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{{Adams
#REDIRECT [[BSEP 08-0093, Cycle 18 Core Operating Limits Report, Revision 1]]
| number = ML082190542
| issue date = 07/17/2008
| title = Brunswick, Unit 2 - Cycle 18 Core Operating Limits Report, Revision 1
| author name = Leich P A
| author affiliation = Progress Energy Carolinas, Inc, Progress Energy Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000324
| license number = DPR-062
| contact person =
| case reference number = BSEP 08-0093
| document type = Fuel Cycle Reload Report, Letter
| page count = 34
}}
 
=Text=
{{#Wiki_filter:Progress Energy July 17, 2008 SERIAL: BSEP 08-00931 U. S. Nuclear Regulatory Commission ATTN: DocumentControl Desk /Washington, DC 20555-0001
 
==Subject:==
Brunswick Steam Electric Plant, Unit No. 2 Docket No. 50-324/License No. DPR-62 Unit 2 Cycle 18 Core Operating Limits Report, Revision 1 Ladies and Gentlemen:
Enclosed is Revision 1 of theCore Operating Limits Report (COLR) for the Brunswick Steam Electric Plant (BSEP), Unit 2, Cycle 18 operation.
Carolina Power & Light Company, now doing business as Progress, Energy Carolinas, Inc., is providing the enclosed Revision 1 of the COLR in accordance with BSEP Technical Specification 5.6.5.d, which requires that the COLR, including any mid-cycle revisions or supplements, be provided to the NRC upon issuance.
The COLR revision becomes effective on-July 30, 2008. The enclosed revision of the COLRksupersedes the -Revision 0 report previously submitted by letter dated April 2, 2007, (i.e., ADAMS Accession Numbers ML070990198 and ML070990200).
No regulatory commitments are contained in this submittal.
Please refer any questions regarding this submittal to Mr. Gene Atkinson, Supervisor'-
Licensing/Regulatory Programs, at (910) 457-2056.Sincerely, Philip A. Leich Manager -Support Services Brunswick Steam Electric Plant LJG/ljg --
 
