ML040840501
| ML040840501 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/15/2004 |
| From: | Gallagher M Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML040840501 (27) | |
Text
Exel e nsM Exelon Nuclear 200 Exelon Way www.exeloncorp.com Nuclear Kennett Square, PA 19348 TS 6.9.1.12 March 15, 2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555 Limerick Generating Station, Unit 1 Facility Operating License No. NPF-39 NRC Docket No. 50-352
Subject:
Issuance of the Core Operating Limits Report for Reload 10, Cycle 11, Revision 0
Dear Sir/Madam:
Enclosed is a copy of the Core Operating Limits Report (COLR) for Limerick Generating Station, Unit 1, Reload 10, Cycle 11, Revision 0. Revision 0 of this report incorporates the revised cycle specific parameters resulting from the new core configuration implemented during the LGS, Unit 1 (1R10) 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, 0z -F-04 11-4 Michael P. Gallagher Director, Licensing and Regulatory Affairs Enclosure cc: H. J. Miller, Administrator, Region I, USNRC A. L. Burritt, USNRC Senior Resident Inspector, LGS S. Wall, Senior Project Manager, USNRC vc)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-Li RIO LR10 Core Operating Limits Report Page 1, Rev. 0 CORE OPERATING UMITS REPORT FOR UMERICK GENERATING STATION UNIT I RELOAD 10, CYCLE 11 Prepared By:_ Date: cQ// L!
M. P. Hynes Engineer Reviewed By:
4 G. W. Beckneil Independent Reviewer
.Date:4&k Approved Date: o9b-o-e 4-
-. Manager Nuclear BWR Design
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI RIO LI RIO Core Operating Umits Report Page 2, Rev. 0 LIST OF FFFFCTIVF PAr:FS Page(s) Revision 1-26 0o
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LIRIO Li RI0 Core Operating Limits Report Page 3, Rev. 0 INTRODUCTION AND SUIMMARY This report provides the following cycle-specific parameter limits for Limerick Generating Station Unit I Cycle 11:
- Maximum Average Planar Unear Heat Generation Rate (MAPLHGR)
- Minimum Critical Power Ratio (MCPR)
- Rod Block Monitor (RBM) setpoints
- Linear Heat Generation Rate (LHGR)
- Turbine Bypass Valve parameters
- Reactor Coolant System Recirculation Flow Upscale Trips These values have been determined using NRC-approved methodology, Reference 9, and are established such that all applicable limits of the 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 Fuel Management Procedure NF-AB-120.
The data presented in this report is valid for all points and domains on the operating map, including:
- Maximum Extended Load Line Limit (MELLL) down to 81% of rated core flow during full power operation
- Increased Core Flow (ICF) up to 110% of rated core flow
. Feedwater Heater Out of Service (FWHOOS) up to 600F feedwater temperature reduction at any time during the cycle prior to cycle extension.
Further information on the cycle specific analyses for Limerick I Cycle 11 and their associated operating domains is available in Reference 2.
MAPLHGR I IMITS The limiting MAPLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of average planar exposure is given in Figures 1 through 7. These figures are used when hand calculations are required as specified in Technical Specification 3.2.1. The MAPLHGR limit curves of Figures 1 through 7 were generated from References 3 and 4.
For single loop operation, a reduction factor is used which is shown in Table 3 (Reference 2).
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LIRIO Li RI0 Core Operating Limits Report Page 4, Rev. 0 MCER LIMITS The MCPR value for use in Technical Specification 3.2.3 for each fuel type is given in Table 1. This table is derived from the Reference 2 analyses and is valid for all Cycle 11 fuel types and operating domains. Information regarding the treatment of these MCPR limits for SLO is also provided.
Bounding MCPR values are also provided for inoperable Recirculation Pump Trip (RPTOOS) or inoperable Steam Bypass System (TBVOOS). These two options represent the Equipment Out of Service (Equipment OOS) conditions.
