ML12100A086

Cycle 19, Core Operating Limits Report, March 2012

ML12100A086
Person / Time
Site:	Brunswick
Issue date:	03/26/2012
From:	Westmoreland G Progress Energy Carolinas
To:	Office of Nuclear Reactor Regulation
References
BSEP 12-0040
Download: ML12100A086 (44)

Text

BSEP 12-0040 Enclosure 1 Brunswick Unit 1, Cycle 19 Core Operating Limits Report, March 2012 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 1, Revision 0 BRUNSWICK UNIT 1, CYCLE 19 CORE OPERATING LIMITS REPORT March 2012 Prepared By: Verified By: Westmoreland, Gregory 2012.03.26 09:32:21 -04'00'Gregory R. Westmoreland BWR Fuel Engineering loppolo, Crystian 2012.03.26 10:01:13 -04'00'Crystian J. loppolo BWR Fuel Engineering Thomas, Roger 2012.03.27 08:07:49 -04'00'Roger L. Thomas BWR Fuel Engineering

-Supervisor Approved By:

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B1C19 Core Operating Limits Report Design Calc. No. 1 B21-0649 Page 2, Revision 0 LIST OF EFFECTIVE PAGES Page(s)1-39 Revision 0 This document consists of 39 total pages.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design CaIc. No. 1B21-0649 B1C19 Core Operating Limits Report Page 3, Revision 0 TABLE OF CONTENTS Subiect Page Cover ......................................................

List of Effective Pages .......................................................................................................................

2 T a b le o f C o n te n ts ...............................................................................................................................

3 L is t o f T a b le s ...........................................

• ...............................................................................

4 L is t o f F ig u re s ..................................

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5 N o m e n c la tu re ....................................................................................................................................

6 Introduction and Summary ..................................................................................................................

8 A P L H G R L im its ...................................................................................................................................

9 M C P R L im its .......................................................................................................................................

9 L H G R L im its .....................................................................................................................

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1 0 P B D A S e tp o in ts ................................................................................................................................

1 0 R B M S e tp o in ts ..................................................................................................................................

1 1 Equipment Out-of-Service

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12 Single Loop Operation

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12 Inoperable Main Turbine Bypass System ....................................................................................

13 Feedwater Tem perature Reduction

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13 R e fe re n c e s .......................................................................................................................................

1 4 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Calc. No. 1 B21-0649 B1C19 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 T able 1: R B M S ystem S etpoints .................................................

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16 Table 2: RBM O perability Requirem ents ................................................................................

17 T a b le 3 : P B D A S e tp o ints .....................

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18 Table 4: Exposure Basis for Brunswick Unit 1 Cycle 19 Transient Analysis .............................

19 Table. 5: Power-Dependent M CPRP Lim its ..........................

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20 NSS Insertion Times -BOC to < NEOC Table 6: Pow er-Dependent M C PRP Lim its ................................................................................

21 TSSS Insertion Times -BOC to < NEOC Table 7: Power-Dependent MCPRP Limits ... .................

22 NSS Insertion Times -BOC to < EOCLB Table 8: Power-Dependent M C PRP Lim its ...............................................................................

23 TSSS Insertion Times -BOC to < EOCLB Table 9: Power-Dependent M C PRP Lim its ...............................................................................

24 NSS Insertion Times -BOC to < MCE (FFTR/Coastdown)

Table 10: Power-Dependent MCPRP Limits ........................................

25 TSSS Insertion Times -BOC to < MCE (FFTR/Coastdown)

Table 11: Flow -Dependent M C PRf Lim its ..................................................................................

26 Table 12: AREVA Fuel Steady State LHGRss Limits .................................................................

27 Table 13: AREVA Fuel Power-Dependent LHGRFACp Multipliers

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28 NSS Insertion Times -BOC to < EOCLB Table 14: AREVA Fuel Power-Dependent LHGRFACp Multipliers

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29 TSSS Insertion Times -BOC to < EOCLB Table 15: AREVA Fuel Power-Dependent LHGRFACO Multipliers

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30 NSS Insertion Times -BOC to < MCE (FFTR/Coastdown)

Table 16: AREVA Fuel Power-Dependent LHGRFACp Multipliers

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31 TSSS Insertion Times -BOC to < MCE (FFTR/Coastdown)

Table 17: AREVA Fuel Flow-Dependent LHGRFACf Multipliers

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32 Table 18: AREVA Fuel Steady-State MAPLHGRss Limits .........................................................

33 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Calc. No. 1B21-0649 B1C19 Core Operating Limits Report Page 5, Revision 0 LIST OF FIGURES Figure Title or Description Page Figure 1: Stability O ption III Power/Flow M ap ............................................................................

34 OPRM Operable, Two Loop Operation, 2923 MWt Figure 2: Stability O ption III Power/Flow M ap ..........................................................................

35 OPRM Inoperable, Two Loop Operation, 2923 MWt Figure 3: Stability Option III Power/Flow Map ..........................

36 OPRM Operable, Single Loop Operation, 2923 MWt Figure 4: Stability O ption III Power/Flow M ap ...........................................................................

37 OPRM Inoperable, Single Loop Operation, 2923 MWt Figure 5: Stability O ption III Pow er/Flow M ap ...........................................................................

38 OPRM Operable, FWTR, 2923 MWt Figure 6: Stability O ption III Pow er/Flow M ap ...........................................................................