==Enclosure:==
 
Brunswick Unit 2, Cycle 18 Core Operating Limits Report, June 2008 Revision 1 Progress Energy Carolinas, Inc.Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461 /
Document Control Desk BSEP 08-0093 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Joseph D. Austin, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) (Electronic Copy Only)11555 Rockville Pike Rockville, MD 20852-2738 Chair -North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 BSEP 08-0093 Enclosure Brunswick Unit 2, Cycle 18 Core Operating Limits Report June 2008 Revision 1 NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 1, Revision 1 BRUNSWICK UNIT 2, CYCLE 18 CORE OPERATING LIMITS REPORT June 2008 Prepared By: Verified By: Approved By: Westmoreland, Gregory 2008.06.10, f6:"2:05 00'Greg Westmoreland BWR Fuel Engineering,-
Lead Engineer Pribyl, David i{2008.06.1010:42:25
-04'00'David Pribyl BWR Fuel Engineering,-
Senior Engineer Blom, Michael ýq Supervisor Approval 2008.06.10 11:4j4:48
-04'00'Michael Blom BWR Fuel Engineering
-Supervisor NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 2, Revision 1 LIST OF EFFECTIVE PAGES Page(s)1-2 3-4 5 6-7 8-9 10-21 22 23 24-30 Revision 1 0 1 0 1 0 1 0 1 NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1267 62C18 Core Operating Limits Report Page 3, Revision 0 TABLE OF CONTENTS Subjec Page C o v e r ......................................................................................................................................................
1 List of Effective Pages ...........................................................................................................................
2 Table of Contents ...................................................................................................................................
3 List of Tables .........................................................................................................................................
4 List of Figures ........................................................................................................................................
4 Introduction and Sum m ary ...........................................
..............
.............................
5 Single Loop Operation
...........................................................................................................................
5 Inoperable M ain Turbine Bypass System ........................................................................................
6 Feedwater Temperature Reduction
................................................
6 A PLH GR Lim its ....................................................................................................................................
7 M CPR Lim its ............................................................................................
7 RBM Rod Block Instrum entation Setpoints
....................................................................................
7 Stability Option III .................................................................................................................................
7 Pow er/Flow M aps ..................................................................................................................................
8 References
...............................................................................................................................................
9 NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1267 B2C18 Core Operating Limits Report Page 4, Revision 0 CAUTION References to COLR Figures or tables should be made using titles only; figure and table numbers ma change from cycle to cycle.LIST OF TABLES Table Title Page T able 1: M C PR L im its .................................................................................................................................
10 Table 2: R B M System Setpoints
..................................................................................................................
11 T able 3: PB D A Setpoints
............................................................................................................................
12 LIST OF FIGURES Figure Title or Description Page Figure 1: APLHGR Limit Versus Average Planar Exposure -EDB # 2572 ............................................
13 Figure 2: APLHGR Limit Versus Average Planar Exposure -EDB # 2573 ............................................
14 Figure 3: APLHGR Limit Versus Average Planar Exposure -EDB # 2574 ............................................
15 Figure 4: APLHGR Limit Versus Average Planar Exposure -EDB # 2575 ............................................
16 Figure 5: APLHGR Limit Versus Average Planar Exposure -EDB # 2660 ............................................
17 Figure 6: APLHGR Limit Versus Average Planar Exposure -EDB # 2853 ............................................
18 Figure 7: APLHGR Limit Versus Average Planar Exposure -EDB # 2854 ............................................
19 F igure 8 : (not used] ........................................................................................................................................
20 Figure 9: Flow-Dependent MAPLHGR Limit, MAPLHGR(F)
..............................................................
21 Figure 10: Power-Dependent MAPLHGR Limit, MAPLHGR(P)
............................................................
22 Figure 11: Flow-Dependent MCPR Limit, MCPR(F) ...............................................................................
23 Figure 12: Power-Dependent MCPR Limit, MCPR(P) .............................................................................
24 Figure 13: Stability Option III Power/Flow Map: OPRM Operable, Two Loop Operation, 2923 MWt ........ 25 Figure 14: Stability Option III Power/Flow Map: OPRM Inoperable, Two Loop Operation, 2923 MWt ..... 26 Figure 15: Stability Option III Power/Flow Map: OPRM Operable, Single Loop Operation, 2923 MWt ..... 27 Figure 16: Stability Option III Power/Flow Map: OPRM Inoperable, Single Loop Operation, 2923 MWt ..28 Figure 17: Stability Option III Power/Flow Map: OPRM Operable, FWTR, 2923 MWt .........................
29 Figure 18: Stability Option III Power/Flow Map: OPRM Inoperable, FWTR, 2923 MWt .......................
