BSEP 08-0097, Cycle 17 Core Operating Limits Report, Revision 1

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Cycle 17 Core Operating Limits Report, Revision 1
ML082190752
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 07/30/2008
From: Leich P
Progress Energy Carolinas, Progress Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 08-0097
Download: ML082190752 (51)
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Text

Progress Energy JUL 30 2008.

SERIAL: BSEP 08-0097 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 Unit 1 Cycle 17 Core Operating Limits Report, Revision 1 Ladies and Gentlemen:

Enclosed is Revision 1 of the Core Operating Limits Report (COLR) for the Brunswick Steam Electric Plant (BSEP), Unit 1, Cycle 17 operation. Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., is providing the enclosed Revision I 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 31, 2008. The enclosed revision of the COLR supersedes the Revision 0 report previously submitted by letter dated April 22, 2008, (i.e., ADAMS Accession Number ML081200893).

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, Philip A. Leich Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461 62(

Document Control Desk BSEP 08-0097 / Page 2 WRM/wrm

Enclosure:

Brunswick Unit 1, Cycle 17 Core Operating Limits Report July 2008 Revision 1 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 (Electronic Copy Only)

ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

BSEP 08-0097 Enclosure Brunswick Unit 1, Cycle 17 Core Operating Limits Report July 2008, Revision I

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Calc. No. 1B21-1287 BIC17 Core Operating Limits Report Page 1, Revision 1 BRUNSWICK UNIT 1, CYCLE 17 CORE OPERATING LIMITS REPORT July 2008 p

Westmoreland, Gregory Prepared By: 2008.07.24 13:55:47 -04'00' Greg Westmoreland BWR Fuel Engineering - Lead Engineer Pribyl, David; Verified By: 2008.07.24*14:40:19 -04'00" David Pribyl BWR Fuel Engineering - Senior Engineer Tom Dresser Supervisor Approval k 2008.07.24 16:24:28 -04'00'1 ,

Approved By:

Michael Blom BWR Fuel Engineering - Supervisor

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design CaIc. No. 1B21-1287 B1C17 Core Operating Limits Report Page 2, Revision 1 LIST OF EFFECTIVE PAGES Page(s) Revision 1-2 1 3-7 0 8 1 9-13 0 14 1 14a 1 15-47 0 This document consists of 48 total pages.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report Page 3, Revision 0 TABLE OF CONTENTS Subiect PaQe.

Cover ........ ........................................................... . . ................................................................ 1 List of Effective Pages ........................................................................................................................ 2 Table of Contents ........ .... ................................................ 3 List of Tables ........... ....................................... ................................................................. 4 L ist o f F ig u re s ..................................................................................................................................... 5 Nomenclature ..................................................................................................................................... 6 Introduction and Summary .......................................................................................................... ...... 88 APLHGR Lim its .................................................................................................................................. 9 MCPR Limits.......................................................... ......................................................................... 9 LHGR Limits ....................................................................................................................... ..... 10 PBDA Setpoints ............................................................................................................................. 11 RBM Setpoints .................... .................................................................................................. ....... 12 Equipment Out-of-Service ................................................................................................................ 12 Single Loop Operation ........ ................................................ 12 Inoperable Main Turbine Bypass System ..................................................................................... 13 Feedwater Tem perature Reduction ......................................... ................................................... 13 References ................ ................................................ 14

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design CaIc. No. 1821-1287 B1C17 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 may change from cycle to cycle.