Note that in Table 1 the term "EOR" refers to the cycle exposure at which operation at "rated conditions" is no longer possible (i.e., the cycle exposure at which cycle extension begins). The cycle exposure which represents "EOR" is given in the latest verified and approved Cycle Management Report. This value can change during the cycle due to changes in operating strategy.
ARTS T4FRMAL LIMIT ADMINISTRATION ARTS provides for power- and flow-dependent thermal limit adjustments and multipliers which allow for a more reliable administration of the MCPR and MAPLHGR thermal limits. The flow-dependent adjustment MCPR(F) is sufficiently generic to apply to all fuel types and operating domains (References 2 and 8). However, there are two sets of flow-dependent MAPFAC(F) multipliers for dual-loop and single-loop operation, References 2, 5 and 8. In addition, there are also two sets of power-dependent MAPLHGR multipliers for use with Equipment in Service and with Equipment OOS conditions, Reference 5. Finally, there are two sets of power-dependent MCPR adjustments and multipliers for use with Equipment in Service and with Equipment OOS conditions, References 2 and 5.
These adjustments and multipliers are shown in Figures 8 through 14. Thermal limit monitoring must be performed with the more limiting MCPR and MAPLHGR limits resulting from the power-and flow-biased calculation.
ROD RLOCK MONITOR St*TPOINTS The ARTS RBM provides for power-dependent RBM trips. The trip setpointslallowable values and applicable RBM signal filter time constant data are shown in Table 2. These values are for use with Technical Specification 3.3.6. The use of the setpoints specified in Table 2 is documented in References 2 and 10.
LINFAR HEAT GENERATION RATES The maximum LHGR value for each fuel type for use in Technical Specification 3.2.4 is given in Table 4. The LHGR is an exposure dependent value. Due to the proprietary nature of these values only the maximum LHGR for each fuel type is listed in Table 4. The LHGR data is listed in Reference 11 (GNF proprietary).
EXELON Nuclear, Nuclear Fuels EXELON-COLR-1-R10 LI RI0 Core Operating Limits Report Page 5, Rev. 0 STEAM RYPASS SYSTEM OPERAUILIW The operability requirements for the steam bypass system for use in Technical Specifications 3.7.8 and 4.7.8.C are found in Table 5 (Reference 6). If these requirements cannot be met, the MCPR, MCPR(P) and MAPFAC(P) limits for inoperable Steam Bypass System, known as Turbine Bypass Valve Out Of Service (TBVOOS), must be used.
RFCIRCMILATION PUMP TRIP OPERARIT If the recirculation pump trip is inoperable, then the MCPR linifts for Recirculation Pump Trip Out Of Service (RPTOOS) must be used. The MCPR(P) and MAPFAC(P) curves are independent of recirculation pump trip operability (Reference 5).
CONTROL ROD BLOCK INSTRUMENTATION RFACTOR COOLANT SYSTEM RECIRCI ATIION FLOW I1PSCALE TRIP Technical Specification Limiting Condition for Operation number 3.3.6 requires control rod block instrumentation channels shall be OPERABLE with their trip setpoints 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 value and as such is found InTable 6 of this COLR. Table 6 lists the Nominal Trip Setpoint and Allowable Value. These setpoints are set high enough to allow full utilization of the enhanced ICF domain up to 110% of rated core flow.
Reference 10 provides the current basis for the trip setpoint values used.
SAFETY I IMIT MINIMUM CRITICAL POWFR RATIO (SLMCPR)
The Safety Umit Minimum Critical Power Ration (SLMCPR) for Limerick 1 Cycle 11 is 1.07 for Dual Loop Operation and 1.08 for Single Loop Operation. These values are documented in Reference 2.
RFFERFNUEB
- 1. "Technical Specifications and Bases for Limerick Generating Station Unit 1", Docket No. 50-352, Ucense No. NPF-39.
