View source for BSEP 09-0054, Core Operating Limits Report, Revision 2 for Unit 1 Cycle 17

{{Adams
| number = ML092160594
| issue date = 07/23/2009
| title = Core Operating Limits Report, Revision 2 for Unit 1 Cycle 17
| author name = Mentel P
| author affiliation = Progress Energy Carolinas, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000325
| license number = DPR-071
| contact person = 
| case reference number = BSEP 09-0054
| document type = Fuel Cycle Reload Report, Letter type:BSEP
| page count = 51
}}

=Text=
{{#Wiki_filter:Pro ]ess Energy 32009 SERIAL: BSEP 09-0054 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

==Subject:==
Brunswick Steam Electric Plant, Unit No. 1 Docket No. 50-325/License No. DPR-71 Core Operating Limits Report, Revision 2 for Unit 1 Cycle 17 Ladies and Gentlemen:
In accordance with Technical Specification (TS) 5.6.5.d, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., is submitting Revision 2 of the Core Operating Limits Report (COLR) for the Brunswick Steam Electric Plant (BSEP), Unit No. 1. TS 5.6.5.d requires that the COLR, including any mid-cycle revisions or supplements, be provided to the NRC upon issuance.
A copy of the Unit 1 Cycle 17 COLR, May 2009, Revision 2, is enclosed. The Unit 1, Cycle 17 COLR has been revised to: (1) correct a pressure drop analysis input assumption that resulted in slightly non-conservative operating limits near end-of-cycle and all equipment out-of-service conditions and (2) remove unnecessary information. The COLR revision becomes effective on July 23, 2009.
Revision 1 of the Unit 1 Cycle 17 COLR was submitted by CP&L's letter dated July 30, 2008 (i.e., ADAMS Accession Number ML082190752).
No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Gene Atkinson, Supervisor - Licensing/Regulatory Programs, at (910) 457-2056.
Sincerely, Phyllis N. Mentel Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant POBox 10429 Southport, NC28461

Document Control Desk BSEP 09-0054 / Page 2 WRM/wrm

==Enclosure:==
Brunswick Unit 1, Cycle 17, Core Operating Limits Report, May 2009, Revision 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. Philip B. O'Bryan, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 cc (without enclosure):
Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

BSEP 09-0054 Enclosure Brunswick Unit 1, Cycle 17 Core Operating Limits Report, May 2009, Revision 2

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                 Design Calc. No. 1B21-1287 BLC17 Core Operating Limits Report                                      Page 1, Revision 2 BRUNSWICK UNIT 1, CYCLE 17 CORE OPERATING LIMITS REPORT May 2009 Westmorelan~d, Gregory 2009.05.2709:5-2:21 -04'00' Prepared By:
Greg Westmoreland BWR Fuel Engineering - Lead Engineer Stroupe, Charle&#xfd; 2009.05.27 11,;1 06 -04'00' Verified By:
Charles Stroupe BWR Fuel Engineering - Senior Engineer Thomas, Roger 2009.05.27 I*I.2 :07 -04'00' Approved By:
Roger Thomas BWR Fuel Engineering - Supervisor

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                     Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                          Page 2, Revision 2 LIST OF EFFECTIVE PAGES Paqe(s)                                     Revision 1-2                                           2 3-7                                           0 8                                             1 9                                             0 10                                            2 11-13                                         0 14                                            2 14a                                            1 15-18                                         0 19-24                                         2 25-27                                         0 28-31                                         2 32-39                                         0 40                                            2 41-47                                         0 This document consists of 48 total pages.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                                                                     Design Caic. No. 1B21-1287 B1C17 Core Operating Limits Report                                                                                                          Page 3, Revision 0 TABLE OF CONTENTS Sub.ect                                                                                                                                                     Page C ov e r ..................................................................................................................................................        1 List of Effective Pages ...................................................................................................................                  :.... 2 T a b le of C o n te n ts ...............................................................................................................................          3 Lis t of T a b le s ......................................................................................................................................         4 Lis t of F ig u re s .....................................................................................................................................         5 N o m e n c la tu re .....................................................................................................................................         6 Introduction and Summary ..................................................................................................................                        8 A P LH G R Lim its ...................................................................................................................................             9 MC PR Lim its .......................................................................................................................................              9 LH G R Lim its .....................................................................................................................................              10 P B D A S e tp o in ts ................................................................................................................................           11 R B M S e tp o in ts ..................................................................................................................................           12 Equipment Out-of-Service ................................................................................................................                         12 Single Loop Operation ......................................................................................................................                      12 Inoperable Main Turbine Bypass System ....................................................................................                                        13 Feedwater Temperature Reduction ..............................................................................................                                    13 R efe re n c e s .......................................................................................................................................          14

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                                                     Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                                                          Page 4, Revision 0 I                                                    CAUTION References to COLR Figures or Tables should be made using titles only; Figure and Table numbers Imay change from cycle to cycle.I LIST OF TABLES Table       Title                                                                                                                              Paqe T able 1:    R B M System S etpoints ..............................................................................................              15 Table 2:     RBM O perability Requirem ents ................................................................................                     16 T a b le 3:  P B D A S etpo ints ............................................................................................................. 17 Table 4:     Exposure Basis for Brunswick Unit 1 Cycle 17 Transient Analysis .............................                                       18 Table 5:     Power-Dependent MCPRp Lim its ...............................................................................                       19 NSS Insertion Times - BOC to < NEOC Table 6:     Power-Dependent MCPRp Lim its ................................................................................                      20 TSSS Insertion Times - BOC to < NEOC Table 7:     Power-Dependent MCPRp Lim its ................................................................................                      21 NSS Insertion Times - BOC to < EOCLB Table 8:     Power-Dependent MCPRp Lim its ...............................................................................                       22 TSSS Insertion Times - BOC to < EOCLB Table 9:     Power-Dependent MCPRp Lim its ...............................................................................                       23 NSS Insertion Times - BOC to < MCE (FFTR/Coastdown)
Table 10: Pow er-Dependent MC PRp Lim its ......................................................................... 24 TSSS Insertion Times - BOC to < MCE (FFTR/Coastdown)
Table 11:    Flow-Dependent MC PRf Lim its .................................................................................                     25 Table 12: ATRIUM-10 Steady State LHGRss Limits ...................................................................                               26 Table 13: G E14 Steady-State LHG Rss Lim its ...........................................................................                         27 Table 14: ATRIUM-10 Power-Dependent LHGRFACp Multipliers .............................................                                           28 NSS Insertion Times - BOC to < EOCLB Table 15: ATRIUM-10 Power-Dependent LHGRFACp Multipliers .............................................                                           29 TSSS Insertion Times - BOC to < EOCLB Table 16: ATRIUM-10 Power-Dependent LHGRFACp Multipliers ........................                                                                30 NSS Insertion Times - BOC to < MCE (FFTR/Coastdown)
Table 17: ATRIUM-10 Power-Dependent LHGRFACp Multipliers .............................................                                           31 TSSS Insertion Times - BOC to < MCE (FFTR/Coastdown)
Table 18: ATRIUM-10 Flow-Dependent LHGRFACf Multipliers .................................................. 32 Table 19: ATRIUM-10 Steady-State MAPLHGRss Limits ..........................................................                                     33