LIST OF TABLES Table Title Page Table 1: R BM System Setpoints .............................................................................................. 15 Table 2: RBM O perability Requirem ents .................................................................................. 16 T able 3: P B D A S etpoints ....................................................................................................... . . 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: Pow er-Dependent M CPRp Lim its .................................................................................... 23 NSS Insertion Times - BOC to < MCE (FFTR/Coastdown)

Table 10: Power-Dependent MCPRp Limits ............................................................................... 24 TSSS Insertion Times - BOC to < MCE (FFTRlCoastdown)

Table 11: Flow-Dependent MCPRf Lim its ................................................................................... 25 Table 12: ATRIUM-10 Steady State LHGRss Lim its ...................................................... ................. 26 Table 13: GE14 Steady-State LHGRss 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-100T-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-P1ODNAB437-12G6.0-10OT-150-T-2662 (only)

Table 24: GE14 Steady-State MAPLHGRss Limits ..................................................................... 38 GE14-P1ODNAB407-16GZ-10OT-150-T-2853 (only)

Table 25: GE14 Steady-State MAPLHGRss Limits ..................................................................... 39 GE14-P1O0DNAB425-18GZ-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 Option III Power/Flow Map ........................................................................... 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 Option III Power/Flow Map ........................................................................... 44 OPRM Operable, Single Loop Operation, 2923 MWt Figure 4: Stability O ption III Power/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 SafetyAnalysis 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 FWTR 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 Calc. No. 1B21-1287 B1C17 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 Calc. 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.

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 Requirement TS Table 3.3.1.1-1 Function 2f Average Power Range Monitors - OPRM Upscale.

TS 3.3.1.1 LCO Condition I Alternate method to detect and suppress thermal-hydraulic instability oscillations.

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:

  • 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:

  • GEl4 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.O)0in 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.

0 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 0 selecting the appropriate limits set.

  • The MCPR limits are established such that they bound all pressurization and non-pressurization events.

e 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 (Tables 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, fuel design 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 selecting the appropriate multiplier set.
  • The original licensing basis for GE14 LHGR limits did not include a core power and core flow dependency. However, in order to be consistent with the determination of ATRIUM-1 0 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 isdetermined 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 Caic. 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 I1l. 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 is an 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 Calc. 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:

  • 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 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 CaIc. 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:

  • TBVOOS operation coincident with FHOOS is supported using the combined TBVOOS/FHOOS limits.

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 110.30F.

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>100 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.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Calc. No. 1B21-1287 B1C17 Core Operating Limits Report Page 14, Revision 1 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 1 B21-1287, "Preparation of the B1C17 Core Operating Limits Report,"

Revision 1.

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 2, October 2003.
4. ANP-2674(P), "Brunswick Unit 1 Cycle 17 Reload Safety Analysis," Revision 2, March 2008.
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 Calc. 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. 1821-1287 B1C17 Core Operating Limits Report Page 15, Revision 0 Table 1 RBM System. Setpoints1 Setpoint a, d Trip Setpoint Allowable Value Lower Power Setpoint (LPSP b) 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 (td2) < 2.0 seconds < 2.0 seconds a See Table 2 for RBM Operability Requirements.

b Setpoints in percent of Rated Thermal Power.

c Setpoints relative to a full scale reading of 125. For example, < 114.1 means

< 114.1/125.0 of full scale.

d. Trip setpoints and allowable values are based on a high power analytical setpoint of 108% (unfiltered).

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

>29% and < 90% 1.65 SLO 9%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) OLMCPR(2PT)

Setpoint (Sp) 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 B1C17 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) 29,667 Break point for exposure-dependent MCPRp limits (NEOC) 32,076 Design EOFP +basis rod patterns to 14 EFPD (EOCLB) 33,841 End of reactivity Maximum for FFTR /Coastdown 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 CaIc. No. 1B21-1287 B1C17 Core Operating Limits Report Page 19, Revision 0 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 < 50%F > 65%F < 65%F < 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.38 1.37 90.0 1.42 1.40 50.0 1.59 1.58

> 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 100.0 1.36 1.36 90.0 1.40 1.38 50.0 1.57 1.57

> 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.42 1.39 90.0 1.45 1.42 TBVOOS 50.0 1.64 1.63 and > 65%F < 65%F 5 50%F > 65%F < 65%F < 50%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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 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. 1821-1287 BIC17 Core Operating Limits Report Page 20, Revision 0 Table 6 6