- 2. Supplemental Reload Ucensing Report for Umerick Generating Station Unit I Reload 10 Cycle 11", Global Nuclear Fuel Document No. 0000-0018-2410-SRLR, Revision 0, January 2004.
- 3. tlattice Dependent MAPLHGR Report for Umerick Generating Station Unit I Reload 10 Cycle 11", Global Nuclear Fuel Document No. 0000-0018-2410-MAPLHGR, Revision 0, February 2004.
- 4. "Lattice Dependent MAPLHGR Report for Urmerick Generating Station Unit 1 Reload 9 Cycle 10", Global Nuclear Fuel Document No. J11 -03984MAPL, Revision 0,January 2002.
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LIRIO LI RI0 Core Operating Limits Report Page 6, Rev. 0
- 5. uGE14 Fuel Design Cycle-Independent Analyses for Limerick Generating Station Units 1 and 2" GE-NE-L12-00884-00-41P, March 2001.
- 6. "OPL-3 Transient Protection Parameters Verification for Reload Licensing Analyses for Limerick I Reload 10 Cycle 11", Resolved as documented in DRF 20111 (L1C11 Reload Licensing DRF).
- 7. "Limerick Generating Station Units I and 2 ECCS-LOCA Evaluation for GEI4', GE Nuclear Energy Document No. GE-NE-JI 1-03793-09-01 P, February 2001.
- 8. "ARTS Flow-Dependent Limits with TBVOOS for Peach Bottom Atomic Power Station and Limerick Generating Station", GENE Document NEDC-32847P, June 1998.
- 9. 'General Electric Standard Application for Reactor Fuel', NEDE-24011-P-A-14, June 2000 and U.S. Supplement NEDE-24011-P-A-14-US, June 2000.
- 10. "Power Range Neutron Monitoring System Setpoint Calculations Limerick Generating Station, Units 1 &2Mod. No. P00224%, LE-01 07, Rev. 0, March 2000 (GE Nuclear Energy).
- 11. 'Fuel Bundle Information Report for Limerick Generating Station Unit I Reload 10 Cycle 11',
Global Nuclear Fuel Document No. 0000-0018-2410-FBIR, January 2004.
EXELON Nuclear, Nuclear Fuels EXELON.COLR-LIRIO Li RI0 Core Operating Limits Report Page 7, Rev. 0 Figure 1 MAXIMUM AVERAGE PLANAR UNEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GE1 3-P9CTB417-13GZ-100T-146-T (GEt 3)
(Reference 4)
This Figure is Referred to by Technical Specification 3.2.1 13.S -------- .... .... .......... .. . - ................... ...
4' bd 1.* ..... . . . -- - - .......... . . ............ ... .. ............... . . . .. , . . ... .. . ............ 8 0.0 14.0 20 0 S. 45 6 .@
Average Planar Ixposure (Gird/ST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd/sT) 4kW~ (f:WdmS 0.0 10.46 7.0 11.53 25.0 12.01 0.2 10.54. 8.0 11.69 30.0 11.59 1.0 10.65 9.0 11.85 35.0 10.96 2.0 10.79 10.0 12.02 40.0 10.32 3.0 10.93 12.5 12.26 45.0 9.66 4.0 11.08 15.0 12.45 50.0 8.97 5.0 11.22 17.5 12.44 55.0 7.43 6.0 11.37 20.0 12.32 58.03 6.29
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L1R10 LIRI0 Core Operating Limits Report Page 8, Rev. 0 Figure 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GE1 3-P9CTB417-1 IGZ-100T-146-T (GE1 3)
(Reference 4)
This Figure is Referred to by Technical Specification 3.2.1 4.,
......... ... ...... ,. A............... ......................
Ii....
X .... .. I ......
