating limits shall be those previously reviewed and approved bq the NRC, specifically those described in the follou ing doctimena:
- 1. General Electric Standard Appiication or Reactor Fuel, NEDE-240f 1-P-A-f S, September 2005 and US. Supplement ItEDE-24OI I -P-A-1 S-US, September 2005, Operaiing Region refers KO operztion on the Power to Flozt-map w irh uf without EFltTR.
1 Page 14
Exelon Nuclear Fuels Doc if): COLR Limerick 1, Rev. 5 11.0 References I. Technical Specifications and Bases for Limerick Generating Station Unit 1, Docket No. 50-352, L i c e n ~ NO.
- 2. Supplemental Retoad Licensing Report for Limerick Generating Station Unit 1 Reload 1 t Cycle 12, Global NucIear Fuel Document No. oooO-#42-245 I-SRLR, Revision 0, February 2006.
3, GE14 Fuel Design Cycle-Independent Anatyses for Limerick Generating Station Unirs 1 and 2, GE-NE-L12-00884-00-0IP, March 2001.
- 4. OPL-3 Transient Protection Parameters Verification for Reload Licensiog Analyses for Limerick I Reload 1 I Cycle i 2, GAT Document Web Center
- 5. ARTS Flow-Dependent Limits with TEVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station, GESE Document NEDC-32847P, June 1998.
- 6. Genera1 Electric Standard Application for Reactor Fuel, NEDE-2301 1 -P-A-t S, September 2005 and U.S. Supptement NEDE-2401 I-P-A-I5-US, September 2005.
7. Power Range Neutron Monitoring System Setpoint Calculations Limerick Generating Station, Units 1 &
2 Mod. No. POO224, LE-0107, Rev. 0, March 2000.
- 8. Limerick I and 2 Off-Rated Annfyses Below the Ptt: Power Level. GE Nuclear Document No. GE-NE-0000-0037-3253-R0, March 2005.
- 9. Fuel Bundle Information Report for Limerick Generating Station Unit 2 Reload 8 CycIe Y., Global Nuclear Fuel Documefit No. oo00-003 1 -770S-FBTR. January 2005.
- 40. Fuei Bundle Information Report for Limerick Generating Station Unit I Reload I I Cycle IT, Global Nuclear Fuel Document No. ooaO-~3-245 I -iLIAPL, Febniary 2006.
1 1. Application of rhr Limerick Unit I and 2 Power Dependent Limits for a 55% PLU Pouer Level, MJM-EXN-HH1-0.5-i 15, December 2005
- 12. Supplemental Retoad Licensing Report for Limerick Generating Station Knit 2 Reload 8 Cycle Y.
Global Nuclear Fuel Document No. oo00-003 i-7705-SRLR, Revision 0, January 2005.
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