39 OPRM Inoperable, FWTR, 2923 MWt Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B1C19 Core Operating Limits Report NOMENCLATURE APLHGR Average Planar Linear Heat Generation Rate APRM Average Power Range Monitor (Subsystem)

ARTS APRM/RBM Technical Specification Design CaIc. No. 1B21-0649 Page 6, Revision 0 BOC BSP BWROG CAVEX COLR CRWE DIVOM EFPD EOC EOCLB EOFP EOOS F FHOOS FFTR FWTR HCOM HPSP HTSP ICF IPSP ITSP Beginning of Cycle Backup Stability Protection BWR Owners Group Core Average Exposure Core Operating Limits Report Control Rod Withdrawal Error Delta CPR Over Initial MCPR Versus Oscillation Magnitude Effective Full Power Day End of Cycle End of Cycle Licensing Basis End of Full Power Equipment Out of Service Flow (Total Core)Feedwater Heater Out of Service Final Feedwater Temperature Reduction Feedwater Temperature Reduction Hot Channel Oscillation Magnitude High Power Set Point High Trip Set Point Increased Core Flow Intermediate Power Set Point Intermediate Trip Set Point LCO LHGR LHGRss LHGRFAC LHGRFACf LHGRFACp LPRM LPSP LTSP MAPLHGR MAPLHGRss MAPFAC MAPFACf MAPFACP MAPFACSLO Limiting Condition of Operation Linear Heat Generation Rate Steady-State Maximum Linear Heat Generation Rate Linear Heat Generation Rate Factor Flow-Dependent Linear Heat Generation Rate Factor Power-Dependent Linear Heat Generation Rate Factor Local Power Range Monitor (Subsystem)

Low Power Set Point Low Trip Set Point Maximum Average Planar Linear Heat Generation Rate Steady-State Maximum Average Planar Linear Heat Generation Rate Maximum Average Planar Linear Heat Generation Rate Factor Flow-Dependent Maximum Average Planar Linear Heat Generation Rate Factor Power-Dependent Maximum Average Planar Linear Heat Generation Rate Factor Maximum Average Planar Linear Heat Generation Rate Factor when in SLO Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Calc. No. 1B21-0649 B1C19 Core Operating Limits Report Page 7, Revision 0 NOMENCLATURE (continued)

MCE Maximum Core Exposure MCPR Minimum Critical Power Ratio MCPRf Flow-Dependent Minimum Critical Power Ratio MCPRp Power-Dependent Minimum Critical Power Ratio 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 NRC Nuclear Regulatory Commission 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)

RFVVT Reduced Feedwater Temperature RPT Recirculation Pump Trip 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 B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 8, Revision 0 I CAUTION References to COLR Figures or Tables should be made using titles only; Figure and Table numbers may. change from cycle to cycle.I Introduction and Summary The Brunswick Unit 1, Cycle 19 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 LC Condtio I 1 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* MCPR TS 5,6.5.a* LHGR 9 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 1-21) 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 30 and is based on analysis results documented in References 27-29.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Calc. No. 1B21-0649 BIC19 Core Operating Limits Report Page 9, Revision 0 APLHGR Limits Steady-state MAPLHGRss limits are provided for AREVA Fuel (Table 18). These steady-state MAPLHGRss limits must be modified as follows:* AREVA Fuel MAPLHGR limits do not have a power or flow dependency.

Power-dependent MAPFACp multipliers and flow-dependent MAPFACf multipliers with a constant value of 1.0 under all conditions have been assigned to AREVA Fuel.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 .)rmin MAPLHGR LimitSLO = MAPLHGRss x (MAPFACP, MAPFACf, MAPFACSLo)m0n where MAPFACSLO

= 0.85 for ATRIUM-10 fuel= 0.80 for ATRIUM 1OXM 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.

MCPR Limits The MCPR limits presented in Tables 5 through 11 support any TLO SLMCPR value < 1.11 and any SLO SLMCPR value < 1.12. The SLMCPR values listed in Technical Specification 2.1.1.2 are less than or equal to these values.* 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 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 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design CaIc. No. 1B21-0649 B1C19 Core Operating Limits Report Page 10, Revision 0 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 AREVA Fuel (Table 12). These steady-state LHGRss limits must be modified as follows:* AREVA Fuel LHGR limits have a core power and core flow dependency.

AREVA Fuel power-dependent LHGRFACp multipliers (Tables 13-16) and flow-dependent LHGRFACf multipliers (Table 17) must be used to modify the steady-state LHGRss limits (Table 12) for off-rated conditions.

• AREVA Fuel 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 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.

PBDA Setpoints Brunswick Unit 1 has implemented BWROG Long Term Stability Solution Option III (OPRM) with the methodology described in Reference

23. Plant specific analysis incorporating the Option III hardware is described in Reference

24. Reload validation has been performed in accordance with Reference 19.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 (1.11) is set by the least limiting 100%P MCPRp limit (1.39) 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 19 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 in accordance with Reference

26. This code is a coupled neutronic-thermal-hydraulic three-dimensional transient model for the purpose of determining the relationship between the Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design CaIc. No. 1B21-0649 BIC19 Core Operating Limits Report Page 11, Revision 0 relative change in ACPR and the HCOM on a plant specific basis. The stability-based OLMCPRs are based upon using the most limiting ACPR calculated for a given oscillation magnitude or the generic value provided in Reference 19.In cases where the OPRM system is declared inop~erable, Backup Stability Protection (BSP) in accordance with Reference 25 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 29 to facilitate operation under Stability Option II I 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 28.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-217345217345which 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.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 22). These setpoints will ensure the power-dependent MCPR limits will provide adequate protection against violation of the SLMCPR during a postulated CRWE event. Reference 27 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.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design Calc. No. 11B21-0649 B1C19 Core Operating Limits Report Page 12, Revision 0 Equipment Out-of-Service Brunswick Unit 1, Cycle 19 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 all the items OOS below. These conditions are general analysis assumptions used to ensure conservative analysis results and were not meant to define specific EOOS conditions beyond those already defined in Technical Specifications.