.6.0.. . _ _ . . _ _ _ . ___ _ . _. . . _ __
0.0 20.0 30.. 4. . 5.0 0 £0.0 Average 1P2-ar Exposure (Gwd/BT)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR GWd l sWift ( s (GWdm ikW/ft) MWkf 0.0 10.79 7.0 11.75 25.0 12.00 0.2 10.85 8.0 11.91 30.0 11.60 1.0 10.93 9.0 12.06 35.0 10.96 2.0 11.05 10.0 12.21 40.0 10.33 3.0 11.17 12.5 12.43 45.0 9.67 4.0 11.31 15.0 12.55 50.0 8.98 5.0 11.45 17.5 12.47 55.0 7.49 6.0 11.59 20.0 12.32 58.2 6.29
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L1 R10 LR10 Core Operating Urmits Report Page 9, Rev. 0 Figure 3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GE4-P1 0CNAB417-7G8.0/8G7.0-1OOT-150-T-2527 (GE14C)
(Reference 4)
This Figure Is Referred to by Technical Specification 3.2.1 12..
..... ....... ......... . _ .5......
a1. I . . ....... ..... : .,. . ,............ .. - -- - .. ......... .. ........
- 1 P.,
4.4 A
7 .4
.. 4
.0 Avg Plan Avg. Plan Avg. Plan Exp iosure MAPLHGR Exposure MAPLHGR Exposure ?MPLHGI 4LIkWtft) (GM~dtI (kW&~) (G3WI&I) ikwift)
I ) 10.00 7.0 10.81 25.0 10.34
)210.01 8.0 10.91 30.0 9.87 1.0 10.03 9.0 10.99 35.0 9.39
.I Z010.11 10.0 11.07 40.0 8.91
.010.22 12.0 11.17 45.0 8.40 1.0 10.34 15.0 11.04 50.0 7.87 i.0 10.49 17.0 10.95 55.0 5.89
.010.64 20.0 10.76 57.06 4.86
EXELON Nuclear, Nuclear Fuels EXELON-COIR-L R10 LIR10 Core Operating Limits Report Page 10, Rev. 0 Figure 4 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GEl4-PlOCNAB417-13GZ-10OT-150-T-2528 (GE14C)
(Reference 4)
This Figure Is Referred to by Technical Specification 3.2.1
,=. .... . ..... ....... ...... .... . ... .. . ........ ...... ..
. ...... ................ -- - ..- - - - - - - .4 .. , ........... ......... .... ..... . .....
.§ ............ .' -- ---- ........
- 7. 0 5, ,, .. e.., ,,,,,,,,,,,,,,, ........ ... ...... ............ ................... ............ ..... .......................... ,., .... ....
4 .0 4.0 e _ __ - ; -.--- T---- -- as--- i--- _ _ _ _ _ _
Average Planar exposure (GWd/ST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWdI (kW/t+/-) ( GWd E 4kWjf- (4GWd/ tkWf) 0.0 10.17 7.0 10.92 25.0 10.34 0.2 10.22 8.0 11.02 30.0 9.86 1.0 10.26 9.0 11.09 35.0 9.38 2.0 10.32 10.0 11.15 40.0 8.90 3.0 10.42 12.0 11.25 45.0 8.40 4.0 10.53 15.0 11.09 50.0 7.86 5.0 10.66 17.0 10.98 55.0 5.91 6.0 10.81 20.0 10.78 57.12 4.85
EXELON Nuclear, Nuclear Fuels EXELON.COLR-LI RIO LIRIO Core Operating Limits Report Page 11, Rev. 0 Figure 5 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GE14-PIOCNAB417-7G8.0/8G7.0-80U45R-150-T-2531 (GE14C)
(Reference 4)
This Figure is Referred to by Technical Specification 3.2.1 I...
11.0
, .,,,, .Z-e = .............................. '. , ........ .. , ' ..... ....... ....
/ .' '
.'\ ! ' -
0.0. : : : : :
43 ........
I. : : : : :
I ....... ...... .... ... ..
§ ... . ............