30 NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 5, Revision 1 Introduction and Summary CAUTION References to COLR Figures or Tables should be made using titles only; figure and table numbers ma change from cycle to cycle. I This report provides the values of the power distribution limits and control rod withdrawal block instrumentation setpoints for Brunswick Unit 2, Cycle 18 as required by TS 5.6.5.OPERATING LIMIT REQUIREMENT Average Planar Linear Heat Generation Rate (APLHGR) limits TS 5.6.5.a. 1 (with associated core flow and core power adjustment factors)Minimum Critical Power Ratio (MCPR) limits TS 5.6.5.a.2 (with associated core flow and core power adjustment factors)Period Based Detection Algorithm (PBDA) Setpoint for Function 2.f of TS 3.3.1.1', TS 5.6.5.a.3 Oscillation Power Range Monitor (OPRM)Allowable Values and power range setpoints for Rod Block Monitor Upscale TS 5.6.5.a.4 Functions of TS 3.3.2.1 Per TS 5.6.5.b and 5.6.5.c, these values have been determined using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met. The limits specified in this report support single recirculation loop operation (SLO) as required by TS LCO 3.4.1 and inoperable Main Turbine Bypass System as required by TS 3.7.6.In order to support the Stability Option III with an inoperable OPRM scram function, the following is also included in this report: OPERATING LIMIT REQUIREMENT BWROG Interim Corrective Action Stability Regions TS LCO 3.3.1.1, Condition I The generation of this COLR is documented in Reference 1 and is based on analysis results summarized in Reference 12.Single Loop Operation Brunswick Unit 2, Cycle 18 may operate over the entire MEOD range with SLO over the entire cycle as permitted by TS 3.4.1 with applicable limits specified in the COLR for TS LCO's 3.2.1, and 3.2.2.The applicable -limits are: LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) Limits: per Reference 1, the Figures 9 and 10 described in the APLHGR Limits section below include a SLO limitation of 0.8 on the MAPLHGR(F) and MAPLHGR(P) multipliers.
NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1267 B2C18 Core Operating Limits Report Page 6, Revision 0 LCO 3.2.2, Minimum Critical Power Ratio (MCPR) Limits: per Reference 1, Table 1 and Figures 11 and 12, the MCPR limits presented apply to SLO without modification.
Various indicators on the Power/Flow maps are provided not as operating limits but rather as a convenience for the operators:
a single loop operation (SLO) Entry Rod Line is shown on the two loop operation maps to avoid regions of instability in the event of a pump trip; a maximum core flow line is shown on the single loop operation maps to avoid vibration problems; a maximum core power of 50%RTP in SLO mitigates a spurious trip signal which could result from APRM noise; and Average Power Range Monitors (APRM) Simulated Thermal Power (STP) Scram and Rod Block nominal trip setpoint limits are shown to illustrate where these setpoints occur. Note that the APRMSTP setpoints are only approximations, shown at the estimated core flow corresponding to the actual drive flow-based setpoints.
The approximations serve to indicate where the operator may encounter the APRMSTP -High Allowable Value setpoints (LCO 3.3.1.1, Table 3.3.1.J1-1:
Reactor Protection System Instrumentation, Function 2.b).Inoperable Main Turbine Bypass System Brunswick Unit 2, Cycle 18 may operate with an inoperable Main Turbine Bypass System in accordance with TS 3.7.6 with applicable limits specified in the COLR for TS LCO 3.2.1 and LCO 3.2.2. The applicable limits are as follows: LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) Limits: in accordance with Reference 1 as shown in Figure 10, TBPOOS does not require an additional reduction in the MAPLGHR(P) limits, as the Turbine Bypass Operable and Inoperable limits are identical.
LCO 3.2.2, Minimum Critical Power Ratio (MCPR) Limits: in accordance with Reference 1, TBPOOS does not require an additional increase in the MCPR(P) multiplier as shown in Figure 12, as the Turbine Bypass Operable and Inoperable limits are identical.
TBPOOS requires increased MCPR limits, included in Table 1.The system response time assumed by the safety analyses from event initiation to start of bypass valve opening is 0.10 seconds, with 80% of the bypass flow capacity achieved in 0.30 seconds. Although the Turbine Bypass Out-of-Service (TBPOOS) analysis supports operation with all bypass valves inoperable for the entire maximum extended operating domain (MEOD) range and up to 1 10'F rated equivalent feedwater temperature reduction, three or more turbine bypass valves inoperable renders the Main Turbine Bypass System inoperable.
Feedwater Temperature Reduction A variation within lOF of nominal feedwater temperature or a power level less than 30% RTP has been evaluated as being in compliance with normal feedwater temperature operating limits. A feedwater temperature reduction in excess of 10°F together with the reactor power at a minimum of 30% rated requires the use of the Reduced FWTR MCPR limits (Table 1) and Stability Option III Power/Flow limits (Figures 17 and 18).
NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1267 B2C18 Core Operating Limits Report Page 7, Revision 0 APLHGR Limits The limiting APLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of planar average exposure is given in Figures 1 through 7. These values were determined with the SAFER/GESTR LOCA methodology described in GESTAR-I (Reference 2).Figures 1 through 7 are to be used only when hand calculations are required as specified in the bases for TS 3.2.1. Hand calculated results may not match a POWERPLEX calculation since normal monitoring of the APLHGR limits with POWERPLEX uses the complete set of lattices for each fuel type provided in Reference 3.The core flow and core power adjustment factors for use in TS 3.2.1 are presented in Figures 9 and 10.For any given flow/power state, the minimum of MAPLHGR(F) determined from Figure 9 and MAPLHGR(P) determined from Figure 10 is used to determine the governing limit.MCPR Limits The Scram Speed MCPR OPTION A, OPTION B, and non-pressurization transient MCPR limits for use in TS 3.2.2 for each fuel type as a function of cycle average exposure are given in Table 1. These values were determined with the GEMINI(TRACG) methodology and GEXL14 critical power correlation described in GESTAR-I1 (Reference