• Any 1 inoperable SRV* 1 inoperable TBV (Note that for TBVOOS and TBVOOS/FHOOS all 4 TBVs are assumed inoperable)

• 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 19 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: 0 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 Function 2.b: Average Power Range Monitors Simulated Thermal Power -High Allowable Value).* When in SLO, Figures 3 and 4 implement the corrective action for AR-217345217345which restricts reactor power to no more than 50% RTP 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. 1 B21-0649 B1C19 Core Operating Limits Report Page 13, Revision 0 Inoperable Main Turbine Bypass System Brunswick Unit 1, Cycle 19 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 19 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 were 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'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 >10°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 is 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 Calc. No. 1B21-0649 BIC19 Core Operating Limits Report Page 14, Revision 0 References In accordance with Brunswick Unit 1 Technical Specification 5.6.5.b, the analytical methods for determining Brunswick Unit 1 core operating limits have been specifically reviewed and approved by the NRC and are listed as References 1 through 21.1. NEDE-24011-P-A, "GESTAR II -General Electric Standard Application for Reactor Fuel", and US Supplement, Revision 15, September 2005.2. XN-NF-81-58(P)(A) and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Revision 2, March 1984.3. XN-NF-85-67(P)(A), "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Revision 1, September 1986.4. EMF-85-74(P)

Supplement 1(P)(A) and Supplement 2(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, February 1998.5. ANF-89-98(P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs," Revision 1, May 1995.6. XN-NF-80-19(P)(A)

Volume 1 and Volume 1 Supplement 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors -Neutronic Methods for Design and Analysis," March 1983.7. 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 1986.8. EMF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2," Revision 0, October 1999.9. XN-NF-80-19(P)(A)

Volume 3, "Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description," Revision 2, January 1987.10. XN-NF-84-105(P)(A)

Volume 1 and Volume 1 Supplements 1 and 2, "XCOBRA-T:

A Computer Code for BWR Transient Thermal Hydraulic Core Analysis," February 1987.11. ANF-524(P)(A) and Supplements 1 and 2, "ANF Critical Power Methodology for Boiling Water Reactors," Revision 2, November 1990.12. ANF-913(P)(A)

Volume 1 and Volume 1 Supplements 2, 3, 4, "COTRANSA2:

A Computer Program for Boiling Water Reactor Transient Analyses," Revision 1, August 1990.13. ANF-1358(P)(A), "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Revision 3, September 2005.14. EMF-2209(P)(A), "SPCB Critical Power Correlation", Revision 3, September 2009.15. EMF-2245(P)(A), "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel," Revision 0, August 2000.16. EMF-2361(P)(A), EXEM BWR-2000 ECCS Evaluation Model," Revision 0, May 2001.17. EMF-2292(P)(A), "ATRIUMTM-10:

Appendix K Spray Heat Transfer Coefficients," Revision 0, September 2000.18. EMF-CC-074(P)(A)

Volume 4, "BWR Stability Analysis -Assessment of STAIF with Input from MICROBURN-B2," Revision 0, August 2000.19. NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application," August 1996.20. BAW-10247PA, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors," Revision 0, April 2008.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis Design CaIc. No. 11B21-0649 B1C19 Core Operating Limits Report Page 15, Revision 0 21. ANP-10298PA, "ACE/ATRIUM 1OXM Critical Power Correlation," Revision 0, March 2010.22. NEDC-31654P, "Maximum Extended Operating Domain Analysis for Brunswick Steam Electric Plant," February 1989.23. NEDO-31960-A, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology," November 1995.24. GENE-C51-00251-00-01, "Licensing Basis Hot Bundle Oscillation Magnitude for Brunswick 1 and 2," Revision 0, March 2001.25. OG02-0119-260 "Backup Stability Protection (BSP) for Inoperable Option III Solution, GE Nuclear Energy," July 17, 2002.26. BAW-10255PA, "Cycle Specific DIVOM Methodology Using the RAMONA5-FA Code," Revision 2, May 2008.27. Design Calculation 1C51-0001, "Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (1-C51-APRM i through 4 Loops and 1-C51-RBM-A and B Loops)," Revision 3, May 2004.28. Design Calculation 0B21-1015, "BNP Power/Flow Maps," Revision 7.29. ANP-3061(P), "Brunswick Unit 1 Cycle 19 Reload Safety Analysis," Revision 0, December 2011.30. BNP Design Calculation 1 B21-0649, "Preparation of the B1C19 Core Operating Limits Report," Revision 0.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis BIC19 Core Operating Limits Report Design CaIc. No. 1B21-0649 Page 16, Revision 0 Table 1 RBM System Setpoints' Setpoint a, d [ Setpoint Value Allowable Value Lower Power Setpoint (LPSP b) < 27.7 < 29.0 Intermediate Power Setpoint (IPSP ) < 62.7 < 64.0 High Power Setpoint (HPSP b) < 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) 0 seconds < 2.0 seconds a See Table 2 for RBM Operability.Requir6ements.