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                                    Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                                         Page 5, Revision 0 Table 20: GE14 Steady-State MAPLHGRss Limits .....................................................................                  34 GE14-P1ODNAB416-17GZ-10OT-150-T-2496 (only)
Table 21: GE14 Steady-State MAPLHGRss Limits .....................................................................                  35 GE14-P1ODNAB413-16GZ-10OT-150-T-2660 (only)
Table 22: GE14 Steady-State MAPLHGRss Limits .....................................................................                  36 GE14-P1ODNAB429-18GZ-10OT-150-T-2661 (only)
Table 23: GE14 Steady-State MAPLHGRss Limits .....................................................................                  37 GE14-P 1ODNAB437-12G6.0-10OT-150-T-2662 (only)
Table 24: GE14 Steady-State MAPLHGRss Limits .....................................................................                  38 GE14-PIODNAB407-16GZ-10OT-150-T-2853 (only)
Table 25: GE14 Steady-State MAPLHGRss Limits .....................................................................                  39 GE14-P1ODNAB425-18GZ-10OT-150-T-2854 (only)
Table 26: GE14 Power-Dependent MAPFACp Multipliers ..........................................................                       40 Table 27: GE14 Flow-Dependent MAPFACf Multipliers .............................................................                     41 LIST OF FIGURES Figure     Title or Description                                                                                                   Page Figure 1:  Stability O ption III Pow er/Flow M ap ............................................................................      42 OPRM Operable, Two Loop Operation, 2923 MWt Figure 2:  Stability O ption III Power/Flow Map ...........................................................................         43 OPRM Inoperable, Two Loop Operation, 2923 MWt Figure 3:  Stability O ption III Pow er/Flow Map ................................................................................ 44 OPRM Operable, Single Loop Operation, 2923 MWt Figure 4:  Stability O ption III Pow er/Flow Map ................................................................................ 45 OPRM Inoperable, Single Loop Operation, 2923 MWt Figure 5:  Stability O ption III Power/Flow Map ...........................................................................         46 OPRM Operable, FWTR, 2923 MWt Figure 6:  Stability O ption III Power/Flow Map ...........................................................................         47 OPRM Inoperable, FWTR, 2923 MWt

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                   Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                        Page 6, Revision 0 NOMENCLATURE APLHGR         Average Planar Linear Heat Generation Rate APRM           Average Power Range Monitor (Subsystem)
ARTS           APRM/RBM Technical Specification BOC            Beginning of Cycle BSP            Backup Stability Protection BWROG          BWR Owners Group CAVEX          Core Average Exposure COLR           Core Operating Limits Report CRWE           Control Rod Withdrawal Error DIVOM          Delta CPR Over Initial MCPR Versus Oscillation Magnitude EFPD           Effective Full Power Day EOC            End of Cycle EOCLB          End of Cycle Licensing Basis EOFP           End of Full Power EOOS           Equipment Out of Service F              Flow (Total Core)
FHOOS          Feedwater Heater Out of Service FFTR           Final Feedwater Temperature Reduction FVWTR          Feedwater Temperature Reduction HCOM           Hot Channel Oscillation Magnitude ICF            Increased Core Flow LCO            Limiting Condition of Operation LHGR           Linear Heat Generation Rate LHGRss         Steady-State Maximum .Linear Heat Generation Rate LHGRFAC        Linear Heat Generation Rate Factor LHGRFACf       Flow-Dependent Linear Heat Generation Rate Factor LHGRFACp       Power-Dependent Linear Heat Generation Rate Factor LPRM           Local Power Range Monitor (Subsystem)
MAPLHGR        Maximum Average Planar Linear Heat Generation Rate MAPLHGRss      Steady-State Maximum Average Planar Linear Heat Generation Rate MAPFAC         Maximum Average Planar Linear Heat Generation Rate Factor MAPFACf        Flow-Dependent Maximum Average Planar Linear Heat Generation Rate Factor MAPFACp        Power-Dependent Maximum Average Planar Linear Heat Generation Rate Factor MAPFACSLO      Maximum Average Planar Linear Heat Generation Rate Factor when in SLO MCE            Maximum Core Exposure MCPR           Minimum Critical Power Ratio MCPRf          Flow-Dependent Minimum Critical Power Ratio MCPRP          Power-Dependent Minimum Critical Power Ratio

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                     Design CaIc. No. 1B21-1287 B1C 17 Core Operating Limits Report                                         Page 7, Revision 0 NOMENCLATURE (continued)
MELLL          Maximum Extended Load Line Limit MEOD           Maximum Extended Operating Domain MSIVOOS        Main Steam Isolation Valve Out of Service NEOC           Near End of Cycle NFWT          Nominal Feedwater Temperature NSS           Nominal SCRAM Speed OLMCPR         Operating Limit Minimum Critical Power Ratio OPRM           Oscillation Power Range Monitor OOS            Out of Service P             Power (Total Core Thermal)
PBDA          Period Based Detection Algorithm PRNM          Power Range Neutron Monitoring (System)
RBM           Rod Block Monitor (Subsystem)
RFWT          Reduced Feedwater Temperature RTP           Rated Thermal Power SLMCPR        Safety Limit Minimum Critical Power Ratio SLO           Single Loop Operation SRV           Safety Relief Valve
* SRVOOS        Safety Relief Valve Out of Service STP           Simulated Thermal Power TBV           Turbine Bypass Valve TBVINS        Turbine Bypass Valves In Service TBVOOS        Turbine Bypass Valves Out of Service (all bypass valves OOS)
TIP           Traversing Incore Probe TLO           Two Loop Operation TS            Technical Specification TSSS          Technical Specification SCRAM Speed

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                Design CaIc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                     Page 8, Revision 1 I                                                    CAUTION References to COLR Figures or Tables should be made using titles only; Figure and Table numbers I may change from cycle to cycle.                                                                                 I Introduction and Summary The Brunswick Unit 1, Cycle 17 Core Operating Limits Report (COLR) provides values for the core operation limits and setpoints required by Technical Specifications (TS) 5.6.5.a.
Item                                                 RFequirement TS Table 3.3.1.1-1 Function 2f      Average Power Range Monitors - OPRM Upscale.
TS LCO 3.3.1.11 Condtio       Alternate method to detect and suppress thermal-hydraulic instability oscillations.
LCO Condition I TS Table 3.3.2.1-1   Rod Block Monitor - Upscale and Operability Requirements Function 1 TS 3.2.1        Average Planar Linear Heat Generation Rate (APLHGR).
TS 3.2.2        Minimum Critical Power Ratio (MCPR).
TS 3.2.3        Linear Heat Generation Rate (LHGR).
TS LCO 3.4.1      APLHGR, MCPR and LHGR limits for SLO.
TS LCO 3.7.6      APLHGR, MCPR and LHGR limits for an inoperable Main Turbine Bypass System.
Core Operating Limits required to be documented in COLR:
* APLHGR TS 5.6.5.a
* MCPR
* LHGR
* PBDA setpoints
* RBM allowable values and power range setpoints TS 5.6.5.b       Analytical methods approved by the NRC for determining core operating limits.
TS 5.6.5.c       Core Operating Limits shall be determined such that all applicable limits of the safety analysis are met.
TS 5.6.5.d       The COLR shall be provided upon issuance for each cycle to the NRC.
The core operating limits and setpoints presented in this COLR have been determined using NRC approved methodologies (References 7, 12, 14-30) in accordance with TS 5.6.5.b and are established such that all applicable limits of the plant safety analysis are met in accordance with TS 5.6.5.c.
In addition to the TS required core operating limits and setpoints, this COLR also includes maps showing the allowable power/flow operating range including the Option III stability ranges.
The generation of this COLR is documented in Reference 1 and is based on analysis results documented in References 2, 3, 4 and 5.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                            Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                 Page 9, Revision 0 APLHGR Limits Steady-state MAPLHGRss limits are provided for ATRIUM-10 (Table 19) and GE14 (Tables 20 - 25).
These steady-state MAPLHGRss limits must be modified as follows:
    "   GE14 MAPLHGR limits have a core power and core flow dependency. GE14 power-dependent MAPFACp multipliers (Table 26) and flow-dependent MAPFACf multipliers (Table 27) must be used to modify the steady-state MAPLHGRss limits (Tables 20 - 25) for off-rated conditions.
* ATRIUM-10 MAPLHGR limits do not have a power or flow dependency. However, in order to be consistent with the determination of GE14 MAPLHGR limits, power-dependent MAPFACP multipliers and flow-dependent MAPFACf multipliers with a constant value of 1.0 under all conditions have been assigned to ATRIUM-10.
    "   GE14 power-dependent MAPFACp multipliers are dependent on EOOS as indicated in Table 26. See COLR section titled "Equipment Out of Service" for a list of analyzed EOOS conditions. Care should be used when selecting the appropriate multiplier set.
* The applied MAPLHGR limit is dependent.on the number of recirculation loops in operation.
The steady-state MAPLHGR limit must be modified by a MAPFACSLO multiplier when in SLO.
MAPFACSLO has a fuel design dependency as shown below.
The applied TLO and SLO MAPLHGR limits are determined as follows:
MAPLHGR LimitTLO = MAPLHGRss x (MAPFACp, MAPFACf, 1.0)min MAPLHGR LimitSLO = MAPLHGRss x (MAPFACp, MAPFACf, MAPFACSLO)min where MAPFACSLO      = 0.85 for ATRIUM-10 fuel
                                                             = 0.80 for GE14 fuel Linear interpolation should be used to determine intermediate values between the values listed in the tables. Some of the limits tables show two breakpoints at 26.0%P and 50.0%P. IF performing a hand calculation of a limit AND the power is exactly on the breakpoint (i.e. 26.0 or 50.0), THEN select the most restrictive limit associated with the breakpoint.
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 applicable fuel type provided in Reference 5.
MCPR Limits The MCPR limits presented in Tables 5 through 11 are based on the TLO SLMCPR listed in Technical Specification 2.1.1.2.
* MCPR limits have a core power and core flow dependency. Power-dependent MCPRp limits are presented in Tables 5 through 10 while flow-dependent MCPRf limits are presented in Table 11.
* Power-dependent MCPRp limits are dependent on CAVEX, SCRAM insertion speed, EOOS, fuel design, number of operating recirculation loops (i.e., TLO or SLO) and core thermal power.
Values for the CAVEX breakpoints are provided in Table 4. See COLR section titled "Equipment Out of Service" for a list of analyzed EOOS conditions. Care should be used when