Power-Dependent MCPRp Limits TSSS Insertion Times BOC to < NEOC EOOS Power ATRIUM-10 GEl4 Condition (% rated) MCPRP MCPRP 100.0 1.46 1.43 90.0 1.47 1.45 50.0 1.55 1.54 Base Case > 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.49 1.46 90.0 1.52 1.49 50.0 1.65 1.64

> 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 100.0 1.47 1.44 90.0 1.48 1.46 50.0 1.62 1.62

> 65%F  ! 65%F 5 50%F > 65%F 5 65%F < 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.50 1.47 90.0 1.53 1.50 TBVOOS 50.0 1.70 1.69 and > 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 6 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 0 Table 7 7

Power-Dependent MCPRp Limits NSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM-10 GE14 Condition (% rated) MCPRP MCPRp 100.0 1.40 1.41 90.0 1.43 1.43 50.0 1.53 1.53 Base Case > 65%F < 65%F < 50%F > 65%F < 65%F 5 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.43 1.43 90.0 1.46 1.45 50.0 1.62 1.61

> 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 100.0 1.41 1.42 90.0 1.44 1.44 50.0 1.57 1.57

> 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.45 1.48 90.0 1.48 1.51 TBVOOS 50.0 1.64 1.63 and > 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 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 22, Revision 0 Table 8 8

Power-Dependent MCPRp Limits TSSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM-10 GE14 Condition (% rated) MCPRP MCPRP 100.0 1.46 1.46 90.0 1.47 1.47 50.0 1.55 1.54 Base Case > 65%F < 65%F < 50%F > 65%F S 65%F S 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.49 1.48 90.0 1.52 1.50 50.0 1.65 1.64

> 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 100.0 1.47 1.47 90.0 1.48 1.49 50.0 1.62 1.62

> 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.50 1.54 90.0 1.53 1.55 TBVOOS 50.0 1.70 1.69 and > 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 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 23, Revision 0 Table 9 Power-Dependent MCPRp Limits 9 NSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS 10 Power ATRIUM-10 GE14 Condition (% rated) MCPRP MCPRP 100.0 1.45 1.44 90.0 1.45 1.44 Base Case 50.0 1.57 1.57 Operation > 65%F < 65%F < 50%F > 65%F < 65%F < 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.46 1.48 90.0 1.48 1.51 50.0 1.70 1.65 TBVOOS > 65%F < 65%F < 50%F > 65%F 5 65%F < 50%F (includes EHOOS) 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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 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 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 0 Table 10 Power-Dependent MCPRP Limits11 TSSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS12 Condition Power

(% rated) ATRIUM-10 MCPRP GE14 MCPRP 100.0 1.48 1.47 90.0 1.48 1.49 Base Case 50.0 1.62 1.62 Operation > 65%F < 65%F < 50%F > 65%F 5 65%F 5 50%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 2.47 2.63 2.50 2.45 23.0 2.73 2.60 2.55 2.76 2.61 2.54 100.0 1.50 1.54 90.0 1.53 1.55 50.0 1.70 1.69 TBVOOS > 65%F < 65%F < 50%F > 65%F < 65%F < 50%F (includes 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 2.76 3.13 2.90 2.72 23.0 3.31 3.14 3.00 3.30 3.14 2.95 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 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 GE14 Steady-State LHGRss Limits 15 Peak GEl4 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 0 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 5 65%F < 50%F Operation 50.0 0.67 0.77 --

26.0 0.57 0.62 --

26.0 0.53 0.57 0.60 23.0 0.51 0.55 0.59 100.0 0.99 80.0 0.96 50.0 0.87

> 65%F < 65%F < 50%F TBVOOS 50.0 0.67 0.77 --

26.0 0.57 0.62 --

26.0 0.44 0.49 0.55 23.0 0.42 0.46 0.50 100.0 1.00 80.0 0.99 50.0 0.91

> 65%F < 65%F < 50%F 50.0 0.67 0.77 --

26.0 0.57 0.62 --

26.0 0.53 0.57 0.60 23.0 0.51 0.55 0.59 100.0 0.99 80.0 0.95 50.0 0.86 TBVOOS > 65%F < 65%F < 50%F and aHd 50.0 0.67 0.77 --