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 HTSP Analytical Limit of 107.4 with RBM filter.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 B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 17, Revision 0 Table 2 RBM Operability Requirements 2 IF the following conditions are met, THEN RBM Not Required Operable Thermal Power (% rated)MCPR>29% and < 90% 1.75 SLO 9%1.75 SLO>90% >1.53 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 B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 18, Revision 0 Table 3 PBDA Setpoints 3 Amplitude Trip OLMCPR(SS)

OLMCPR(2PT)

Setpoint (SP)1.05 1.24 1.26 1.06 1.25 1.28 1.07 1.27 1.30 1.08 1.29 1.32 1.09 1.31 1.34 1.10 1.33 1.36 1.11 1.35 1.38 1.12 1.37 1.40 1.13 1.39 1.42 1.14 1.42 1.44 1.15 1.44 1.46 Acceptance Criteria Off-rated OLMCPR @ Rated Power 45% Flow OLMCPR PDBA Setpoint Setpoint Malue Amplitude Trip (SP) 1.11 1.12 1.13 1.14 1.15 Confirmation Count (NP) 14 14 15 16 16 3 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 B1C19 Core Operating Limits Report Table 4 Exposure Basis 4 for Brunswick Unit 1 Cycle 19 Transient Analysis Design Calc. No. 1B21-0649 Page 19, Revision 0 Core Average Exposure (MWd/MTU)

Comments 30,998 Break point for exposure-dependent MCPRP limits (NEOC)33,159 Design basis rod patterns to EOFP + 1.5 EFPD (EOCLB)34,912 End of reactivity for FFTR/Coastdown

-Maximum Core Exposure (MCE)4 The exposure basis for the defined break points is 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 B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 20, Revision 0 Table 5 Power-Dependent MCPRp Limits 5 NSS Insertion Times BOC to < NEOC EOOS Power ATRIUM 1OXM ATRIUM-10 Condition

(% rated) MCPRp MCPRp 100.0 1.39 1.48 90.0 1.42 1.50 80.0 1.43 1.51 65.0 1.64 1.67 Base Case 50.0 1.68 1.71 Operation

> 65%F < 65%F > 65%F -< 65%F 50.0 1.92 1.78. 1.98 1.87 26.0 2.33 2.19 2.38 2.26 26.0 2.74 2.71 2.91 2.91 23.0 2.88 2.85 3.04 3.04 100.0 1.42 1.51 90.0 1.46 1.53 80.0 1.49 1.57 65.0 1.64 1.67 50.0 1.68 1.71 TBVOOS > 65%F s 65%F > 65%F -< 65%F 50.0 1.92 1.78 1.98 1.87 26.0 2.33 2.19 2.38 2.26 26.0 3.25 3.05 3.36 3.20 23.0 3.48 3.29 3.54 3.42 100.0 1.39 1.48 90.0 1.42 1.50 80.0 1.45 1.51 65.0 1.64 1.67 FHOOS 50.0 1.68 1.71> 65%F !5 65%F > 65%F S 65%F 50.0 1.92 1.78 1.98 1.87 26.0 2.33 2.19 2.38 2.26 26.0 2.74 2.71 2.91 2.91 23.0 2.88 2.85 3.04 3.04 100.0 1.42 1.51 90.0 1.47 1.53 80.0 1.51 1.57 TBVOOS 65.0 1.64 1.67 and 50.0 1.68 1.73 FHOOS > 65%F 5 65%F > 65%F !5 65%F 50.0 1.92 1.78 1.98 1.87 26.0 2.33 2.19 2.38 2.26 26.0 3:25 3.05 3.36 3.20 1 23.0 1 3.48 3.29 3.54 3.42 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 B11C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 21, Revision 0 Table 6 Power-Dependent MCPRp Limits 6 TSSS Insertion Times BOC to < NEOC EOOS Power ATRIUM 1OXM ATRIUM-10 Condition

(% rated) MCPRp MCPRp 100.0 1.44 1.54 90.0 1.46 1.54 80.0 1.47 1.55 65.0 1.64 1.67 Base Case 50.0 1.68 1.71 Operation

> 65%F _ 65%F > 65%F < 65%F 50.0 1.93 1.78 2.00 1.87 26.0 2.34 2.20 2.39 2.26 26.0 2.74 2.71 2.91 2.91 23.0 2.88 2.85 3.04 3.04 100.0 1.47 1.56 90.0 1.51 1.58 80.0 1.53 1.61 65.0 1.64 1.67 50.0 1.68 1.72 TBVOOS > 65%F < 65%F > 65%F < 65%F 50.0 1.93 1.78 2.00 1.87 26.0 2.34 2.20 2.39 2.26 26.0 3.25 3.05 3.36 3.20 23.0 3.48 3.29 3.54 3.42 100.0 1.44 1.54 90.0 1.46 1.54 80.0 1.48 1.55 65.0 1.64 1.67 FHOOS 50.0 1.68 1.71> 65%F < 65%F > 65%F _ 65%F 50.0 1.93 1.78 2.00 1.87 26.0 2.34 2.20 2.39 2.26 26.0 2.74 2.71 2.91 2.91 23.0 2.88 2.85 3.04 3.04 100.0 1.47 1.56 90.0 1.51 1.58 80.0 1.54 1.61 TBVOOS 65.0 1.64 1.67 and .50.0 1.69 1.76 FHOOS > 65%F < 65%F > 65%F < 65%F 50.0 1.93 1.78 2.00 1.87 26.0 2.34 2.20 2.39 2.26 26.0 3.25 3.05 3.36 3.20 1 23.0 3.48 3.29 3.54 3.42 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 B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 22, Revision 0 Table 7 Power-Dependent MCPRp Limits 7 NSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 10XM ATRIUM-10 Condition