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                            Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                 Page 10, Revision 2 selecting the appropriate limits set.
    "   The MCPR limits are established such that they bound all pressurization and non-pressurization events.
* The power-dependent MCPRp limits (Tables 5-10) must be adjusted by an adder of 0.01 when in SLO.
The applied TLO and SLO MCPR limits are determined as follows:
MCPR LimitTLO = (MCPRP, MCPRf)max MCPR LimitsLO = (MCPRP + 0.01, MCPRf)max Linear interpolation should be used to determine intermediate values between the values listed in the tables. Some of the limits tables show two breakpoints at 26.0%P and 50.0%P. IF performing a hand calculation of a limit AND the power is exactly on the breakpoint (i.e. 26.0 or 50.0), THEN select the most restrictive limit associated with the breakpoint.
LHGR Limits Steady-state LHGRss limits are provided for ATRIUM-10 (Table 12) and GE14 (Table 13). These steady-state LHGRss limits must be modified as follows:
* ATRIUM-10 LHGR limits have a core power and core flow dependency. ATRIUM-10 power-dependent LHGRFACp multipliers (Tables 14-17) and flow-dependent LHGRFACf multipliers (Table 18) must be used to modify the steady-state LHGRss limits (Table 12) for off-rated conditions.
* ATRIUM-10 power-dependent LHGRFACp multipliers are dependent on CAVEX, SCRAM insertion speed, EOOS, and core thermal power. Values for the CAVEX breakpoints are provided in Table 4. See COLR section titled '&#xfd;Equipment Out of Service" for a list of analyzed EOOS conditions. Care should be used when selecting the appropriate multiplier set.
* The original licensing basis forGE14 LHGR limits did not include a core power and core flow dependency. However, in order to be consistent with the determination of ATRIUM-10 LHGR limits, power-dependent LHGRFACp multipliers and flow-dependent LHGRFACf multipliers with a constant value of 1.0 under all conditions have been assigned to GE14.
* GE14 LHGR limits are effectively monitored by GE14 APLHGR limits in accordance with the NRC approved methodology described in Reference 12.
* The applied LHGR limit is not dependent on the number of operating recirculation loops. No adjustment to the LHGR limit is necessary for SLO.
The applied LHGR limit is determined as follows:
LHGR Limit = LHGRss x (LHGRFACp, LHGRFACf)min Linear interpolation should be used to determine intermediate values between the values listed in the tables. Some of the limits tables show two breakpoints at 26.0%P and 50.0%P. IF performing a hand calculation of a limit AND the power is exactly on the breakpoint (i.e. 26.0 or 50.0), THEN select the most restrictive limit associated with the breakpoint.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                              Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                   Page 11, Revision 0 PBDA Setpoints Brunswick Unit 1 has implemented BWROG Long Term Stability Solution Option III (OPRM) with the methodology described in Reference 6. Plant specific analysis incorporating the Option III hardware is described in Reference 13. Reload validation has been performed in accordance with Reference 7.
The analysis was performed at 100%P assuming a two pump trip (2PT) and at 45%F assuming steady-state (SS) conditions at the highest rod line power (60.5%). The PBDA setpoints are set such that either the least limiting MCPRp limit or the least limiting MCPRf limit will provide adequate protection against violation of the SLMCPR during a postulated reactor instability. Based on the MCPR limits presented in Tables 5 through 11, the required Amplitude Trip Setpoint (1.12) is set by the least limiting 100%P MCPRP limit (1.35) which has an associated Confirmation Count Setpoint (14). The PBDA setpoints shown in Table 3 are valid for any feedwater temperature.
Evaluations by General Electric (GE) have shown that the generic DIVOM curves specified in Reference 7 may not be conservative for current plant operating conditions for plants which have implemented Stability Option Ill. To address this issue, AREVA has performed calculations for the relative change in CPR as a function of the calculated HCOM. These calculations were performed with the RAMONA5-FA code. This code is a coupled neutronic-thermal-hydraulic three-dimensional transient model for the purpose of determining the relationship between the relative change in ACPR and the HCOM on a plant specific basis. This method was developed consistent with the recommendations of the BWROG in Reference 8. The generation of the plant-specific DIVOM data with this model is consistent with the BWROG resolution of this nonconservatism as provided in Reference 9.
In cases where the OPRM system is declared inoperable, Backup Stability Protection (BSP) in accordance with Reference 10 is provided. Analyses have been performed to support operation with nominal feedwater temperature conditions and reduced feedwater temperature conditions (FHOOS and FFTR).
The power/flow maps (Figures 1-6) were developed based on Reference 4 to facilitate operation under Stability Option III as implemented by Function 2.f of Table 3.3.1.1-1 and LCO Condition I of Technical Specification 3.3.1.1. All maps illustrate the region of the power/flow map above 25% RTP and below 60% drive flow (correlated to core flow) where the system is required to be enabled. The generation of these maps is documented in Reference 2.
The maps supporting an operable OPRM (Figures 1, 3 and 5) show a Scram Avoidance Region, which is not a licensing requirement but isan operator aid to illustrate where the OPRM system may generate a scram to avoid an instability event. Note that the STP scram and rod block limits are defined in Technical Specifications, the Technical Requirements Manual, and Plant procedures, and are included in the COLR as an operator aid rather than a-licensing requirement.
Figures 3 and 4 implement the corrective action for AR-217345 which restricts reactor power to no more than 50% RTP when in SLO with OPRM operable or inoperable. This operator aid is intended to mitigate a spurious OPRM trip signal which could result from APRM noise while operating at high power levels.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                          Design CaIc. No. 1B21-1287 B1C17 Core Operating Limits Report                                               Page 12, Revision 0 RBM Setpoints The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation are presented in Table 1 and were determined to be consistent with the bases of the ARTS program (Reference 11). These setpoints will ensure the power-dependent MCPR limits will provide adequate protection against violation of the SLMCPR during a postulated CRWE event. Reference 3 revised these setpoints to reflect changes associated with the installation of the NUMAC PRNM system. RBM operability requirements, consistent with Notes (a) through (e) of Technical Specification Table 3.3.2.1-1, are provided in Table 2.
Equipment Out-of-Service Brunswick Unit 1, Cycle 17 is analyzed for the following operating conditions with applicable MCPR, APLHGR and LHGR limits.
    "   Base Case Operation
* SLO
* TBVOOS
    "   FHOOS
    "   Combined TBVOOS and FHOOS Base Case Operation as well as the above-listed EOOS assumes the following items OOS:
* Any 1 inoperable SRV 0    1 inoperable TBV
* Up to 40% of the TIP channels OOS
* Up to 50% of the LPRMs OOS Please note that during FFTR/Coastdown, FHOOS is included in Base Case Operation and TBVOOS.
Single Loop Operation Brunswick Unit 1, Cycle 17 may operate in SLO over the entire MEOD range with applicable MCPR, APLHGR and LHGR limits. The following must be considered when operating in SLO:
    "    SLO is not permitted with FHOOS.
    "    SLO is not permitted with TBVOOS.
    "    SLO is not permitted with MSIVOOS.
Various indicators on the Power/Flow Maps are provided not as operating limits but rather as a convenience for the operators. The purposes for some of these indicators are as follows:
* The SLO Entry Rod Line is shown on the TLO maps to avoid regions of instability in the event of a pump trip.
     "   A maximum core flow line is shown on the SLO maps to avoid vibration problems.
* APRM STP Scram and Rod Block nominal trip setpoint limits are shown at the estimated core flow corresponding to the actual drive flow-based setpoints to indicate where the Operator may encounter these setpoints (See LCO 3.3.1.1, Reactor Protection System Instrumentation