. { ......
. . A_........:
- : : : T\
- : : : :\
- : : : : \
- : : : : \
7.0 ........... ....... , j . l. .. .... ., A.....\
- : : - : \
- : : : : \
- : : : \
- : : ' ' \
- : : ' ' \
............. ................... , . ,. ........................................... ...................................................................... .... ..... ........ ............. .. ..... .. .... ..... . s.
- : : : : G
- : : : : \
- . : : : s 5.0 ..... ... ........ ... . . ..... ..... . ...................... ................................ .. .. .. . . . . .. . . . .... ... . . . . .. . . . ..
- 4. 0 :
- 0. 10.0 20.0 3 06.0 4 0. 0 5 0.0 0.0 Average Planar Exposure (Gwd/ST)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLHGR (GWd= (kWEif) 4LdR &kWift) (GWdZ1 (kW~f) 0.0 10.08 7.0 10.86 25.0 10.36 0.2 10.09 8.0 10.95 30.0 9.88 1.0 10.10 9.0 11.02 35.0 9.40 2.0 10.18 10.0 11.10 40.0 8.91 3.0 10.28 12.0 11.21 45.0 8.40 4.0 10.40 15.0 11.07 50.0 7.86 5.0 10.54 17.0 10.98 55.0 5.91 6.0 10.70 20.0 10.79 57.13 4.85
EXELON Nuclear, Nuclear Fuels EXELON-COL1R-LI11RIO LI RIO1 Core Operating Limits Report Page 12, Rev. 0 Figure 6 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GEl14-PIlOCNAB4I17-I15GZ-10OT-1I50-T-2592 (GEl14C)
(Reference 3)
This Figure Is Referred to by Technical Specification 3.2.1 12 . S I1I. 0 169.0a 4j .0a Ik A: 6. 0 7 .0 6 .a
- 5. 0 4.0a 0 .100 26. 0 36 6 4 0 .0 50.0 6.
average 1lanar exposure (Ova/IT)
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLH-GR Exposure MAPLHGR (G-Md= 4kWfft) (GW-df (kWif) (GWMI& 4kWjjft 0.0 10.00 8.0 10.91 20.0 10.76 0.2 10.01 9.0 10.99 25.0 10.34 1.0 10.03 10.0 11.07 30.0 9.87 2.0 .10.11 11.0 11.14 35.0 9.39 3.0 10.22 12.0 11.17 40.0 8.91 4.0 10.3.4 13.0 11.13 45.0 8.40 5.0 10.49 14.0 11.08 50.0 7.87 6.0 10.64 15.0 11.04 55.0 5.89 7.0 10.81 17.0 10.95 57.06 4.86
EXELON Nuclear, Nuclear Fuels EXELON-COLR4LIRIO LiRI0 Core Operating Limits Report Page 13, Rev. 0 Figure 7 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BUNDLE TYPE GE14-P1OCNAB414-14GZ-10OT-150-T-2701 (GE14C)
(Reference 3)
This Figure is Referred to by Technical Specification 3.2.1
§ 7., e .. ... , . , - -- -- --- -- -; - -- -- - .i
- 0.:'::0. :::::: :: 20': ':: 0 10:0 ::::.:'
Avg. Plan Avg. Plan Avg. Plan Exposure MAPLHGR Exposure MAPLHGR Exposure MAPLH1GR (GWdISI ikw=t (GWISI ikWMt 4GM~dESI) (kWIft) 0.0 10.03 8.0 10.99 20.0 10.76 0.2 10.08 9.0 11.12 25.0 10.30 1.0 10.16 10.0 11.2 30.0 9.79 2.0 10.24 11.0 11.25 35.0 9.24 3.0 10.35 12.0 11.28 40.0 8.72 4.0 10.47 13.0 11.21 45.0 8.24 5.0 10.61 14.0 11.14 50.0 7.76 6.0 10.73 15.0 11.08 55.0 5.86 7.0 10.86 17.0 10.96 57.02 4.85
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI RIO LI RIO Core Operating Limits Report Page 14, Rev. 0 FIGURE 8 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)
THIS FIGURE ISVALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DOMAINS (RPT IN SERVICE OR RPTOOS)
(Reference 5)
This Figure is Referred to by Technical Specification 3.2.1 1.0 4.