(% rated) MCPRp MCPRp 100.0 1.41 1.53 90.0 1.44 1.54 80.0 1.45 1.55 65.0 1.64 1.67 Base Case 50.0 1.68 1.71 Operation

> 65%F < 65%F > 65%F < 65%F 50.0 1.92 1.78 1.98 1.87 26.0 2.33 2.19 2.38 2.26 26.0 2.74 2.71 2.91 2.91 23.0 2.88 2.85 3.04 3.04 100.0 1.44 1.55 90.0 1.48 1.57 80.0 1.50 1.60 65.0 1.64 1.67 50.0 1.68 1.71 TBVOOS > 65%F < 65%F 65%F < 65%F 50.0 1.92 1.78 1.98 1.87 26.0 2.33 2.19 2.38 2.26 26.0 3.25 3.05 3.36 3.20 23.0 3.48 3.29 3.54 3.42 100.0 1.41 1.53 90.0 1.44 1.54 80.0 1.45 1.55 65.0 1.64 1.67 FHOOS 50.0 1.68 1.71>65%F < 65%F > 65%F < 65%F 50.0 1.92 1.78 1.98 1.87 26.0 2.33 2.19 2.38 2.26 26.0 2.74 2.71 2.91 2.91 23.0 2.88 2.85 3.04 3.04 100.0 1.44 1.55 90.0 1.48 1.57 80.0 1.51 1.60 TBVOOS 65.0 1.64 1.67 and 50.0 1.68 1.73 FHOOS > 65%F < 65%F > 65%F < 65%F 50.0 1.92 1.78 1.98 1.87 26.0 2.33 2.19 2.38 2.26 26.0 3.25 3.05 3.36 3.20 23.0 3.48 3.29 3.54 3.42 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 B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 23, Revision 0 Table 8 Power-Dependent MCPRp TSSS Insertion Times BOC to < EOCLB Limits 8 EOOS Power ATRIUM 1OXM ATRIUM-10 Condition

(% rated) MCPRp MCPRp 100.0 1.44 1.56 90.0 1.47 1.57 80.0 1.47 1.57 65.0 1.64 1.67 Base Case 50.0 1.68 1.71 Operation

> 65%F -65%F > 65%F < 65%F 50.0 1.93 1.78 2.00 1.87 26.0 2.34 2.20 2.39 2.26 26.0 2.74 2.71 2.91 2.91 23.0 2.88 2.85 3.04 3.04 100.0 1.47 1.60 90.0 1.51 1.61 80.0 1.53 1.63 65.0 1.64 1.68 50.0 1.68 1.73 TBVOOS > 65%F < 65%F > 65%F _ 65%F 50.0 1.93 1.78 2.01 1.88 26.0 2.34 2.20 2.40 2.27 26.0 3.25 3.05 3.37 3.21 23.0 3.48 3.29 3.55 3.43 100.0 1.44 1.56 90.0 1.47 1.57 80.0 1.48 1.57 65.0 1.64 1.67 HOS 50.0 1.68 1.71> 65%F < 65%F > 65%F -7 65%F 50.0 1.93 1.78 2.00 1.87 26.0 2.34 2.20 2.39 2.26 26.0 2.74 2.71 2.91 2.91 23.0 2.88 2.85 3.04 3.04 100.0 1.47 1.60 90.0 1.51 1.61 80.0 1.54 1.63 TBVOOS 65.0 1.64 1.68 and 50.0 1.69 1.77 FHOOS > 65%F < 65%F > 65%F -< 65%F 50.0 1.93 1.78 2.01 1.88 26.0 2.34 2.20 2.40 2.27 26.0 3.25 3.05 3.37 3.21 1 23.0 3.48 3.29 3.55 3.43 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 B1C19 Core Operating Limits Report Design CaIc. No. 1B21-0649 Page 24, Revision 0 Table 9 Power-Dependent MCPRP Limits 9 NSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 1OXM ATRIUM-10 Condition

(% rated) MCPRP MCPRP 100.0 1.44 1.57 Base Case 90.0 1.46 1.57 Operation 80.0 1.46 1.58 65.0 1.64 1.67 (FFTR/FHOOS 50.0 1.68 1.71 included)

> 65%F -65%F > 65%F < 65%F 50.0 1.92 1.78 1.98 1.87 (Bounds operation 26.0 2.33 2.19 2.38 2.26 with NEWF) 26.0 2.74 2.71 2.91 2.91 23.0 2.88 2.85 3.04 3.04 100.0 1.45 1.57 90.0 1.49 1.58 TBVOOS 80.0 1.51 1.61 65.0 1.64 1.67 (FFTR/FHOOS 50.0 1.68 1.73 included)