26.0 0.57 0.62 --

26.0 0.44 0.49 0.55 23.0 0.42 0.46 0.50 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. 1821-1287 B1C17 Core Operating Limits Report Page 29, Revision 0 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 0.94 50.0 0.93 Base Case > 65%F < 65%F 5 50%F Operation 50.0 0.65 0.76 --

26.0 0.57 0.62 --

26.0 0.53 0.57 0.60 23.0 0.51 0.55 0.59 100.0 0.95 80.0 0.93 50.0 0.87

> 65%F <65%F < 50%F 50.0 0.65 0.76 --

26.0 0.57 0.62 --

26.0 0.44 0.49 0.55 23.0 0.42 0.46 0.50 100.0 0.95 80.0 0.94 50.0 0.90

> 65%F < 65%F 5 50%F 50.0 0.65 0.76 --

26.0 0.57 0.62 --

26.0 0.53 0.57 0.60 23.0 0.51 0.55 0.59 100.0 0.95 80.0 0.93 TBVOOS 50.0 0.85 and > 65%F < 65%F and < 50%F 0.65 0.76 --

EHOOS 50.0 26.0 0.57 0.62 --

26.0 0.44 0.49 0.55 23.0 0.42 0.46 0.50 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 0 Table 16 18 ATRIUM-i 0 Power-Dependent LHGRFACp Multipliers NSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS 19 Power ATRIUM-10 Condition (% rated) LHGRFACp 100.0 1.00 80.0 0.97 Base Case 50.0 0.91 Operation > 65%F < 65%F < 50%F 50.0 0.67 0.76 --

(includes FHOOS) 26.0 0.57 0.62 --

26.0 0.53 0.57 0.60 23.0 0.51 0.55 0.59 100.0 0.97 80.0 0.92 50.0 0.86 TBVOOS > 65%F < 65%F < 50%F 50.0

5. 0.67 067.6 0.76 --

(includes FHOOS) 26.0 0.57 0.62 --

26.0 0.44 0.49 0.55 1 23.0 0.42 0.46 0.50 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.

19 FFTR 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 0 Table 17 ATRIUM-10 Power-Dependent LHGRFACP Multipliers 20 TSSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS 2 1 Power ATRIUM-10 Condition (% rated) LHGRFACP 100.0 1.00 80.0 0.94 Base Case 50.0 0.89 Operation > 65%F < 65%F < 50%F 50.0 0.65 0.74 --

(includes FHOOS) 26.0 0.57 0.62 --

26.0 0.53 0.57 0.60 23.0 0.51 0.55 0.59 100.0 0.95 80.0 0.91 50.0 0.85 TBVOOS > 65%F < 65%F < 50%F (includes FHOOS) 50.0 0.65 0.74 --

26.0 0.57 0.62 --

26.0 0.44 0.49 0.55 23.0 0.42 0.46 0.50 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.