0.8 4 0.6343 M PLHGR(P) = MAPFAC(P)
- MAPLHGRstd 6# Fw 'MAPLHGRstd - Standard MAPLHGR Lnits For 25% > P: No Themal Limts Monltaong Required 0.485 ,_ 0.490 No Liits Specified 0.434 0.473 For25% c P < 30%: MAPFAC(P) a 0.490 + 0.0010(P - 30%4)
/: Forc 60% Core Flow MAPFAC(P) = 0.473 + 0.0078(P - 30%A)
> 60% Flow For > 60% Core Flow 0 .2 Fo30% c P: MAPFAC(P) = 1.04 0.005224{P - 100%)
e.0 a I0 20 o so so 7 80 0 1 0a Power (M Rated)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI R10 L1R1O Core Operating Limits Report Page 15, Rev. 0 FIGURE 9 POWER DEPENDENT MAPLHGR MULTIPLIER MAPFAC(P)
THIS FIGURE ISVALID FOR THE TBVOOS OPERATING DOMAIN (Reference 5)
This Figure Is Referred to by Technical Specification 3.2.1 1.0 i 0.e I 0.6343/
- MAPLHGR(P) - MAPFAC(P) MAPLHGRstd U .s
< 60% Flow MAPLHGRstd - Standard MAPLHGR Umits I . 0 .4
.463 .
0.490
.No For 25% > P: No Thennal Umits Monitoring Required Umits Specified 03 For 25% cP < 30%: MAPFAC(P) = 0.490 + 0.0054(P - 30%)
For < 60% Core Flw
> 60% Flow MAPFAC(P) = 0.386 + 0.0068(P - 30%)
For > 60% Core Flow 8.2 4.
For 30% c P: MAPFAC(P) - 1.0+ 0.005224(P - 100%)
e .e . P Ii I i F S 10 20 3e6 4 5e 6S 7e 0ee 0 2 a
-Poer (% Rated
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI R10 LI RIO Core Operating Limits Report Page 16, Rev. 0 FIGURE 10 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)
THIS FIGURE ISVALID FOR ALL OPERATING DOMAINS EXCLUDING SINGLE LOOP OPERATION (References 5 and 8)
This Figure is Referred to by Technical Specification 3.2.1 1.1
.0 _ _ _
0 .3 C
I MAPLHGFF) 11
= MAPFAC~F)
- MAPLHG1std
! 0.7 For Tvo LowOpeQa~ton, > 70% WT MAPFAC.F) = Th Mnirrmi of EMf-ER 1.0 O R{0.0268 x CWT -70Y10 + 0.9732) a .6 Fbr Tmo Loop Operaion < 70%/ WT MAPFAC(F) = {C0 6682 x (W7/100) + 0.5055) 0.5 . WT %Rated OeFlow 0.4 .-i 30 40 50 40 70 t0 O0 100 110 Core Flow (% Rated)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI RIO 1IRD10 Core Operating Limits Report Page 17, Rev. 0 FIGURE 11 FLOW DEPENDENT MAPLHGR MULTIPLIER MAPFAC(F)
THIS FIGURE IS VALID FOR SINGLE LOOP OPERATION (References 2 and 8)
This Figure is Referred to by Technical Specification 3.2.1 1.1 W...
a6 .7 6.6 MAPLHGR(F) = MAPFAC(F)
- MAPLHGRstd For Single Loop Operatio, MAPFAC(F) - ihe Minimwm of EflHER 0.79 OR {0.6682 x (WT 1100) + 0.5055 0.3 I
= % Rated Core Flow I .4 3 4.0 5s 90 7. to '0I 1I0 11a Core Flow (% Rated)
Note: The above multiplier is capped at the SLO Reduction factor provided in TabLe 3.