> 65%F < 65%F > 65%F < 65%F (Bounds operation 50.0 1.92 1.78 1.98 1.87 with NFWT) 26.0 2.33 2.19 2.38 2.26 26.0 3.25 3.05 3.36 3.20 23.0 3.48 3.29 3.54 3.42 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 B1C19 Core Operating Limits Report Design CaIc. No. 1 B21-0649 Page 25, Revision 0 Table 10 Power-Dependent MCPRP Limits 1 0 TSSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 1OXM ATRIUM-10 Condition

(% rated) MCPRP MCPRP'100.0 1.50 1.72 Base Case 90.0 1.50 1.72 Operation 80.0 1.50 1.72 65.0' 1.64 1.74 (FFTR/FHOOS 50.0 1.68 1.78 included)

> 65%F < 65%F > 65%F < 65%F 50.0 1.93 1.78 2.07 1.94 (Bounds operation 26.0 2.34 2.20 2.46 2.33 with NFWT) 26.0 2.74 2.71 2.98 2.98 23.0 2.88 2.85 3.11 3.11 100.0 1.50 1.72 90.0 1.51 1.72 TBVOOS 80.0 1.54 1.72 65.0 1.64 1.74 (FFTR/FHOOS 50.0 1.69 1.83 included)

> 65%F -65%F > 65%F <- 65%F (Bounds operation 50.0. 1.93 1.78 2.07 1.94 with NFWT) 26.0 2.34 2.20 2.46 2.33 26.0 3.25 3.05 3.43 3.27 23.0 3.48 3.29 3.61 3.49'0 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 B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 26, Revision 0 Table 11 Flow-Dependent MCPRf Limits 1 1 Core Flow (% of rated) MCPRf 0.0 1.72 31.0 1.72 55.0 1.62 100.0 1.20 107.0 1.20 Limits valid for all SCRAM insertion times and all core average exposure ranges.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B1C19 Core Operating Limits Report Design CaIc. No. 1B21-0649 Page 27, Revision 0 Table 12 AREVA Fuel Steady-State LHGRss Limits Peak ATRIUM 1OXM ATRIUM-10 Pellet Exposure LHGR LHGR (GWd/MTU) (kW/ft) (kW/ft)0.0 14.1 13.4 18.9 14.1 13.4 74.4 7.4 7.1 Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B1C19 Core Operating Limits Report Design CaIc. No. 1B21-0649 Page 28, Revision 0 Table 13 AREVA Fuel Power-Dependent LHGRFACp Multipliers 1 2 NSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 1OXM ATRIUM-10 Condition

(% rated) LHGRFACp LHGRFACP 100.0 1.00 1.00 90.0 1.00 1.00 50.0 0.92 0.90 Base Case > 65%F 5 65%F > 65%F < 65%F Operation 50.0 0.86 0.86 0.78 0.86 26.0 0.68 0.72 0.65 0.73 26.0 0.40 0.42 0.43 0.46 23.0 0.36 0.38 0.39 0.43 100.0 1.00 0.91 90.0 1.00 0.91 50.0 0.92 0.85> 65%F -65%F > 65%F -65%F TBVOOS 50.0 0.86 0.86 0.78 0.85 26.0 0.68 0.72 0.65 0.73 26.0 0.36 0.42 0.38 0.41 23.0 0.32 0.37 0.35 0.37 100.0 1.00 1.00 90.0 1.00 1.00 50.0 0.92 0.89> 65%F -5 65%F > 65%F -< 65%F 50.0 0.86 0.86 0.78 0.86 26.0 0.68 0.72 0.65 0.70 26.0 0.40 0.42 0.43 0.46 23.0 0.36 0.38 0.39 0.43 100.0 1.00 0.91 90.0 1.00 0.91 50.0 0.92 0.84 TBVOOS >65%F 0.9 65%F > 65%F -65%F and aHd 50.0 0.86 0.86 0.78 0.84 FHOOS 26.0 0.68 0.72 0.65 0.70 26.0 0.36 0.42 0.38 0.41 23.0 0.32 0.37 0.35 0.37 12 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 B1C19 Core Operating Limits Report Design CaIc. No. 1B21-0649 Page 29, Revision 0 Table 14 AREVA Fuel Power-Dependent LHGRFACP Multipliers13 TSSS Insertion Times BOC to < EOCLB EOOS Power ATRIUM 1OXM ATRIUM-10 Condition

(% rated) LHGRFACP LHGRFACP 100.0 1.00 1.00 90.0 1.00 1.00 50.0 0.92 0.89 Base Case > 65%F < 65%F > 65%F < 65%F Operation 50.0 0.86 0.86 0.76 0.85 26.0 0.68 0.72 0.64 0.73 26.0 0.40 0.42 0.43 0.46 23.0 0.36 0.38 0.39 0.43 100.0 1.00 0.87 90.0 1.00 0.87 50.0 0.92 0.85> 65%F !5 65%F > 65%F 5 65%F TBVOOS 50.0 0.86 0.86 0.76 0.85 26.0 0.68 0.72 0.64 0.73 26.0 0.36 0.42 0.38 0.41 23.0 0.32 0.37 0.35 0.37 100.0 1.00 1.00 90.0 1.00 1.00 50.0 0.92 0.88>65%F -65%F > 65%F -65%F 50.0 0.86 0.86 0.76 0.85 26.0 0.68 0.72 0.64 0.70 26.0 0.40 0.42 0.43 0.46 23.0 0.36 0.38 0.39 0.43 100.0 1.00 0.87 90.0 1.00 0.87 50.0 0.92 0.83 TBVOOS and > 65%F -9 65%F > 65%F -8 65%F and 50.0 0.86 0.86 0.76 0.83 26.0 0.68 0.72 0.64 0.70 26.0 0.36 0.42 0.38 0.41 23.0 0.32 0.37 0.35 0.37 13 Limits support operationwith 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 BIC19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 30, Revision 0 Table 15 AREVA Fuel Power-Dependent LHGRFACp Multipliers 1 4 NSS Insertion Times BOC to < MCE (FFTR/Coastdown)