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                         Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                              Page 13, Revision 0 Function 2.b: Average Power Range Monitors Simulated Thermal Power - High Allowable Value).
Figures 3 and 4 implement the corrective action for AR-217345 which restricts reactor power to no more than 50% RTP when in SLO with OPRM operable or inoperable. This operator aid is intended to mitigate a spurious OPRM trip signal which could result from APRM noise while operating at high power levels.
Inoperable Main Turbine Bypass System Brunswick Unit 1, Cycle 17 may operate with an inoperable Main Turbine Bypass System over the entire MEOD range and cycle with applicable APLHGR, MCPR and LHGR limits as specified in the COLR. An operable Main Turbine Bypass System with only one inoperable bypass valve was assumed in the development of the Base Case Operation limits. Base Case Operation is synonymous with TBVINS. The following must be considered when operating with TBVOOS:
* Two or more inoperable bypass valves renders the entire Main Turbine Bypass System inoperable requiring the use of TBVOOS limits. The TBVOOS analysis supports operation with all bypass valves inoperable.
     "  TBVOOS operation coincident with FHOOS is supported using the combined TBVOOS/FHOOS limits.
* SLO is not permitted with TBVOOS.
Feedwater Temperature Reduction Brunswick Unit 1, Cycle 17 may operate with RFWT over the entire MEOD range and cycle with applicable APLHGR, MCPR and LHGR limits as specified in the COLR. NFWT is defined as the range of feedwater temperatures from NFWT to NFWT - 10'F. NFWT and its allowable variation was assumed in the development of the Base Case Operation limits. The FHOOS limits and FFTR/Coastdown limits were developed for a maximum feedwater temperature reduction of 11 0.3&deg;F.
The following must be considered when operating with RFWT:
     "  Although the acronyms FWTR, FHOOS, RFWT and FFTR all involve reduced feedwater temperature, the use of FFTR is reserved for cycle energy extension using reduced feedwater temperature at and beyond a core average exposure of EOCLB using FFTR/Coastdown limits.
     "  Prior to reaching the EOCLB exposure breakpoint, operation with FWTR >1O&deg;F and reactor power > 30% RTP requires use of the FHOOS limits. Below 30% RTP, Base Case Operation limits bound FHOOS limits.
     "  Until a core average exposure of EOCLB is reached, implementation of the FFTR/Coastdown limits are not required even if coastdown begins early.
     "  When operating with RFWT, the appropriate Stability Option III Power/Flow Maps (Figures 5 and 6) must be used.
* FHOOS operation coincident with TBVOOS is supported using the combined TBVOOS/FHOOS limits.
* SLO is not permitted with RFWT.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                       Design Caic. No. 1B21-1287 B1C17 Core Operating Limits Report                                            Page 14, Revision 2 References References designated with asterisks denote documents containing NRC approved methodologies listed in Brunswick Unit 1 Technical Specification 5.6.5.b.
: 1. BNP Design Calculation 1B21-1287, "Preparation of the B1C17 Core Operating Limits Report,"
Revision 2.
: 2. Design Calculation 0B21-1015, "BNP Power/Flow Maps," Revision 7.
: 3. Design Calculation 1C51-0001, "BNP Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (1-C51-APRM 1 through 4 Loops and 1-C51-RBM-A and B Loops," Revision 3, May 2004.
: 4. ANP-2674(P), "Brunswick Unit 1 Cycle 17 Reload Safety Analysis," Revision 3, February 2009.
: 5. NEDC-31624P, "Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 1 Reload 15 Cycle 16," Supplement 1, Revision 9.
: 6. NEDO-31960-A, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology,"
November 1995.
* 7. NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application," August 1996.
: 8. OG04-0153-260, "Plant-Specific Regional Mode DIVOM Procedure Guideline," June 15, 2004.
: 9. BWROG-03047 "Resolution of Reportable Condition for Stability Reload Licensing Calculations Using Generic Regional Mode DIVOM Curve," September 30, 2003.
: 10. OG02-0119-260 "Backup Stability Protection (BSP) for Inoperable Option III Solution, GE Nuclear Energy," July 17, 2002.
: 11. NEDC-31654P, "Maximum Extended Operating Domain Analysis for Brunswick Steam Electric Plant," February 1989.
* 12. NEDE-2401 1-P-A, "GESTAR II - General Electric Standard Application for Reactor Fuel", and US Supplement, Revision 14, June 2000.\
: 13. GENE-C51-00251-00-01, "Licensing Basis Hot Bundle Oscillation Magnitude for Brunswick 1 and 2," Revision 0, March 2001.
* 14. XN-NF-81-58(P)(A), "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model,"
Revision 2, March 1984.
* 15. XN-NF-85-67(P)(A), "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel,"
Revision 1, September 1986.
* 16. EMF-85-74(P) Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, February 1998.
* 17. ANF-89-98(P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs," Revision 1, May 1995.
* 18. XN-NF-80-19(P)(A) Volume 1, "Exxon Nuclear Methodology for Boiling Water Reactors -
Neutronic Methods for Design and Analysis," March 1983.
* 19. XN-NF-80-19(P)(A) Volume 4, "Exxon Nuclear Methodology for Boiling Water Reactors:
Application of the ENC Methodology to BWR Reloads," Revision 1, June 1986.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                      Design CaIc. No. 1B21-1287 B1C17 Core Operating Limits Report                                           Page 14a, Revision 1
* 20. EMF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors:
Evaluation and Validation of CASMO-4/MICROBURN-B2," Revision 0, October 1999.
* 21. XN-NF-80-19(P)(A) Volume 3, "Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," Revision 2, January 1987.
* 22. XN-NF-84-105(P)(A) Volume 1, "XCOBRA-T: A Computer Code for BWR Transient Thermal Hydraulic Core Analysis," February 1987.
* 23. ANF-524(P)(A), "ANF Critical Power Methodology for Boiling Water Reactors," Revision 2, November 1990.
* 24. ANF-913(P)(A) Volume 1, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Revision 1, August 1990.
* 25. ANF-1358(P)(A), "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Revision 3, September 2005.
* 26. EMF-2209(P)(A), "SPCB Critical Power Correlation", Revision 2, September 2003.
* 27. EMF-2245(P)(A), "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel," Revision 0, August 2000.
* 28. EMF-2361(P)(A), EXEM BWR-2000 ECCS Evaluation Model," Revision 0, May 2001.
* 29. EMF-2292(P)(A), "ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients," Revision 0, September 2000.
* 30. EMF-CC-074(P)(A) Volume 4, "BWR Stability Analysis - Assessment of STAIF with Input from MICROBURN-B2," Revision 0, August 2000.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                    Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                         Page 15, Revision 0 Table 1 RBM System Setpoints1 Setpoint     d                        ia,,
i Stpoint   'T Allowable Value Lower Power Setpoint (LPSP )                             27.7             < 29.0 Intermediate Power Setpoint (IPSPb)                      62.7             < 64.0 High Power Setpoint (HPSP )                              82.7             < 84.0 Low Trip Setpoint (LTSPc)                              < 114.1           < 114.6 Intermediate Trip Setpoint (ITSPc)                     < 108.3           < 108.8 High Trip Setpoint (HTSPc)                             < 104.5           < 105.0 RBM Time Delay      (tN2)                         < 2.0 seconds       < 2.0 seconds a     See Tabl e2 for RBM Operability Requiremen*ts.
b     Setpoints in percent of Rated Thermal Power:.
c     Setpoir* srelative to a full scale reading of 125. For example, < 114.1 means
                       ,< 11 .1/125.0 of fu~ll scale.
: d. Tripsetpoints and allowable values are based onVa high pwraayia 1   This table is referred to by Technical Specification 3.3.2.1 (Table 3.3.2.1-1) and 5.6.5.a.5.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                 Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                      Page 16, Revision 0 Table 2 2
RBM Operability Requirements IF the following conditions are met, THEN RBM Not Required Operable Thermal Power
(% rated)                   MCPR
                                      &#x17d;29% and < 90%                 1.65 SLO 90&#x17d;1.65 SLO
                                             >90%                  >1.39   TLO 2   Requirements valid for all fuel designs, all SCRAM insertion times and all core average exposure ranges.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                   Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                        Page 17, Revision 0 Table 3 3
PBDA Setpoints Amplitude Trip            OLMCPR(SS)                  LMCP.R(20T) 1.05                      1.21                      1.20 1.06                      1.23                      1.22 1.07                      1.24                      1.24 1.08                      1.26                      1.26 1.09                      1.29                      1.28 1.10                      1.31                      1.30 1.11                      1.33                      1.32 1.12                      1.36                      1.35 1.13                      1.38                      1.37 1.14                      1.41                      1.40 1.15                      1.43                      1.42
:Acceptance Criteria     Off-rated OLMCPR @              Rated Power, 45% Flow                   OLMCPR This table is referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-1) and 5.6.5.a.4.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                               Design Calc. No. 1B21-1287 BIC17 Core Operating Limits Report                                                    Page 18, Revision 0 Table 4 Exposure Basis 4 for Brunswick Unit 1 Cycle 17 Transient Analysis Core Average Exposure                                Comments (MWd/MTU)
Break point for exposure-dependent MCPRP 29,667             limits (NEOC)
Design basis rod patterns to 32,076             EOFP + 14 EFPD (EOCLB) 33,841             End of reactivity for FFTR /Coastdown -
Maximum Core Exposure (MCE) 4   The exposure basis for the defined break points are the core average exposure (CAVEX) values shown above regardless of the actual BOC CAVEX value of the As-Loaded Core.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                 Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                      Page 19, Revision 2 Table 5 5
Power-Dependent MCPRp Limits NSS Insertion Times BOC to < NEOC EOOS         Power            ATRIUM-10                    GE14 Condition     (% rated)           MCPRP                     MCPRp 100.0              1.35                       1.35 90.0              1.38                       1.37 50.0              1.53                       1.53 Base Case                 > 65%F        < 65%F      > 65%F         < 65%F Operation        50.0       2.02          1.82        2.02            1.81 26.0       2.39          2.21        2.39           2.22 26.0       2.60          2.49        2.63           2.50 23.0       2.73          2.60        2.76            2.61 100.0              1.40                       1.38 90.0              1.42                       1.41 50.0              1.59                       1.57
                                             > 65%F        _ 65%F      > 65%F         _<65%F TBVOOS          50.0       2.02          1.82        2.02            1.81 26.0       2.39          2.21         2.39           2.22 26.0       3.14          2.89         3.13           2.90 23.0        3.31         3.14         3.30           3.14 100.0              1.37                       1.36 90.0             1.40                       1.38 50.0             1.57                       1.57