: 2) without assuming EOC-RPT, and are consistent with a Safety Limit MCPR of 1.11 specified by TS 2.1.1.2.The core flow and core power adjustment factors for use in TS 3.2.2 are presented in Figures 11 and 12. For any given power/flow state, the maximum of MCPR(F) determined from Figure 11 and MCPR(P) determined from Figure 12 is used to determine the governing limit. All MCPR limits presented in Table 1, Figure 11 and Figure 12 apply to two recirculation pump operation (TLO) and SLO without modification.
RBM Rod Block Instrumentation Setpoints The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation for use in TS 3.3.2.1 (Table 3.3.2.1-1) are presented in Table 2. These values were determined to be consistent with the bases of the ARTS program, and the determination of MCPR limits with the GEMINI(TRACG) methodology and the GEXL-PLUS critical power correlation described in GESTAR-I1 (Reference
: 2) as well as the NUMAC PRNM system as discussed in Reference
: 8. The table also includes the cycle-specific MCPR limits regarding the required operability of the RBM, consistent with Technical Specification Table 3.3.2.1-1.
Stability Option III Brunswick Unit 2 has implemented BWROG Long Term Stability Solution Option III using Oscillation Power Range Monitors (OPRMs) with the methodology described in Reference
: 4. Plant specific analysis incorporating the Option III hardware is described in Reference
: 5. Reload validation has been performed in accordance with Reference
: 6. The resulting stability based MCPR Operating Limit is provided for two conditions as a function of OPRM amplitude setpoint in Table 3. If desirable, Table 3 would support higher stability limits for various MCPR operating limits greater than the least limiting A O00 OLMCPR values provided in Table 1 or Figures 11 or 12, but the suggested stability setpoints ensure no OLMCPR restrictions from Option III. Table 3 shows that for an OPRM setpoint NGG Nuclear Fuels Mgmt. & Safety Analysis Design Caic. No. 2B21-1267 B2C18 Core Operating Limits Report Page 8, Revision 1 (Amplitude Setpoint Sp) of 1.13, OLMCPR(SS) is less restrictive than Figure 11 at 45% maximum flow or Figure 12 at 60.6% maximum power. Table 3 also shows that OLMCPR(2PT) is less restrictive than any limiting Table 1 OLMCPR for Sp equal to 1. 13. Therefore the OPRM Period Based Detection Algorithm (PBDA) setpoint limit for Amplitude Sp referenced by function 2.f of Table 3.3.1.1-1 of Technical Specification 3.3.1.1 is 1.13 for Cycle 18. Per Table 3-2 of Reference 6, an Sp value of 1.13 supports selection of a Confirmation Count Setpoint Np of 15 or less.Stability Option III also affects the power/Flow maps as described below.Power/Flow Maps Six Power/Flow maps for use at up to 2923 MWt (Figures 13-18) were developed based on References 1 and 7 to facilitate operation under Stability Option III as implemented by LCO 3.3.1.1, Condition I and function 2.f of Table 3.3.1.1-1 of the Technical Specifications.
All six maps illustrate the region of the power/flow map above 25% power and below 60% drive flow where the system is required to be enabled. [Note that the power/flow maps can only approximate the licensed Enabled Region, because the maps display core flow, while the Enabled Region is based on drive flow].Figures 13, 15 and 17 support an operable OPRM function 2.f and Figures 14, 16 and 18 support an inoperable OPRM function 2.f for TLO, SLO or FWTR, respectively.
Each figure for an operable OPRM shows a Scram Avoidance Region where the OPRM system may generate a scram to avoid an instability event. The figures for an inoperable OPRM event show the additional stability regions which address BWROG-94078 Interim Corrective Actions required to support LCO 3.3.1.1, Condition I. Figures 14, 16 and 18 for OPRM inoperable also includes a 5% Buffer Region around the Immediate Exit Region as an operator aid [Note for Figure 16 (SLO), the 5% Buffer Region does not fully enclose the Immediate Exit Region as on Figures 14 and 18].Figures 15 and 16 for SLO show the maximum allowable core flow at 45 Mlbs/hr and has the STP scram and rod block limits appropriately reduced. Note that the STP scram and rod block limits are defined in Technical Specifications, the Technical Requirements Manual, and Plant procedures.
Figures 15 and 16 also implement the corrective action for A/R 217345 which restricts reactor operation to no more than 50% RTP in SLO with OPRM operable or inoperable.
This operator aid is intended to mitigate a spurious trip signal which could result from APRM noise while operating at high power levels.Figures 17 and 18 for FWTR differ from TLO and SLO by including extended scram regions to provide additional stability protection.
Although the scram region for SLO above 50% RTP is more restrictive, intentional operation with SLO and FWTR is prohibited.
NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1267 B2C18 Core Operating Limits Report Page 9, Revision 1 References
: 1) BNP Design Calculation 2B21-1267, "Preparation of the B2C 18 Core Operating Limits Report," Revision 1, June 2008.2) NEDE-2401 1-P-A (including U.S. supplement), "General Electric Standard Application for Reactor Fuel," Revision 15, September 2005.3) NEDC-31624P, "Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 17 Cycle 18," Supplement 2, Revision 10, January 2007.4) NEDO-31960-A, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology," November 1995.5) GE-NE-C51-00251-00-01, Revision 0, "Licensing Basis Hot Bundle Oscillation Magnitude for Brunswick 1 and 2," March 2001.6) NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.7) BNP Design Calculation 0B21-1015, Revision 7, "Power/Flow Maps," March 2008.8) BNP Design Calculation 2C5 1-0001 Revision 3, "Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (2-C5 1 -APRM 1 through 4 Loops and 2-C51 -RBM-A and B Loops," May 26, 2004.9) NEDE-32906P-A, Revision 1, and Supplements, "TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analyses," April 2003.10) GE-NE-0000-0022-8180-RO, "Brunswick Nuclear Station TRACG Implementation for Reload Licensing Transient Analysis," February 2004.11) GE-NE-0000-0036-9469-R1, Revision 1, "Brunswick 1 and 2 Off-Rated Analyses Below the PLU Power Level," April 2006.12) Global Nuclear Fuel Document 0000-0052-0675-SRLR, Rev. 0; "Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2, Reload 17 Cycle 18," February 2007.