EOOS Power ATRIUM 10XM ATRIUM-10 Condition

(% rated) LHGRFACP LHGRFACP Base Case 100.0 1.00 1.00 Operation 90.0 1.00 1.00 50.0 0.92 0.86 (FFTR/FHOOS

> 65%F -< 65%F > 65%F < 65%F included) 50.0 0.86 0.86 0.78 0.86 260 0.68 0.72 0.65 0.70 (Bounds operation 26.0 0.40 0.42 0.43 0.46 with NFVWT) 23.0 0.36 0.38 0.39 0.43 100.0 1.00 0.91 TBVOOS 90.0 1.00 0.91 50.0 0.92 0.84 (FFTR/FHOOS

> 65%F -65%F > 65%F -65%F included) 50.0 0.86 0.86 0.78 0.84 (Bounds operation 26.0 0.68 0.72 0.65 0.70 with NFVVT) 26.0 0.36 0.42 0.38 0.41 23.0 0.32 0.37 0.35 0.37 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.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B1C19 Core Operating Limits Report Design CaIc. No. 1B21-0649 Page 31, Revision 0 Table 16 AREVA Fuel Power-Dependent LHGRFACp TSSS Insertion Times BOC to < MCE (FFTR/Coastdown)

Multipliers 1 5 EOOS Power ATRIUM 1OXM ATRIUM-10 Condition

(% rated) LHGRFACp LHGRFACp Base Case 100.0 1.00 1.00 Operation 90.0 1.00 1.00 50.0 0.92 0.85 (FFTR/FHOOS

> 65%F < 65%F > 65%F < 65%F included) 50.0 0.86 0.86 0.76 0.85 26.0 0.68 0.72 0.64 0.70 (Bounds operation 26.0 0.40 0.42 0.43 0.46 with NFWT) 23.0 0.36 0.38 0.39 0.43 100.0 1.00 0.86 TBVOOS 90.0 1.00 0.86 50.0 0.92 0.83 (FFTR/FHOOS

> 65%F -- 65%F > 65%F -65%F included) 50.0 0.86 0.86 0.76 0.83 (Bounds operation 26.0 0.68 0.72 0.64 0.70 with NFWT) 26.0 0.36 0.42 0.38 0.41 23.0 0.32 0.37 0.35 0.37 15 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 B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 32, Revision 0 Table 17 AREVA Fuel Flow-Dependent LHGRFACf Multipliers 1 6 Core Flow ATRIUM 10XM ATRIUM-10 (% of rated) LHGRFACf LHGRFACf 0.0 0.58 0.85 31.0 0.58 0.85 65.0 --- 1.00 75.0 1.00 ---107.0 1.00 1.00 16 Multipliers valid for all SCRAM insertion times and all core average exposure ranges.

Progress Ehergy Nuclear Fuels Mgmt. and Safety Analysis BIC19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 33, Revision 0 Table 18 AREVA Fuel Steady-State MAPLHGRss Limits 1 7' 18, 19 Average Planar Exposure ATRIUM 10XM ATRIUM-1 0 (GWd/MTU)

MAPLHGR MAPLHGR (kW/ft) (kW/ft)0.0 13.1 12.5 15.0 13.1 12.5 67.0 7.7 7.3 17 AREVA Fuel MAPLHGR limits do not have a power or flow dependency.

Thus, the ATRIUM-10 and ATRIUM 1OXM MAPFACP and the MAPFACf multipliers have a constant value of 1.0 under all conditions.

18 ATRIUM-1 0 MAPLHGR limits must be adjusted by a 0.85 multiplier when in SLO. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.19 ATRIUM 1OXM MAPLHGR limits must be adjusted by a 0.80 multiplier when in SLO. SLO not permitted for FHOOS, TBVOOS or MSIVOOS.