                                             > 65%F        < 65%F       > 65%F         -<65%F 50.0       2.02         1.82         2.02           1.81 26.0       2.39         2.21         2.39           2.22 26.0       2.60         2.49         2.63           2.50 23.0       2.73         2.60         2.76           2.61 100.0              1.43                       1.40 90.0             1.46                       1.43 TBVOOS           50.0             1.64                       1.63 and                     > 65%F       < 65%F       > 65%F        < 65%F FHOOS           50.0       2.02         1.82         2.02           1.81 26.0       2.39         2.21         2.39           2.22 26.0       3.14         2.89         3.13           2.90 23.0       3.31         3.14         3.30           3.14 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.01. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                  Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                       Page 20, Revision 2 Table 6 6
Power-Dependent MCPRp Limits TSSS Insertion Times BOC to < NEOC EOOS         Power            ATRIUM-16                    GE14 Condition     (% rated)           MCPRP                     MCPRP 100.0              1.48                       1.45 90.0              1.49                       1.46 50.0              1.56                       1.55 Base Case                 > 65%F         - 65%F     > 65%F          < 65%F Operation        50.0        2.06          1.84       2.04            1.83 26.0        2.41          2.21       2.41            2.22 26.0        2.60          2.49       2.63            2.50 23.0        2.73          2.60       2.76            2.61 100.0              1.51                       1.48 90.0              1.53                       1.50 50.0              1.66                       1.64
                                             > 65%F         < 65%F     > 65%F          < 65%F TBVOOS           50.0        2.06          1.84       2.04            1.83 26.0        2.41          2.21       2.41            2.22 26.0        3.14          2.89       3.13            2.90 23.0        3.31          3.14       3.30            3.14 100.0              1.49                       1.46 90.0              1.50                       1.47 50.0              1.62                       1.62
                                             > 65%F         < 65%F     > 65%F          < 65%F 50.0        2.06          1.84       2.04            1.83 26.0        2.41          2.21       2.41            2.22 26:0        2.60          2.49        2.63           2.50 23.0        2.73          2.60        2.76           2.61 100.0               1.52                      1.49 90.0               1.55                      1.51 TBVOOS           50.0              1.70                      1.69 and                     > 65%F        < 65%F      > 65%F       - < 65%F FHOOS           50.0       2.06          1.84        2.04           1.83 26.0        2.41          2.21        2.41           2.22 26.0       3.14          2.89        3.13           2.90 23.0       3.31          3.14        3.30           3.14 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation,;the TLO MCPRp limits shown above must be adjusted by adding 0.01. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                Design Caic. No. 1B21-1287 B1C17 Core Operating Limits Report                                                     Page 21, Revision 2 Table 7 7
Power-Dependent MCPRp Limits NSS Insertion Times BOC to < EOCLB EOOS         Power            ATRIUM-10                    GE14 Condition     (% rated)           MCPRP                     MCPRp 100.0              1.41                       1.42 90.0              1.43                       1.43 50.0              1.55                       1.53 Base Case                 > 65%F        --65%F       > 65%F        < 65%F Operation        50.0       2.02          1.82         2.02          1.81 26.0       2.39          2.21         2.39          2.22 26.0       2.60          2.49         2.63          2.50 23.0       2.73          2.60         2.76          2.61 100.0              1.44                       1.44 90.0              1.47                       1.47 50.0              1.63                       1.61
                                             > 65%F        < 65%F       > 65%F        < 65%F TBVOOS            50.0       2.02         1.82         2.02          1.81 26.0        2.39         2.21         2.39          2.22 26.0        3.14         2.89         3.13          2.90 23.0        3.31         3.14         3.30          3.14 100.0              1.42                       1.44 90.0             1.44                       1.45 50.0             1.57                       1.57
                                              > 65%F       - 65%F       > 65%F        - 65%F EHOOS           50.0       2.02         1.82         2.02          1.81 26.0       2.39         2.21         2.39          2.22 26.0       2.60         2.49         2.63          2.50 23.0       2.73         2.60         2.76          2.61 100.0              1.46                       1.50 90.0             1.49                       1.52 TBVOOS.          50.0             1.64                       1.63 and                     > 65%F       < 65%F       > 65%F        < 65%F FHOOS           50.0       2.02         1.82         2.02          1.81 26.0       2.39         2.21         2.39          2.22 26.0       3.14         2.89         3.13          2.90 23.0       3.31         3.14         3.30          3.14 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.01. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                     Page 22, Revision 2 Table 8 8
Power-Dependent MCPRp Limits TSSS Insertion Times BOC to < EOCLB EOOS         Power            ATRIUM-10                   GE14 Condition     (% rated)           MCPRP                    MCPRP 100.0              1.48                      1.47 90.0              1.49                      1.48 50.0              1.56                      1.55 Base Case                 > 65%F        < 65%F      > 65%F        < 65%F Operation        50.0       2.06          1.84        2.05          1.83 26.0       2.41          2.21        2.41          2.22 26.0       2.60          2.49        2.63          2.50 23.0       2.73          2.60        2.76          2.61 100.0              1.51                      1.51 90.0              1.53                      1.52 50.0              1.66                      1.64
                                             > 65%F        _<65%F      > 65%F        < 65%F TBVOOS          50.0       2.06          1.84        2.05          1.83 26.0       2.41          2.21        2.41          2.22 26.0        3.14         2.89        3.13          2.90 23.0       3.31          3.14        3.30          3.14 100.0              1.49                      1.49 90.0              1.50                      1.50 50.0              1.62                      1.62
                                             > 65%F        _<65%F      > 65%F        < 65%F 50.0        2.06         1.84        2.05          1.83 26.0        2.41         2.21        2.41          2.22 26.0        2.60         2.49        2.63          2.50 23.0        2.73         2.60        2.76          2.61 100.0              1.52                      1.55 90.0              1.55                      1.57 TBVOOS          50.0              1.70                      1.69 and                     > 65%F       < 65%F      > 65%F        < 65%F FHOOS          50.0        2.06         1.84        2.05          1.83 26.0        2.41         2.21        2.41          2.22 26.0        3.14 "       2.89        3.13          2.90 23.0        3.31         3.14        3.30          3.14 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.01. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                 Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                      Page 23, Revision 2 Table 9 Power-Dependent MCPRp Limits 9 NSS Insertion Times BOC to < MCE (FFTR/Coastdown) 10 EOOS              Power           ATRIUM-10                   GE14 Condition       (% rated)           MCPRP                    MCPRP 100.0             1.46                      1.45 90.0             1.47                      1.46 Base Case            50.0             1.57                      1.57 Operation                    > 65%F
* 65%F      > 65%F        < 65%F 50.0       2.02         1.82        2.02          1.81 (includes FHOOS)         26.0       2.39         2.21        2.39          2.22 26.0       2.60         2.49        2.63          2.50 23.0       2.73         2.60        2.76          2.61 100.0             1.47                      1.50 90.0             1.50                      1.52 50.0             1.64                      1.63 TBVOOS                       > 65%F       < 65%F      > 65%F        -665%F 50.0       2.02         1.82        2.02          1.81 26.0       2.39         2.21        2.39          2.22 26.0       3.14         2.89        3.13          2.90 1     23.0       3.31         3.14        3.30          3.14 9    Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO
   , MCPRp limits shown above must be adjusted by adding 0.01. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.
10 FFTR/FHOOS included in Base Case Operation and TBVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                               Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                    Page 24, Revision 2 Table 10 Power-Dependent MCPRp Limits" TSSS Insertion Times 1BOC to < MCE (FFTR/Coastdown)
EOOS 12         Power            ATRIUM-10                   GE14 Condition       (% rated)           MCPRP                    MCPRP 100.0              1.50                      1.49 90.0              1.50                      1.50 Base Case           50.0              1.62                      1.62 Operation                    > 65%F       < 65%F      > 65%F         -<65%F 50.0        2.06         1.84        2.05           1.83 (includes FHOOS)        26.0        2.41         2.21        2.41           2.22 26.0        2.60         2.49        2.63           2.50 23.0        2.73         2.60        2.76           2.61 100.0              1.52                      1.55 90.0              1.55                      1.57 50.0              1.70                      1.69 TBVOOS                       > 65%F       < 65%F      > 65%F        -965%F 50.0        2.06         1.84        2.05           1.83 (includes FHOOS)        26.0        2.41         2.21        2.41           2.22 26.0        3.14         2.89        3.13           2.90 1    23.0        3.31         3.14        3.30           3.14 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service. For single-loop operation, the TLO MCPRp limits shown above must be adjusted by adding 0.01. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.
12  FFTR/FHOOS included in Base Case Operation and TBVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                              Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                   Page 25, Revision 0 Table 11 13 Flow-Dependent MCPRf Limits Core Flow           ATRIUM-10/GE14
(% of rated)               MCPRf 0.0                    1.55 31.0                    1.55 100.0                    1.20 107.0                    1.20 13  Limits valid for all SCRAM insertion times and all core average exposure ranges.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis            Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                 Page 26, Revision 0 Table 12 ATRIUM-10 Steady-State LHGRss Limits Peak            ATRIUM-10 Pellet Exposure         LHGR (GWd/MTU)             (kW/ft) 0.0                13.4 18.9                13.4 74.4                7.1