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 10, Revision 0 Table 1 MCPR Limits (EOC RPT not required)Non-pressurization TransientMcPR Limits.. ;,Fuel.~p t .. y: ..ExposuJreRange:, BOC -EOC GE14 1.30 Pressurization Transient MCPR.Limits 100% Power OLMCPR Turbine Feedwater
.Scram,, Exposure Range:
* Exposure Range: 'Bypass Temperature"'
Fuel Type, Speed System Normal? 'MCPR BOGto " EOR5900 MWd/MTto'Operable?
> ' ." Option E°RE900°MWd/MT
' EOC Operable Normal GE14 A 1.53 1.57 B 1.35 1.39 Operable Reduced GE14 'A 1.53 1.57 B 1.35 1.39 Inoperable Normal GE14 A 1.61 1.61 B 1.43 1.43 Inoperable Reduced GE14 ..A 1.61, 1.61 1B .43 1.43 This Table is referred to by Technical Specifications 3.2.2, 3.4.1 and 3.7.6.
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 11, Revision 0 Table 2 RBM System Setpoints Setpointa Trip Setpoint Allowable Value Lower Power Setpoint (LPSP ) 27.7 -- 29.0 Intermediate Power Setpoint (IPSPb) 62.7 !5 64.0 High Power Setpoint (HPSP ) 82.7 5 84.0 Low Trip Setpoint (LTSPc) 114.1 5 114.6 Intermediate Trip Setpoint (ITSPc) 5 108.3 -5 108.8 High Trip Setpoint (HTSPc) 5 104.5 5 105.0 RBM Time Delay (td2) 5 2.0 seconds < 2.0 seconds a RBM Operability requirements are not applicable:
(1) if MCPR > 1.76; or (2) if MCPR >1.45-and thermal power > 90% Rated Thermal Power.b Setpoints in percent of Rated Thermal Power., c' Setpoints relative toa full scale reading of 125.For example, 5 114.1 means 5 114.1/125.0 of full scale.This Table is referred to by Technical Specification 3.3.2.1 (Table 3.3.2.1-1).
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 12, Revision 0 Table 3 PBDA Setpoints OPRM Setpoint OLMCPR(SS)
OLMCPR(2PT) 1.05 1.224 1.097 1.06 1.248 1.119 1.07 1.273 1.142 1.08 1.300 1.165 1.09 1.327 1.190 1.10 1.356 1.215 1.11 1.384 1.241 1.12 1.414 1.268 1.13 1.445 1.295 1.14 1.477 1.324 1.15 1.511 1.355 Acceptance Criteria Off-rated OLMCPR @ Rated Power OLMCPR 45% Flow, 60.6% power PBDA Setpoint Setpoint Value Amplitude Sp 1.13 Confirmation Count Np 15 This Table is referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-1).
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 13, Revision 0 Figure 1 12.0 11.0 10.0.-j.-9.0 8.0 7.0 6.0 5.0 4.0 Fuel Type GE14-P1ODNAB420-18GZ-10OT-150-T-2572 Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure -EDB# 2572[This Figure is Referred To By------ Technical Specification 3.2.1 Exposure Limit ____(GWd/Mt) (kW/ft) -_0.00 9.29 0.22 9.37 1.10 9.51 2.20 9.70 3.31 9.91 4.41 10.11 5.51 10.26 "_6.61 10.40 -, 7.72 10.53 "-8.82 10.66 9.92 10.78 11.02 10.89 12.13 11.00 13.23 10.99 Permissible 14.33 10.97 Region of 15.43 10.96 Operation 16.53 10.93 18.74 10.86 22.05 10.67 27.56 10.25 i _33.07 9.80 -_=38.58 9.29 -44.09 8.81 49.60 8.34 55.12 7.86 " 60.63 5.62 62.23 4.90 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT)
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 14, Revision 0 Figure 2 12.0 11.0 10.0 9.0 I-n 8.0-J 0.7.0 6.0 5.0 4.0 Fuel Type GE14-P1ODNAB419-6G7.0/7G6.0/3G2.0-10OT-150-T-2573 Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure -EDB# 2573[This Figure is Referred To By-- Technical Specification 3.2.1 Exposure Limit-(GWd/Mt) (kW/ft)-0.00 9.24 --0.22 9.31 1.10 9.43 --2.20 9.60 , 3.31 9.77 4.41 9.96 5.51 10.13 6.61 10.27 7.72 10.40 8.82 10.52 9.92 10.64 11.02 10.77 12.13 10.89 Permissible 13.23 10.88 Region of 14.33 10.88 Operation 15.43 10.88 16.53 10.87 18.74 10.83 22.05 10.67 27.56 10.23 33.07 9.78 -, 38.58 9.33 44.09 8.87 49.60 8.37 55.12 7.84 60.63 5.55 62.07 4.90------ -0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 15, Revision 0 Figure 3 Fuel Type GE14-P1ODNAB425-3G7.0/14G6.O/1 G2.0-10OT-150-T-2574 Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure -EDB# 2574 12.0 11.0 10.0 T I I I I This Figure is Referred To By V Technical Specification 3.2.1 ri/Nk&#xfd;I I I-0=-j 0~9.0 8.0 7.0 A Exposure Limit (GWd/Mt) (kW/ft)0.00 9.37 0.22 9.44 1.10 9.55 2.20 9.70 3.31 9.85 4.41 10.01 5.51 10.16 6.61 10.30 7.72 10.45 8.82 10.60 9.92 10.70 11.02 10.79 12.13 10.87 13.23 10.87 14.33 10.85 15.43 10.84 16.00 10.84 16.53 10.84 18.74 10.82 21.09 10.72 22.05 10.68 27.56 10.26 33.07 9.82 38.58 9.33 44.09 8.83 49.60 8.35 55.12 7.85 60.63 5.72 62.46 4.90 Permissible
-Region of Operation k 6.0 5.0 4.0 I -- -- -4 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 16, Revision 0 Figure 4 12.0 11.0 10.0 I-9.0 8.0 7.0 Fuel Type GE1 4-P1 ODNAB439-12G6.0-1 OOT-1 50-T-2575 Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure -EDB# 2575 IB--- -- -I -I I --* i ' 'This Figure is Referred To By--,,_ _. _ ,_ -, ,Technical Specification 3.2.1 Exposure Limit (GWd/Mt) (kW/ft)t), 0.00 9.68 -0.22 9.72 , 1.10 9.79 -- _ -_2.20 9.89 ,+_ _3.31 9.99 --.4.41 10.09 -5.51 10.20 , , _6.61 10.31 , -_7.72 10.43 _ ._ _8.82 10.55 '_9.92 10.67 11.02 10.79 !12.13 10.92 13.23 10.93 14.33 10.92 Permissible 15.43 10.90 Region of 16.00 10.89 Operation 16.53 10.88 18.74 10.81 21.09 10.66 22.05 10.60 -.2 7 .5 6 1 0 .1 8 , .. ...33.07 9.76 -.38.58 9.32 -I, 44.09 8.87 ,* 49.60 8.37 .-.55.12 7.83 60.63 5.54-62.06 4.88 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT)6.0 5.0 4.0 NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 17, Revision 0 Figure 5 12.0 11.0 10.0 I-CD=~1 0~9.0 8.0 7.0 Fuel Type GE1 4-P1 ODNAB413-16GZ-1 OOT-1 50-T-2660 Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure -EDB# 2660_,_____, ______ ____This Figure is Referred To By-i -zzz, Technical Specification 3.2.1 Exposure Limit __(GWd/Mt) (kW/ft)0.00 9.57 _N 0.22 9.60 1.10 9.66 2.20 9.77 3.31 9.92 4.41 10.08 --_5.51 10.26 6.61 10.44 7.72 10.59 8.82 10.74 9.92 10.87 11.02 11.00 12.13 11.12 13.23 11.15 14.33 11.16 Permissible 15.43 11.16 Region of 16.00 11.16 16.53 11.16 Operation 18.74 11.13 __21.09 11.02 22.05 10.98 27.56 10.57 33.07 10.15 38.58 9.65 44.09 9.12 49.60 8.59 55.12 8.04 60.63 6.48 63.50 5.18 64.16 4.88------- -6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 17, Revision 0 Figure 5 12.0 11.0 10.0 I-0 9.0 8.0 7.0 Fuel Type GEl 4-P1 ODNAB413-16GZ-1 OOT-1 50-T-2660 Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure -EDB# 2660__,,_____,,__