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI RIO LIR10 Core Operating Limits Report Page 18, Rev. 0 TABLE 1 OPERATING LIMIT MINIMUM CRICAL POWER RATiO (OLMCPR)
Use in conjunction with Figures 12, 13 and 14.
(References 2 and 5)
This table is valid for all Cycle 11 fuel types.
S This table is referred to by Technical Specification 3.2.3.
TBV In Service and TBV out of Service RPT Out of Service RPT In Service OPT. B OPT. A OPT. B OPT. A OPT. B OPT. A LOR 200ton t 1.33 1.36 1.38 1.41 1.40 1.51 2000
&W~d/ST TwopLoop EOR- 1.38 1.41 1.43 1.46 1.46 1.63 MWd/ST
_to EOC Single Loop BOC to 1.43a) 1.432) 1.432) 1.432) 1.43f 1.52 Operation EOR -
2000 MWd/ST Single Loop EOR - (2(.42.71.716 Operation 2000 1.43) 1.43 1.44 1.47 1.47 1.64 MWd/ST to EOC Notes:
- 1. When Tau does not equal 0 or 1, determine OLMCPR via linear interpolation.
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI R10 LI R10 Core Operating Limits Report Page 19, Rev. 0 FIGURE 12 POWER DEPENDENT MCPR LIMIT ADJIUSTMENTS AND MULTIPLIERS THIS FIGURE IS VALID FOR THE RCF, ICF, MELLL, FWHOOS AND FWTR OPERATING DOMAINS (RPT IN SERVICE OR RPTOOS)
(References 2 and 5)
This Figure is Referred to by Technical Specification 3.2.3 4..
3.
OPERATING LIMIT MCPR(P) = Kp
- OPERATING LiTrr MCPR(1CD) 3 ..
FOR P <25%: NO THERMAL LIMIT MONORING REQUIRED 3.4 3.39 NO LIMI1s SPECIFED 3.2 FOR 25% ' P ' PUypMS: (POYPASS a 30%)
I 3 .0 3 OLMCPR(P) = 12.44 + 0.043(30% - P)]
I1 2.93 FOR = 60% CORE FLOW 2.3 2.66 OLMCPR(P) - (2.93 + 0.092(30% - PM 2 .4 '60% Flow FOR > 60% CORE FLOW I 2.4 2.2 2.44 FOR30% I P 45%:
FOR45% ' P < 60%:
Kp - 1.28 + 0.0134(45% - P)
Kp - 1.15 +O.867(6% - P)
I 2 .0 FOR 60%' P: Kp 1.00 + 0.00375(100% - P) i.e -
I. 6 1.4 1.2 1.I I. i 0 10 20 3e0 4 I0 0 70 ae0 0 100 Power (% Rated)
EXELON Nuclear, Nuclear Fuels EXELONCOLRL R10 L1RIO C~ore Operating LimIts Report FIGURE 13 poWER DEPENDENT MCPR ULMIT ADJUSTEH AD MUPLIEs hIS F1GURE ISVALID FOR TWE OPERATING DOMAIN TBVOOS (References 2 and 5)
This Figure Is Referred to by Techflat Specificton 3-Z-3
-MT pp)
Me^TN OPERA TING T MC^5R(0) 5.0 4 4.54 5 KTMERLUMIT MONTORINGR No
' >60% Flow oR QI \
No ?OTS SPECIFIED11 kOR 25% C P C P6s*#
YPUPASS 30%)
3.77 OLMCPFORL26630lf% CORE FLOW OL.MCpRp') =13.TT
- o.15330% P) 3% . FOR > 60% COPE FLOW C0%FIW I - 1 2 8 0 013 4 ( 45% P) 3 3FOR45%P<6 0
%'P) 0.16+00 2.41e2.63 F60%
10 20 ', *.0 tswe I~ , . *-
=
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EXELON Nuclear, Nuclear Fuels EXELON-COLR-L1 R10 LI Ri0 Core Operating Limits Report Page 21, Rev. 0 FIGURE 14 FLOW DEPENDENT MCPR LIMITS MCPR(F)
THIS FIGURE ISVALID FOR ALL OPERATING DOMAINS (References 8 and 2)