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                          Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                               Page 27, Revision 0 Table 13 14 15 GE14 Steady-State LHGRss Limits '
Peak                    GE14 Pellet Exposure               LHGR (GWd/MTU)                   (kW/ft)
All                     13.4 14  GE14 LHGR limits are effectively monitored by GE14 MAPLHGR limits in accordance with the NRC approved methodology described in Reference 12.
15  GE14 LHGR limits do not have a power or flow dependency. Thus, the GE14 LHGRFACp and the LHGRFACf multipliers have a constant value of 1.0 under all conditions.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                              Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                   Page 28, Revision 2 Table 14 16 ATRIUM-10 Power-Dependent LHGRFACp Multipliers NSS Insertion Times BOC to < EOCLB EOOS        Power              ATRIUM-10 Condition    (% rated)           LHGRFACP 100.0                1.00 80.0                1.00 50.0                0.94 Base Case                  > 65%F         < 65%F Operation       50.0         0.67           0.77 26.0         0.57        . 0.62 26.0         0.53           0.57 23.0         0.51           0.55 100.0                0.97 80.0                0.94 50.0                0.88
                                                          > 65%F        < 65%F TBVOOS          50.0         0.67            0.77 26.0         0.57            0.62 26.0         0.44            0.49 23.0         0.42            0.46 100.0                1.00 80.0                0.98 50.0                0.91
                                                          > 65%F          -<65%F 50.0         0.67            0.77 26.0         0.57            0.62 26.0         .0.53           0.57 23.0         0.51            0.55 100.0                0.97 80.0                0.94 50.0                0.86 TBVOOS                    > 65%F        < 65%F and and          50.0        0.67            0.77 26.0         0.57            0.62 26.0         0.44            0.49 23.0        0.42            0.46 16  Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                              Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                   Page 29, Revision 2 Table 15 17 ATRIUM-10 Power-Dependent LHGRFACp Multipliers TSSS Insertion Times BOC to < EOCLB EOOS        Power              ATRIUM-10 Condition    (% rated)           LHGRFACp 100.0                1.00 80.0                0.92 50.0                0.92 Base Case                  > 65%F         - 65%F Operation       50.0         0.65          0.75 26.0         0.57          0.62 26.0         0.53          0.57 23.0         0.51          0.55 100.0                0.94 80.0                0.91 50.0                0.86
                                                          > 65%F        _ 65%F 50.0         0.65          0.75 26.0         0.57          0.62 26.0         0.44          0.49 23.0         0.42          0.46 100.0                0.95 80.0                0.92 50.0                0.90
                                                          > 65%F        < 65%F 50.0         0.65          0.75 26.0         0.57          0.62 26.0         0.53          0.57 23.0         0.51          0.55 100.0                0.94 80.0               0.91 50.0               0.85 TBVOOS ad           5         > 65%F        < 65%F and          50.0        0.65 FHOOS                                    0.75 26.0        0.57          0.62 26.0        0.44          0.49 23.0        0.42          0.46 17 Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                               Design CaIc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                    Page 30, Revision 2 Table 16 18 ATRIUM-10 Power-Dependent LHGRFACp Multipliers NSS Insertion Times BOC to < MCE (FFTR/Coastdown) 9 EOOS'           Power              ATRIUM-10 Condition      (% rated)           LHGRFACP 100.0                1.00 80.0                0.95 Base Case          50.0                0.91 Operation                    > 65%F         - 65%F 50.0         0.67           0.75 (includes FHOOS)       26.0         0.57           0.62 26.0         0.53           0.57 23.0         0.51           0.55:
100.0                0.95 80.0                0.91 50.0                0.86 TBVOOS                       > 65%F        < 65%F (includes FHOOS)       50.0         0.67           0.75 26.0         0.57           0.62 26.0         0.44           0.49 23.0         0.42           0.46 18  Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service.
'9 FFTR/FHOOS included in Base Case Operation and TBVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                              Design CaIc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                   Page 31, Revision 2 Table 17 20 ATRIUM-10 Power-Dependent LHGRFACP Multipliers TSSS Insertion Times BOC to < MCE (FFTR/Coastdown)
EOOS 21        Power              ATRIUM-10 Condition      (% rated)           LHGRFACp 100.0                1.00 80.0                0.92 Base Case          50.0                0.89 Operation                    > 65%F         - 65%F 50.0         0.65           0.73 (includes FHOOS)       26.0         0.57           0.62 26.0         0.53           0.57 23.0         0.51           0.55 100.0                0.93 80.0                0.89 50.0                0.85 TBVOOS                       > 65%F        < 65%F (includes FHOOS)       50.0         0.65           0.73 26.0         0.57-          0.62 26.0         0.44           0.49 23.0         0.42           0.46 20  Limits support operation with any combination of any 1 inoperable SRV, 1 inoperable TBV, up to 40% of the TIP channels out-of-service, and up to 50% of the LPRMs out-of-service.
2'  FFTR/FHOOS included in Base Case Operation and TBVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                Design Calc. No. 1B21-1287 B 1C 17 Core Operating Limits Report                                                   Page 32, Revision 0 Table 18 22 ATRIUM-10 Flow-Dependent LHGRFACf Multipliers Core Flow
(% of rated)                 LHGRFACf 0.0                         0.90 31.0                           0.90 49.12                          1.00 107.0                           1.00 22  Multipliers valid for all SCRAM insertion times and all core average exposure ranges.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                             Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                  Page 33, Revision 0 Table 19 23 24 ATRIUM-10 Steady-State MAPLHGRss Limits '
Average Planar Exposure (GWd/MTU)                 MAPLHGR (kW/ft) 0.0                        12.5 15.0                        12.5 67.0                         7.3 23  ATRIUM-1 0 MAPLHGR limits do not have a power or flow dependency. Thus, the ATRIUM-1 0 MAPFACp and the MAPFACf multipliers have a constant value of 1.0 under all conditions.
24  ATRIUM-10 MAPLHGR limits must be adjusted by a 0.85 multiplier when in SLO. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                           Design CaIc. No. 11B21-1287 B1C17 Core Operating Limits Report                                                Page 34, Revision 0 Table 20 25 GE14 Steady-State MAPLHGRss Limits GE1 4-P1 ODNAB416-17GZ-1 OOT-1 50-T-2496 (only)
Average Planar Exposure         Limit (GWd/MTU)         (kW/ft) 0.00         9.27 0.22         9.33 1.10        9.44 2.20         9.59 3.31         9.76 4.41         9.93 5.51        10.11 6.61        10.30 7:72        10.50 8.82        10.71 9.92        10.91 11.02        11.12 12.13        11.31 13.23        11.36 14.33        11.35 15.43        11.34 16.53        11.31 18.74        11.23 22.05        11.03 27.56        10.60 33.07        10.12 38.58         9.49 44.09         8.91 49.60         8.37 55.12          7.87 60.63         6.53 64.27         4.88 25  The GE14 MAPLHGR limits presented in this COLR are a composite set of limits based on the most limiting MAPLHGR limits from each lattice.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                           Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                Page 35, Revision 0 Table 21 26 GEl4 Steady-State MAPLHGRss Limits GE14-P1ODNAB413-16GZ-10OT-150-T-2660 (only)
Average Planar Exposure         Limit (GWd/MTU)         (kW/ft) 0.00         9.57 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 15.43        11.16 15.99        11.16 16.53        11.16 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 26  The GE14 MAPLHGR limits presented in this COLR are a composite set of limits based on the most limiting MAPLHGR limits from each lattice.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                           Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                Page 36, Revision 0 Table 22 27 GE14 Steady-State MAPLHGRss Limits GE14-P1ODNAB429-18GZ-10OT-150-T-2661 (only)
Average Planar Exposure         Limit (GWd/MTU)        (kW/ft) 0.00        8.89 1.10        9.05 2.20        9.16 3.31        9.29 4.41        9.43 5.51        9.55 6.61        9.68 7.72        9.81 8.82        9.94 9.92       10.08 11.02       10.23 12.13       10.28 13.23       10.31 14.33       10.34 15.43       10.37 15.99       10.39 16.53       10.41 18.74       10.49 21.09       10.53 22.05       10.55 27.56       10.35 33.07         9.89 38.58         9.43 44.09          8.95 49.60         8.45 55.12         7.92 60.63         5.83 62.51         4.97 27 The GE14 MAPLHGR limits presented in this COLR are a composite set of limits based on the most limiting MAPLHGR limits from each lattice.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                           Design Calc. No. 11B21-1287 B1C17 Core Operating Limits Report                                                Page 37, Revision 0 Table 23 28 GEl4 Steady-State MAPLHGRss Limits GE14-P 1ODNAB437-12G6.0-10OT-150-T-2662 (only)
Average Planar Exposure         Limit (GWd/MTU)         (kW/ft) 0.00         9.06 1.10         9.20 2.20         9.31 3.31         9.43 4.41         9.55 5.51         9.68 6.61         9.81 7.72         9.95 8.82        10.09 9.92        10.23 11.02        10.38 12.13        10.45 13.23        10.48 14.33        10.51 15.43        10.54 16.00        10.55 16.53        10.56 18.74        10.56 21.09        10.49 22.05        10.47 27.56        10.20 33.07          9.87 38.58          9.42 44.09          8.95 49.60          8.45 55.12          7.91 60.63          5.56 62.02          4.91 28  The GE14 MAPLHGR limits presented in this COLR are a composite set of limits based on the most limiting MAPLHGR limits from each lattice.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                           Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                Page 38, Revision 0 Table 24 29 GEl4 Steady-State MAPLHGRss Limits GE14-P1ODNAB407-16GZ-10OT-150-T-2853 (only)
Average Planar Exposure          Limit (GWd/MTU)         (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 15.43        11.05 16.00        11.05 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 29  The GE14 MAPLHGR limits presented in this COLR are a composite set of limits based on the most limiting MAPLHGR limits from each lattice.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                           Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                Page 39, Revision 0 Table 25 30 GEl4 Steady-State MAPLHGRss Limits GE1 4-P1 ODNAB425-18GZ-1 OOT-1 50-T-2854 (only)
Average Planar 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 16.53        10.37 18.74        10.44 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 30  The GE14 MAPLHGR limits presented in this COLR are a composite set of limits based on the most limiting MAPLHGR limits from each lattice.

*Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                 Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                      Page 40, Revision 2 Table 26 31 32 GEl4 Power-Dependent MAPFACp Multipliers '
EOOS          Power                 GE14 Condition     (% rated)             MAPFACp 100.0                 1.00 50.0                 0.73 Base Case                     > 65%F        - 65%F Operation        50.0          0.62          0.72 (includes FHOOS)      26.0          0.53          0.60 26.0          0.43          0.49 23.0          0.41          0.45 100.0                 1.00 50.0                 0.73 TBVOOS                       > 65%F        _ 65%F 50.0          0.62          0.72 (includes FHOOS)      26.0          0.53          0.60 26.0          0.42          0.48 23.0          0.40          0.44 I
31  Multipliers valid for all SCRAM insertion times and all core average exposure ranges.
32  The GE14 power-dependent and flow-dependent multipliers are capped at 0.80 when in SLO. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                           Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                Page 41, Revision 0 Table 27 33 GEl4 Flow-Dependent MAPFACf Multipliers Core Flow               GE14
(% rated)             MAPFACf 0.0                 0.56 31.0                  0.56 80.0                  1.00 107.0                  1.00 33  The GE14 power-dependent and flow-dependent multipliers are capped at 0.80 when in SLO. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                                          Design Calc. No. 1B21-1287 B1 C1 7 Core Operating Limits Report                                                                             Page 42, Revision 0 Figure 1 Stability Option III Power/Flow Map OPRM Operable, Two Loop Operation, 2923 MWt I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum  Maximum (MELLL)    (1CF)
Core      Core 110.0                                                                                                         Power      Flow      Flow
                                                                                                                   %       M1lbs/r  Mlbs/hr 100       76.19     80.47 99       75.04     80.47 100.0                                                                                                           98       73.89 72.75 80.47 30.47 97 96       71.61     80.47 95       70.49     80.47 94       69.36     80.47 90.0                                                                                                           93       68.25     80.47 92       67.13     80.47 91       66.03     80.47 90       64.93     80.47 80.0                                                                                                           89       63.83     80.47 88       62.74     80.47 87       61.66     80.51 70.0  1+                                                                                                       86 85 84 60.58 59.50 58.43 80.60 80.69 80.79 83       57.37     80.90 82       56.31     81.05 o   60.0                                                                                                           81       55.25     81.21 80       54.20     81.36 79       53.16     81.51 78       52.12     81.67 50.0                                                                                                           77       51.08     81.82 76       50.05     81.98 75       49.02     82.13 74       48.00     82.29 40.0                                                                                                           73       46.98     82.44 72       45.96     82.60 71       44.95     82.75 70       43.94     82.91 30.0                                                                                                           69 68 42.94 41.94 83.06 83.22 67       40.95     83.37 66       39.96     83.52 20.0                                                                                                           65 64 38.97 37.99 83.68 83.83 63       37.01     83.99 62       36.04     84.14 10.0                                                                                                           61 60 35.06 34.10 84.30 84.45 59       33.13     84.61 58       32.17     84.70 0.0 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  Mlbslhr Core Flow 0      10       20      30      40      50        60      70        80     90      100     110     120  % Core Flow