_This Figure is Referred To By ----iiTechnical Specification 3.2.1 Exposure Limit -,_(GWd/Mt) (kW/ft) ---0.00 9.57 0.22 9.60 1.10 9.66 2.20 9.77 3.31 9.92 4.41 10.08 --, _5.51 10.26 6.61 10.44 7.72 10.59 8.82 10.74 9.92 10.87 11.02 11.00 12.13 11.12 13.23 11.15 14.33 11.16 Permissible 15.43 11.16 Region of 16.00 11.16 16.53 11.16 Operation 18.74 11.13 21.09 11.02 22.05 10.98 27.56 10.57 33.07 10.15 38.58 9.65 44.09 9.12 49.60 8.59 55.12 8.04 60.63 6.48 63.50 5.18 64.16 4.88 6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2821-1267 Page 18, Revision 0 Figure 6 12.0 11.0 10.0 0-J 0~9.0 8.0 7.0 Fuel Type GE1 4-P1 ODNAB407-16GZ-1 OOT-1 50-T-2853 Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure -EDB# 2853 This Figure is Referred To By--- -, ITechnical Specification 3.2.1 Exposure Limit--(GWd/Mt) (kW/ft)-0.00 9.47-1.10 9.71-2.20 9.87 -3.31 10.02 -- _4.41 10.17 5.51 10.31 6.61 10.45 7.72 10.57 8.82 10.70 9.92 10.82 11.02 10.93 12.13 11.05 13.23 11.06 14.33 11.05 Permissible 15.43 11.05 Region of 16.00 11.05 Operation 16.53 11.05 18.74 11.02 21.09 10.91 22.05 10.87 27.56 10.49 --33.07 10.08 38.58 9.58 44.09 9.07 49.60 8.54 55.12 7.99 60.63 6.34 63.50 5.03 63.84 4.88 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)6.0 5.0 4.0 NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 19, Revision 0 Figure 7 Fuel Type GE14-P1ODNAB425-18GZ-1OOT-150-T-2854 Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure -EDB# 2854.12.0 11.0 10.0:-C,J-J w 9.0 8.0 7.0____ j-This Figure is Referred To By am"=- -Technical Specification 3.2.1 Exposure Limit____ (GWd/Mt) (kW/ft) --0.00 8.85 1.10 9.01- __ _ _ ___2.20 9.14 3.31 9.27 4.41 9.41 5.51 9.54 6.61 9.68 7.72 9.82 8.82 9.95 9.92 10.09 __11.02 10.23 12.13 10.27 13.23 10.29 14.33 10.31 15.43 10.34 16.00 10.35 Permissible 16.53 10.37 Region of 18.74 10.44 Operation 21.09 10.47 22.05 10.48 27.56 10.28 33.07 9.84 38.58 9.38 44.09 8.91 49.60 8.41 55.12 7.88 60.63 5.70 62.23 4.96------6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Caic. No. 2B21-1267 Page 20, Revision 0 Figure 8[Not Used]
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 21, Revision 0 Figure 9 Flow-Dependent MAPLHGR Limit, MAPLHGR(F) 110 -1.05 This Figure is Referred To By Two Loop Operation Limit Technical Specifications 3.2.1, 3.4.1 and 3.7.6 1.00 0.95 -Max Flow= 102.5%--107%/0.90 --112% -0.90 -0. -Single Loop Operation Limit 0 t50.80 -... i U,.r 0.70 -O MAPLHGR(F)
= MAPFACF
* MAPLHGRsTD MAPLHGRSTD
= Standard MAPLHGR Limits S0.6MAPFACF(F)
= Minimum (1.0, AFWc/100+BF)
Wc = % Rated Core Flow LL 0.60 ....AF And BF Are Fuel Type Dependent Constants Given Below: Max Core Flow 0.55 -- ....(% Rated) AF BF 102.5 0.6784 0.4861 107.0 0.6758 0.4574 112.0 0.6807 0.4214 117.0 0.6886 0.3828 0.45 --- ....0.40 1 -. ...30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 Core Flow (% Rated)
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 22, Revision 1 Figure 10 Power-Dependent MAPLHGR Limit, MAPLHGR (P)1.05 1.00 0.95 0.90-. 0.85 0.U_u-o.. 0.80 S0.75 I,4.0.70.-J 0.65 0.60 0.0.55 a.0.45 0.40 Core Flow < 65% Turbine Bypass Operableor Inoperable
..............j , MAPLHGR(P)
= MAPFACp
* MAPLHGRSTD MAPLHGRSTD
= Standard MAPLHGR Limits 10 CoreFlow>65%
-Turbine Bypass Operable or Inoperable Core Flow< 50% -Turbine a Bypass Operable or Inoperable
'Core Flow < 65% -Turbine Bypass Operable or Inoperable L. T ....... .............--r --For P < 23%: No Thermal Limits Monitoring Required For 23% : P < 26% & Turbine Bypass Operable or Inoperable:
For Core Flow:< 50%: MAPFACp = 0.567 + 0.0157 (P -26%)For Core Flow < 65%: MAPFACp = 0.495 + 0.0130 (P -26%)For Core Flow > 65%: MAPFACp = 0.433 + 0.0063 (P -26%)For26% < P < 50% & Turbine Bypass Operable or Inoperable:
For Core Flow < 65%: MAPFACp = 1.0 + 0.005224 (P -100%)For Core Flow > 65%: MAPFACp = 0.655 + 0.00292 (P -50%)For P > 50%: MAPFACp = 1.0 + 0.005224 (P -100%)Coe lo Core Flow >65% -Turbine_BBypass Operable or Inoperable 0.35 t-I I I I I 0.30.I J, I I 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Pbypass (26%)Power (% Rated)
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Caic. No. 2B21-1267 Page 23, Revision 0 Figure 11 Flow-Dependent MCPR Limit, MCPR(F).1.80 1.70 1.60 a. 1.50 1.40 1.30 1.20 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)
NGG Nuclear Fuels Mgmt. & Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 24, Revision 1 Figure 12 Power-Dependent MCPR Limit, MCPR (P)3.80 3.70 3.60 3.50 3.40 3.30 3.20 3.10 v 3.00 0.vl 2.90 M 2.80 j 2.70 P- 2.60 a. 2.50 , 2.40 0 2.30 2.20 2.10 2.00 1.90 1.80 0 1.70 Al 1.60 0.5 1.50 40-a 1.40 , 1.30 0.o 1.20-1.10 S1.00-r I l i] Ii I I Ii I i i I o[MCPF I I I Rated"MCPR Multiplier (Kp) I I I I1f L ----LMrR(P, Core Flow > 65% -Turbine Bypass I-Operableorlnoperable OperatingLimitMCPRl t OLMCPR(P)
= Kp *OLMCPR(1 00)k '" ForP< 23%: C re Flow< 65% -Turbine Bypass No Thermal Limits Monitoring Required* Operable ornoperable For 23% < P < 26% & Turbine Bypass Operable or Inoperable:
For Core Flow:< 50%: OLMCPR(P)
= [ 2.34 + 0.0700(26%
-P)]For Core Flow< 65%: Core Flow.< 50% -Turbine Bypass OLMCPR(P)
= [ 2.74 + 0.0967(26%
-P)]Operable or Inoperable For Core Flow> 65%: OLMCPR(P)
= [3.13 + 0.0900(26%
-P)]For 26%!5 P < 50% & Turbine Bypass Operable'CoreFlow>65% -TurbineBypass or Inoperable:
Operable or Inoperable For Core Flow <65%:------------------
------- OLMCPR(P)
= 1.82+ 0.01000(50%-
P)For Core Flow > 65%:--.- --/OLMCPR(P)
= 2.03+ 0.01209 (50%- P)For5O%! P <60%:-Kp = 1.18 + 0.00667 (60%- P)-For P > 60%: Core Flow 65% -Turbine Bypass Kp = 1.00 + 0.00450 (100% -.P)Operable or Inoperable This Figure is Referred To By Technical Specification 3.2.2, 3.4.1, 3.7.6 20 251 30 35 40 45 50 55 60 65 .70 75 80 85 90 95 100 Pbypass (26%)Power (% Rated)
Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B2C18 Core Operating Limits Report Figure 13 Stability Option III Power/Flow Map OPRM Operable, Two Loop Operation, 2923 MWt Design Calc. No. 2B21-1267 Page 25, Revision 1 This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 Minimum Maximum (MELLL) (ICF )Core Core Power Flow Flow% Mlbshr Mllushr 100 76.19 80.47 75.04 30.47 98 73.89 80.47 97 72.75 30.47 96 7161 30.47 95 70.49 80.47 94 9.36 3M0.47 93 68.25 30.47 92 67.13 50.47 91 66.03 30.47 90 6.93 30.47 89 63.33 30.47 33 62.74 30.47 37 61.66 30.51 3 3053 30.60 35 59.50 30.09 84 5&.43 30.79 33 57.37 80.90 32 54.31 31.05 31 55.25 31.21 80 54.20 31.36 79 53.15 1.51 78 52.12 31.67 77 51.03 31.32 76 50.05 31.98 75 49.02 82.13 74 48.00 82.29 73 4g.9 82.44 72 45.96 32.60 71 44.95 82.75 70 43.94 82.91 69 42.94 83.06 63 41.94 53.22 67 40.95 33.37 66 39.96 33.52 65 39.97 33.6 64 37.9 33.83 63 37.01 33.99 62 36.04 34.14 61 35.06 34.30 60 34.10 34.45 59 33.13 34.81 58 32.17 34.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %CoreFlow
 