Progress Energy Nuclear Fuels Mgmt. and Safety Analysis B1C19 Core Operating Limits Report Figure 1 Stability Option III Power/Flow Map OPRM Operable, Two Loop Operation, 2923 MWt Design Calc. No. 1 B21-0649 Page 34, Revision 0 I This Figure supports Improved Tqchnical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 110.0 100.0 90.0 80.0 70.0 o 60.0 50.0 40.0 30.0 20.0 10.0 0.0 Minimum Maximum (MELLL) (ICF)Core Core Power Flow Flow% Mlbs/hr Mlbr 100 76.19 80.47 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 95 70.49 80.47 94 69.36 80.47 93 68.25 80.47 92 67.13 80.47 91 66.03 80.47 90 64.93 80.47 89 63.83 80.47 88 62.74 80.47 87 61.66 80.51 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 81 55.25 81.21 80 54.20 81.36 79 53.16 81.51 78 52.12 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 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 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 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 B1C19 Core Operating Limits Report Figure 2 Stability Option III Power/Flow Map OPRM Inoperable, Two Loop Operation, 2923 MWt Design Calc. No. 1B21-0649 Page 35, Revision 0 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 Minimum Maximum (MELLL) (ICF)Core Core Power Flow Flow% Mlbs/hr Mlbs/hr 100 76.19 80.47 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 95 70.49 80.47 94 69.36 80.47 93 68.25 80.47 92 67.13 80.47 91 66.03 80.47 90 64.93 80.47 89 63.83 80.47 88 62.74 80.47 87 61.66 80.51 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 81 55.25 81.21 80 54.20 81.36 79 53.16 81.51 78 52.12 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 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 61 35.06 84.30 60 34,10 84.45 59 33.13 84.61 58 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 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 BIC19 Core Operating Limits Report Figure 3 Stability Option III Power/Flow Map OPRM Operable, Single Loop Operation, 2923 MWt Design CaIc. No. 1B21-0649 Page 36, Revision 0 This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 110.0 100.0 90.0 80.0 70.0 o 60.0 50.0 40.0 30.0 20.0 10.0 0.0 Minimum Maximum (MELLL) (ICF)Core Core Power, Flow Flow% Mlbs/hr Mlbs/hr 100 76.19 80.47 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 95 70.49 80.47 94 69.36 80.47 93 68.25 80.47 92 67.13 80.47 91 66.03 80.47 90 64.93 80.47 89 63.83 80.47 88 62.74 80.47 87 61.66 80.51 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 81 55.25 81.21 80 54.20 81.36 79 53.16 81.51 78 52.12 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 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 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 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 B1C19 Core Operating Limits Report Figure 4 Stability Option III Power/Flow Map OPRM Inoperable, Single Loop Operation, 2923 MWt Design Caic. No. 1B21-0649 Page 37, Revision 0 I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 110.0 100.0 90.0 80.0 70.0 o 60.0 50.0 40.0 30.0 20.0 10.0 n n Minimum Maximum (MELLL) (ICF)Core Core Power Flow Flow SMlbs/hr Mlbs/hr 100 76.19 80.47 99 75.04 80.47 98 73,89 80.47 97 72,75 80.47 96 71.61 80.47 95 70.49 80.47 94 69.36 80.47 93 68,25 80.47 92 67.13 80.47 91 66,03 80.47 90 64.93 80.47 89 63.83 80.47 88 62.74 80.47 87 61.66 80.51 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 81 55.25 81.21 80 54.20 81.36 79 53.16 81.51 78 52.12 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 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 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 V 'J s 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 B1C19 Core Operating Limits Report Design Calc. No. 1B21-0649 Page 38, 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 .r-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 I I \ii~Minimum Maximum (MELLL) (ICF)Core Core Power Flow Flow_ Mibs/hr Mlbs/lir 100 76.19 80.47 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 95 70.49 80.47 94 69.36 80.47 93 68.25 80.47 92 67.13 80.47 91 66.03 80.47 90 64.93 80.47 89 63.83 80.47 88 62.74 80.47 87 61.66 80.51 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 81 55.25 81.21 80 54.20 81.36 79 53.16 81.51 78 52.12 81.67 77 51L08 81.82 76 50.05 81.98 75 49o02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 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 61 35.06 84.30 60 34.10 84.45 59 33,13 84.61 58 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 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 B1C19 Core Operating Limits Report Figure 6 Stability Option III Power/Flow Map OPRM Inoperable, FWTR, 2923 MWt Design CaIc. No. 1B21-0649 Page 39, Revision 0 I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 110.0 100.0 90.0 80.0 70.0 o 60.0 50.0 40.0 30.0 20.0 10.0 0.0 Minimum Maximum (MELLL) (ICF)Core Core Power Flow Flow% Mlbs/hr _Mshr 100 76.19 80.47 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 95 70.49 80.47 94 69.36 80.47 93 68.25 80.47 92 67.13 80.47 91 66.03 80.47 90 64.93 80.47 89 63.83 80.47 88 62.74 80.47 87 61.66 80.51 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 81 55.25 81.21 80 54.20 81.36 79 53.16 81.51 78 52.12 81.67 77 51.08 81.82 76 50.05 81.98 75 49.02 82.13 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 70 43.94 82.91 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 61 35.06 84.30 60 34.10 84.45 59 33.13 84.61 58 32.17 84.70 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow

Reference:

0B21-1015, Revision 7 BSEP 12-0040 Enclosure 3 AREVA Affidavit Regarding Withholding ANP-2989(P), Brunswick Unit ] Thermal-Hydraulic Design Report for ATRIUMTM 1OXM Fuel Assemblies, Revision 0, from Public Disclosure AFFIDAVIT STATE OF WASHINGTON

)) ss.COUNTY OF BENTON 1. My name is Alan B. Meginnis.

I am Manager, Product Licensing, for AREVA NP Inc. and as such I am authorized to execute this Affidavit.

2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary.

I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.3. I am familiar with the AREVA NP information contained in the document ANP-2989(P)

Revision 0, entitled, "Brunswick Unit 1 Thermal-Hydraulic Design Report for ATRIUM 1OXM Fuel Assemblies," dated May, 2011 and referred to herein as "Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.

4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.

5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure.

The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information." 6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary: (a) The information reveals details of AREVA NP's research and development plans and programs or their results.(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.(e) The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8. AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.

9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.SUBSCRIBED before me this 1 day of J _ ,,. _ _ ,2011.NOTAR, Susan K. McCoy (N NOTARY PUBLIC, STATE OF MY COMMISSION EXPIRES: 1/10/12