==Reference:==
0B21-1015, Revision 7

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                                         Design Calc. No. 1B21-1287 B1C1 7 Core Operating Limits Report                                                                             Page 43, Revision 0 Figure 2 Stability Option III Power/Flow Map OPRM Inoperable, Two Loop Operation, 2923 MWt 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 o  60.0 50.0 40.0 30.0 20.0 10.0 0.0 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   % Core Flow

==Reference:==
0B21-1015, Revision 7

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                                          Design Calc. No. 1B21-1287 B1C1 7 Core Operating Limits Report                                                                              Page 44, Revision 0 Figure 3 Stability Option III Power/Flow Map OPRM Operable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum   Maximum (MELLL      tICF)
Core       Core 110.0                                                                                                          Power     Flow       Flow Mlbs/hr   Mlbs/hr 100      76.19     80.47 99      75.04     80.47 100.0                                                                                                            98      73.89     80.47 97      72 75     80.47 96      71.61     80.47 95      70.49     80.47 90.0                                                                                                            94      69.36     80.47 93      68.25     80.47 92      67.13     80.47 91      66.03     80.47 80.0                                                                                                            90      64.93     80.47 89      63.83     80.47 88      62.14     80.47 87      61.66     80.51 70.0                                                                                                            86 85 60.58 59.50 80.60 80.69 84      58.43     80.79 83      57.37     80.90 o  60.0                                                                                                            82      56.31     81.05 81      55.25     81.21 80      54.20     81.36 79      53.16     81.51 78      52.12     81.67 50.0                                                                                                            77      51.08     81A82 76      50.05     81.98 75      49.02     82.13 74      4&00      82.29 40.0                                                                                                            73      46.98     82.44 72      45.96     82.60 71      44.95     82.75 70      43.94     82.91 30.0                                                                                                            69      42.94     83o06 68      41.94     83.22 67       40.95     83.37 66      39.96     83.52 20.0                                                                                                            65      38.97     83.68 64      37.99     83.83 63      37.01     83.99 62      36.04     84.14 10.0                                                                                                            61      35.06     84.30 60      34.10     84.45 59      33.13     84.61 58      32.17     84.70 0.0 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  Mlbslhr 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 Calc. No. 1B21-1287 B1C17 Core Operating Limits Report                                                                               Page 45, Revision 0 Figure 4 Stability Option III Power/Flow Map OPRM Inoperable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum  Maximum (MELLL)    (ICF)
Core      Core 110.0                                                                                                          Power      Flow      Flow Mibs/hr  Mtbih 100       76.19    80.47 99       75.04    80.47 100.0                                                                                                            98       73.89    80.47 97       72.75    80.47 96       71.61    80.47 95       70.49    80.47 90.0                                                                                                            94       69.36    80.47 93       68.25    80.47 92       67.13    80.47 91       66.03    80.47 80.0                                                                                                            90       64.93    80.47 89       63.83    80.47 88       62.74    80.47 87       61.66    80.51 70.0                                                                                                            86 85 60.58 59.50 80.60 80.69 84       58.43    80.79 83       57.37    80.90 82       56.31    81.05 o  60.0                                                                                                            81       55.25    81.21 80       54.20    81.36 79       53.16    81.51 78       52.12    81.67 50.0                                                                                                            77       51.08    81.82 76       s0.05    81.98 75       49.02    82.13 74       48.00    82.29 40.0                                                                                                            73       46.98    82.44 72       45.96    82.60 71       44.95    82.75 70       43.94    82.91 30.0                                                                                                            69       42.94    83.06 68       41'94    83.22 67       40'95    83.37 66       39.96    83.52 20.0                                                                                                            65       38.97    83.68 64       37.99    83.83 63       37.01    83.99 62       36.04    84.14 10.0                                                                                                            61 60 35.06 34.10 84.30 84.45 59       33.13    84.61 58       32.17    84.70 U.U 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   % Core Flow

==Reference:==
0B21-1015, Revision 7

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis                                                          Design CaIc. No. 1B21-1287 B1 C1 7 Core Operating Limits Report                                                                             Page 46, Revision 0 Figure 5 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 Minimum  Maximum (MELLL)     (1CF) 110.0                      i  T I                                                                              Power Core Flow Core Flow
_%        Mlbs/hr   Mlbs/b 100     76.19      80.47 99      75.04      80.47 100.0                                                                                                            98      73.89      80.47 97      72.75      80.47 96      71.61      80.47 95      70.49      80.47 90.0                                                                                                           94      69.36      80.47 93      68.25      80.47 92      67.13      80.47 91      66.03      80.47 80.0                                                                                                           90      64.93      80.47 89      63.83      80.47 88      62.74      80.47 87      61.66      80.51 70.0                                                                                                           86      60.58      80.60 85      59.50      80.69 84      58.43      80.79 83      57.37      80.90 82      56.31      81.05 o   60.0                                                                                                           81      55.25      81.21 80      54.20      81.36 79      53.16      81.51 50.0                                                                                                           78 77 52.12 51.08 81.67 81.82 76      50.05      81.98 75      49.02      82.13 74      48.00      82.29 40.0                                                                                                           73      46.98      82.44 72      45.96      82.60 71      44.95      82.75 70      43.94      82.91 30.0                                                                                                           69      42.94      83.06 68      41.94      83.22 67      40.95      83.37 66      39.96      83.52 20.0                                                                                                           65      38.97      83.68 64      37.99      83.83 63      37.01      83.99 62      36.04      84.14 10.0                                                                                                           61      35.06      84.30 60      34.10      84.45 59      33.13      84.61 58      32.17      84.70 0.0 0.0    7.7      15.4    23.1   30.8    38.5     46.2      53.9     61i.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                                                          Design Caic. No. 1B21-1287 B1 C1 7 Core Operating Limits Report                                                                             Page 47, Revision 0 Figure 6 Stability Option III Power/Flow Map OPRM Inoperable, FWTR, 2923 MWt I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum  Maximum (MELLL)    (tCF)
Core     Core 110.0                                                                                                         Power      Flow      Flow 0       Mlbs/hr  Mlbilhr 100       76.19     80.47 99       75.04     80.47 100.0                                                                                                           98       73.89     80.47 97       72.75     80.47 96       71.61     80.47 95       70.49     80.47 90.0                                                                                                           94       69.36     80.47 93       68.25     80.47 92       67.13    80.47 91       66.03    80.47 80.0                                                                                                           90       64.93    80.47 89       63.83     80.47 88       62.74     80.47 87       61.66     80.51 70.0                                                                                                           86 85 60.58 59.50 80.60 80.69 60.0                                                                                                           84 83 58.43 57.37 80.79 80.90 82       56.31     81.05 81       55.25     81.21 80       54.20     81.36 79       53.16     81.51 50.0                                                                                                           78 77 52.12 51.08 81.67 81.82 76       50.05     81.98 75       49.02     82.13 74       48.00    82.29 40.0                                                                                                           73       46.98     82.44 72       45.96     82.60 71       44.95     82.75 70       43.94     82.91 30.0                                                                                                           69       42.94     83.06 68       41.94     83.22 67       40.95     83.37 66       39.96     83.52 20.0                                                                                                           65       38.97     83.68 64       37.99     83.83 63       37.01     83.99 62       36.04     84.14 10.0                                                                                                           61       35.06     84.30 60       34.10    84.45 59       33.13     84.61 58       32.17    84.70 0.0 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   % Core Flow

==Reference:==
0B21-1015, Revision 7}}