==Reference:==
 
0B21-1015, Revision 7 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B2C18 Core Operating Limits Report Figure 14 Stability Option III Power/Flow Map OPRM Inoperable, Two Loop Operation, 2923 MWt Design Caic. No. 2B21-1267 Page 26, Revision 1 This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 J 120.0 110.0 100.0 90.0 80.0 70.060.0 50.0 40.0 30.0 20.0 10.0 Minimum Maximum (MRLLL) CheF)Core Core Power Flow Flow% Wma~ Mlb/h 100 76.19 80.47 99 75.04 80.47 98 73.85 80.47 97 72.75 80.47 96 71.61 80.47 95 70.49 80.47 94 69.36 80.47 93 68.25 80.47 92 67.13 80.47 91 66.03 80.47 90 66.93 80.47 89 63.83 80.47 88 62.74 80.47 87 61.66 80.51 86 60.5 80.60 85 S5.50 80.69 84 58.43 80.79 83 57.37 80.90 82 SG.31 81.05 81 33.25 81.21 80 54.20 81.36 79 53.16 81.51 78 52.12 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 48.98 82.44 72 45.96 82.80 71 44.95 82.75 70 43.94 82.91 69 42.94 83.06 68 41.94 83.22 67 40.95 63.37 66 39.98 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 62 36.04 64.14 61 35.06 84.30 60 34.10 84.48 S9 33.1.3 84.61 58 32.17 84.70 0 .0 1 .... 1.. ..- I. _0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 T7.0 84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %CoreFlow
 
==Reference:==
 
0B21-1015, Revision 7 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Caic. No. 2B21-1267 B2C18 Core Operating Limits Report Page 27, Revision I Figure 15 Stability Option III Power/Flow Map OPRM Operable, Single Loop Operation, 2923 MWt I This Figure supports Improved Technical Specification 3.3.1.1 arnd the Technical Requrements Manual Specification 3.3 120.0 Minimu Maxinum::: APRM S n MELLLI (ICP)11.... Cre Core 11low Plow--100 7L19 80.47 99 75.04 80.47 98a 73.39 80.47-APRM 97 72.75 30.47.d98 71.1 0.47 Rod- 95 70.49 0.47 9.0 ,- ,4 ".36 0.47 93 68.25 80.47 9R 2 67.13 80.47 80.0 '- -H' 91 8.03 80.47 80.0 90 "9 ,0.,7 89 63.73 20.47+ ++ 2.74 80.47 787 61.0 80.51 70.0 4G9.0 82.6185 aW.O go."0 74 48.43 82.79 793 47.37 82.90 I ,, ,0.0~ 2, S&31 81.05-&#xf7;-+2 1 SS.2S 81.21 3Es S++ I 4.20 81.36 79 43.16 81.61 S2.12 81.67 M. Lm77 51.08 81.22 76 S0.0s 81.'98 C7S 49.02 82.132.29 40073 46.90 82.44 072 4S.96 82.6i0 71 44.9S 82.75 30.0 70 43.94 52.91 20.0 --4 9 4.4 30 5 341.94 83.22++- ....6i7 4Q.95 83.37+-IM NL+..........
f 39.96, "352 20.0 MSI P:Wp: Coro 60 as5 32197 84.7...... 64 37.99 8 93 37.01 83.99 NaUW 62 36,04 ",14 10.0 C- = OPR EnbedRgin 3S.06 "30...... 6 0 3-14.1 $&."1 I. -3. iiu upSw iiu owU 58 32.17 81*70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Gam Flow 0 10 20 30 40 50 60 YO 80 90 100 110 120 % Core Flow
 