21 FFTR 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 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 ATRIUM-10 Steady-State MAPLHGRss Limits 24 Average Planar Exposure (GWd/MTU) MAPLHGR (kW/ft) 0.0 12.5 15.0 12.5 67.0 7.3 23 ATRIUM-10 MAPLHGR limits do not have a power or flow dependency. Thus, the ATRIUM-10 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 Calc. No. 1B21-1287 B1C17 Core Operating Limits Report Page 34, Revision 0 Table 20 25 GE14 Steady-State MAPLHGRss Limits GE14-P1ODNAB416-17GZ-10OT-150-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 GE14 Steady-State MAPLHGRss Limits GE 14-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 GE 14-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. 1B21-1287 BIC17 Core Operating Limits Report Page 37, Revision 0 Table 23 28 GE14 Steady-State MAPLHGRss Limits GE14-P1ODNAB437-12G6.0-10OT-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 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 GE14 Steady-State MAPLHGRss Limits GE14-P1ODNAB407-16GZ-100T-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 GE14 Steady-State MAPLHGRss Limits GE14-P1ODNAB425-18GZ-100T-150-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 o 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 0 Table 26 31 GE14 Power-Dependent MAPFACp Multipliers 32 EOOS Power GE14 Condition (% rated) MAPFACP 100.0 1.00 50.0 0.73 Base Case > 65%F < 65%F < 50%F Operation 50.0 0.62 0.72 --

(includes FHOOS) 26.0 0.53 0.60 --

26.0 0.43 0.49 0.56 23.0 0.41 0.45 0.51 100.0 1.00 50.0 0.73 TBVOOS > 65%F < 65%F 5 50%F 50.0 0.62 0.72 --

(includes FHOOS) 26.0 0.53 0.60 --

26.0 0.42 0.48 0.53 23.0 0.40 0.44 0.49 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 GE14 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 BIC17 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 1 120.0 Minimum Maximum (MELLL) (lCF)

Core Core 110.0 Power Flow Flow 100 76819 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 93 69.36 68.25 80.47 80.47 92 67.13 80.47 91 66.03 80.47 80.0 90 89 64.93 63.83 80.47 80.47 88 62.74 80.47 87 61.66 80.51 86 60.58 80.60 70.0 85 59.50 80.69 84 58.43 80.79 83 57.37 80.90 82 56.31 81.05 IL 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.S2 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 um I L'o -d L- Pump Spee J=iiw Pow:Urk*"- 58 32.17 84.70 I

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

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Caic. No. 1B21-1287 B1C17 Core Operating Limits Report Page 43, Revision 0 Figure 2 Stability Option III Power/Flow Map OPRM Inoperable, Two Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 1 120.0 Minimum Maximum (MELLL) CICF)

Core Core 110.0 Power Flow Flow

% Nibs/hr Mls/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 62.74 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 I

CL 60.0 82 81 56.31 55.25 81.05 81.21 80 54.20 81.36 79 53.16 81.51 50.0 78 77 52.12 51.06 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 82.80 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 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

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Caic. No. 1 B21-1287 B1C17 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 rMELLL) ( ICF)

Core Core 110.0 Power Flow Flow 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 89 64.93 63.83 80.47 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 CL 60.0 81 55.25 81.21 at 80 54.20 81.36 79 53.16 81.51 78 52.12 81.67 50.0 77 51.06 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 60 35.06 34.10 84.30 84.45 59 58 33.13 32.17 84.61 84.70 I

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

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design CaIc. 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 I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 Minimum Maximum SMELLL1 (ICFP Core Core 110.0 Power Flow Flow

% Ml1shr blUs/h 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 89 64.93 63.83 80.47 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 9L 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 30.0f 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 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 %CoreFlow

Reference:

0B21-1015, Revision 7

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design CaIc. No. 1B21-1287 BIC17 Core Operating Limits Report Page 46, Revision 0 Figure 5 Stability Option III Power/Flow Map OPRM Operable, FWTR, 2923 MWt I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 1 120.0 Minimum Maximum (MELLL) (ICF)

Core Core 110.0 Power Flow Flow M MIbs/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 62.74 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 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 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

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Calc. No. 1 B21-1287 B1C17 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 Specifeition 3.3.1.1 and the Technical Requirements Manual Specification 3.3 1 120.0 Minimum Maximum (MELLL) (ICF)

Core Core 110.0 Power Flow Flow

% Mabshr Mlbshr 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 89 64.93 63.83 80.47 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 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 42.94 83.06 68 41.94 83.22 67 40.95 83.37 66 39.96 83.52 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 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

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