This Figure is Referred to by Technical Specification 3.2.3 2.00 For Two Loop Operation, SLMCPR < 1.12 1 go 4 MCPR(F) = The Maximum of ErrHER 1.25 OR ( *0.5784 x (WO1OO) + 1.7073) 1.I0 WT = % Rated Core Flow
- 1. 7.0 4 C 1.60 aI L
1.30 1 1.40 I.30o 1.200 -
1.10 I I 30 60 50 60 70 I0 90 100 110 Core low (% Rated)
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI RIO LI RIO Core Operating Limits Report Page 22, Rev. 0 TABLE 2 ROD BLOCK MONITOR SETPOINTS (References 2, and 10)
This Information is Referred to by Technical Specification 3.3.6 Nominal Trip Setpoint Allowable Value LTSP 121.5% 121.5%
ITSP 116.5% 116.5%
HTSP 111.0% 111.7%
DTSP 92.0% 89.0%
These setpoints (with RBM filter time constant between 0.1 seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit which is less than or equal to the minimum cycle OLMCPR (see COLR references 2 and 10).
LTSP - Low trip setpoint ITSP - Intermediate trip setpoint HTSP - High trip setpoint DTSP - Downscale trip setpoint
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI RIO LIRIO Core Operating Limits Report Page 23, Rev. 0 TABLE 3 MAPLHGR SINGLE LOOP OPERATION (SLO) REDUCTION FACTOR (Reference 2)
This Information Is Referred to by Technical Specification 3.2.1 SLO reduction factor = 0.79 for the Cycle 11 core.
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LiRIO LIR10 Core Operating Limits Report Page 24, Rev. 0 TABLE 4 LINEAR HEAT GENERATION RATE uMITS This Information is Referred to by Technical Specification 3.2.4 FUEL TYRE M~AXIMI OM VAI lIEI GE1 3 14.4 kW/ft GE14 13.4 kW/ft MOT: The LHGR is an exposure dependent value. Due to the proprietary nature of these values only the maximum LHGR for each fuel type is listed in Table 4. The LHGR data is listed in Reference 11 (GNF proprietary).
EXELON Nuclear, Nuclear Fuels EXELON-COLR-LI R10 LIR1 Core Operating Limits Report Page 25, Rev. 0 TABLE 5 TURBINE BYPASS VALVE PARAMETERS (Reference 6)
This Information is Referred to by Technical Specifications 3.7.8 and 4.7.8.C TI IRRIMF RPACC CZYWTIM RFCPQWCF TIAAF Maximum delay time before start of bypass 0.11 sec valve opening following generation of the turbine bypass valve flow signal Maximum time after generation of a turbine 0.31 sec bypass valve flow signal for bypass valve position to reach 80% of full flow (includes the above delay time)
MINIMI IM RF1 11FREDl BYRPASS AI VES TO MAINTAIN SYS3TFM OPFARIAIBp Number of valves = 7
EXELON Nuclear, Nuclear Fuels EXELON-COLR-L1 R1O0 LIMRI Core Operating Limits Report Page 26, Rev. 0 TABLE 6 Control Rod Block Instrumentation Reactor Coolant System Recirculation Flow Upscale Trip (Reference 10)
This Information is Referred to by Technical Specification 3.3.6 Nominal Trip Setpoint - 113.4%
Allowable Value - 115.6%