==Reference:==
 
0B21-1015, Revision 7 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B2C18 Core Operating Limits Report Figure 16 Stability Option III Power/Flow Map OPRM Inoperable, Single Loop Operation, 2923 MWt Design Calc. No. 2B21-1267 Page 28, Revision 1 This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 110.0 100.0 90.0 80.0 70.0 CL 60.0 50.0 40.0 30.0 20.0 10.0 0.0 Miimnum Maximum (MHLLLI (lCF)Core Com Power Flow Flow% Hhj~hc- Mlblh 1.00 76.1 80.47 99 75.04 30.47 98 73.89 80.47 97 72.75 80.47 96 7161 80.47 95 70.49 80.47 94 69.36 80.47 93 68.25 30.47 92 67.13 30.47 91 68.03 80.47 90 64.93 80.47 89 63.83 80.47 U8 82.74 80.47 87 61.6 80.51 86 30.58 80.30 85 59.50 30.69 84 58.43 80.79 83 57.37 30.90 82 S6.31 81.05 81 S5.2S 81.21 80 54.20 81.36 79 53.16 81.51 78 52.12 81.67 77 51.06 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 4S.96 82.60 71 44.95 82.75 70 4&94 82.91 6 42.94 83.06 88 41.94 83.22 67 40.95 83.37 86 39.96 83"52 a5 36.97 83.88 64 37.99 83.83 83 37.01 83.99 62 36.04 84.14 61 35.06 84.30 60 36.10 8445 s5 33.13 84.61 58 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlb/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %CoreFlow
 
==Reference:==
 
0B21-1015, Revision 7 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B2C18 Core Operating Limits Report Design Calc. No. 2B21-1267 Page 29, Revision 1 Figure 17 Stability Option III Power/Flow Map OPRM Operable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 110.0 100.0 90.0 80.0 70.0 C. 60.0 50.0 40.0 30.0 20.0 10.0 Miiilmum Maximuam (MELLL_ (ICF)Core Core Power Flow Flow_ _ Mlb/hr .Mi/hrl 100 76.19 30.47 99 75.04 30.47 98 73.89 30.47 97 72.75 80.47 96 71.61 30.47 95 70.49 30.47 94 69.36 30.47 93 60,25 80.47 92 67.13 80.47 91 66.03 30.47 9o G4.93 30.47 29 63.33 30.47 a 62.74 30.47 87 61.66 80.51 86 0.56 30.60 a5 59.so 30.39 54 5.143 80.79 33 57.37 30.90 32 S.31 31.0S 81 55.25 31.21 s0 S4.20 31.36 79 53.16 31.51 73 52.12 81.67 77 51.08 81.82 76 S0.05 31.93 75 49.02 32.13 74 48.00 82.29 73 4.968 52.44 72 4S.96 52.30 71 44.9S 32.75 70 43.94 &L91 69 42.94 33.06 63 41.94 33.22 37 40.95 33.37 66 39.96 335$2 as 38.97 33.33 64 37.99 "3.13 63 37.01 93.99 62 36.04 "4.14 61 3S.06 34.30 60 34.10 34.45 59 33.13 34.61 so 32.17 84.70 0.0 0.0 7.7 15.4 23.1 30.8 38.5 43.2 53.9 61.6 69.3 77.0 84.7 92.4 0 10 20 30 40 50 60 70 80 90 100 110 120 Mlbs/hr Core Flow% Core Flow
 
==Reference:==
 
0B21-1015, Revision 7 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B2C18 Core Operating Limits Report Figure 18 Stability Option III Power/Flow Map OPRM Inoperable, FWTR, 2923 MWt Design Caic. No. 2B21-1267 Page 30, Revision 1 I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 1 120.0 110.0 100.0 90.0 80.0 70.0 S60.0 CL 50.0 40.0 30.0 20.0 10.0 0.0 Minimum Maximum (MBLLL) (ICF)Core Core Power Flow Flow% Mlba/hr M;l/hr 100 76.19 80.47 99 75.04 M0.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 95 70.49 80.47 94 6.3 80.47 93 68.25 8047 92 67.13 80.47 91 66.03 80.47 90 64.93 80.47 a9 63.83 80.47 a8 62.74 80.47 87 61.6 80.51 36 6058 80.0O 5S $9.S0 80.69 84 58.43 80.79 33 57.37 30.90 82 56.31 81.05 81 55.23 81.21 80 54.20 81.36 79 53.16 &#xa3;1.51 78 52.12 31.67 77 51.08 81.82 76 50.05 31.98 75 49.02 82.13 74 48.00 82.29 73 46.98 92.44 72 45.96 1 82.60 71 44.95 82.75 70 43.94 82.91 69 42.94 33.06 41.94 83.22 67 4Q.95 83.37 86 3I.96 83."2 4S 38.97 83.88 84 37.9 83.83 63 37.01 83.99 62 36.04 84.14 I61 3&06O W4.l 59 33.13 84.61 1 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbsihr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow
 
==Reference:==
 
0B21-1015, Revision 7}}

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