BSEP 04-0012, Cycle 16 Core Operating Limits Report

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Cycle 16 Core Operating Limits Report
ML040370566
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 01/29/2004
From: O'Neil E
Carolina Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 04-0012 2821-1045, Rev 1
Download: ML040370566 (35)
v • d • e


Text

CP&L A Prgress EnergyCaripany JAN 2 9 2004 SERIAL: BSEP 04-0012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Brunswick Steam Electric Plant, Unit No. 2 Docket No. 50-324/License No. DPR-62 Unit 2, Cycle 16 Core Operating Limits Report Ladies and Gentlemen:

The purpose of this letter is to submit the latest revision of the Core Operating Limits Report for the Brunswick Steam Electric Plant (BSEP), Unit 2. Technical Specification 5.6.5.d requires that the Core Operating Limits Report, including any mid-cycle revisions or supplements, be provided to the NRC upon issuance. A copy of the Brunswick Unit 2, Cycle 16 Core Operating Limits Report, January 2004, Revision 1, is enclosed.

The revised BSEP, Unit 2 report incorporates power-flow maps for operation with reduced final feedwater temperatures. The revised report supersedes the report submitted by letter dated March 26, 2003 (i.e., ADAMS Accession Number ML030940709).

Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor -

Licensing/Regulatory Programs, at (910) 457-2073.

Sincerely, Edward T. O'Neil Manager - Support Services Brunswick Steam Electric Plant Brunswick Nuclear Plant PO. Box 10429

$yJA Southport, NC 28461

Document Control Desk BSEP 04-0012 / Page 2 WRM/wrm

Enclosure:

Brunswick Unit 2, Cycle 16 Core Operating Limits Report, January 2004, 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. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 cc (without enclosure):

Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

BSEP 04-0012 Enclosure Brunswick Unit 2, Cycle 16 Core Operating Limits Report, January 2004, Revision 1

U I NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 1, Revision I Progress Energy BRUNSWICK UNIT 2, CYCLE 16 CORE OPERATING LIMITS REPORT January 2004 Prepared By: To Dresser Date: t Tom Dresser Approved By: Date: /

_z__ -_y George E. Smith Supervisor BWR Fuel Engineering I U

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 2, Revision I LIST OF EFFECTIVE PAGES Page(s) Revision 1-9 1 10 - 28 (including 14a and 23a) 0 29-30 1 TABLE OF CONTENTS Subject Page Cover.................................................................................................................................................I List of Effective Pages .............................. 2 Table of Contents .............................. 2 List of Tables and Figures .............................. 3 Introduction and Summary .............................. 4 Single Loop Operation .............................. 5 Inoperable Main Turbine Bypass System ................................ 5 APLHGR Limits .............................. 6 MCPR Limits ................................ 6 RBM Rod Block Instrumentation Setpoints .............................. 6 Stability Option III .............................. 7 References ............................... 9

@ Progress Energy

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Cale. No. 2B21-1045 B2C16 Core Operating Limits Report Page 3, Revision I 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 AND FIGURES Table Title Page Table 2: MCPR Limit S0ts ..................................

Table 2: RBM System S.tpointsl. .

Table 3: PBDA Setpoints.12 Figure 1: APLHGR Limit Versus Average Planar Exposure .13 Figure 2: APLHGR Limit Versus Average Planar Exposure .14 Figure 2a: APLHGR Limit Versus Average Planar Exposure .14a Figure 3: APLHGR Limit Versus Average Planar Exposure .15 Figure 4: APLHGR Limit Versus Average Planar Exposure. 16 Figure 5: APLHGR Limit Versus Average Planar Exposure .17 Figure 6: APLHGR Limit Versus Average Planar Exposure .18 Figure 7: APLHGR Limit Versus Average Planar Exposure .19 Figure 8: APLHGR Limit Versus Average Planar Exposure .20 Figure 9: Flow-Dependent MAPLHGR Limit, MAPLHGR(F) .21 Figure 10: Power-Dcpendent MAPLHGR Limit, MAPLHGR(P) .22 Figure 11: GE13 and GE14 Flow-Dependent MCPR Limit, MCPR(F) .23 Figure II a: Atrium-1O Flow-Dependent MCPR Limit, MCPR(F) .. 23a Figure 12: Power-Dependent MCPR Limit, MCPR(P) .................................... 24 Figure 13: Stabiliht Option III Power/Flow Map: OPRM Operable, Two Loop Operation, 2923 MWt . 25 Figure 14: Stability Option III Power/Flow Map: OPRM Inoperable, Two Loop Operation, 2923 MWt . 26 Figure 15: Stability Option HI Power/Flow Map: OPRM Operable, Single Loop Operation, 2923 MWt . 27 Figure 16: Stability Option III Power/Flow Map: OPRM Inoperable, Single Loop Operation, 2923 MWt . 28 Figure 17: Stability Option III Power/Flow Map: OPRM Operable, FWTR, 2923 MWt.29 Figure 18: Stability Option III Power/Flow Map: OPRM Inoperable, FWTR, 2923 MWt .30 21 Progress Energy

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 4, Revision I Introduction and SummarY COLR Revision 0 was prepared to support Brunswick 2 Cycle 16 operation at up to 2923 MWt (EPUR). The main changes made in Revision 0 were those associated with the thermal limits and Power-Flow maps. Also, the following thresholds were scaled for the higher rated thermal power: the thermal limit monitoring threshold changed from 25% to 23% and the turbine trip scram bypass threshold changed from 30% to 26%. This report provides the values of the power distribution limits and control rod withdrawal block instrumentation setpoints for Brunswick Unit 2, Cycle 16 (B2C 16) as required by TS 5.6.5.

OPERATING LIMIT REQUIREMENT Average Planar Linear Heat Generation Rate (APLHGR) limits TS 5.6.5.a.1 (with associated core flow and core power adjustment factors)

Minimum Critical Power Ratio (MCPR) limits TS 5.6.5.a.2 (with associated core flow and core power adjustment factors)

Period Based Detection Algorithn (PBDA) Setpoint for Function 2.f of TS 3.3.1. 1, TS 5.6.5.a.3 Oscillation Power Range Monitor (OPRM)

Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions TS 5.6.5.a.4 of TS 3.3.2.1 Per TS 5.6.5.b and 5.6.5.c, these values have been determined using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met. The limits specified in this report support single loop operation (SLO) as required by TS LCO 3.4.1 and inoperable Main Turbine Bypass System as required by TS 3.7.6.

In order to support the Stability Option III with an inoperable OPRM scram function, the following is also included in this report:

OPERATING LIMIT REQUIREMENT BWROG Interim Corrective Action Stability Regions TS 3.3.1.1 LCO Condition I Four Siemens ATRIUM-10 (Al0) Lead Qualification Assemblies are loaded in the B2C16 core.

Reference 9 concludes the AlO is bounded by the GE13 operating limits and licensing analyses, with AV Progress Energy

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 5, Revision 1 additional operating and design constraints are imposed on the GEI3 fuel type used to monitor the AIO. The additional operating requirements have been incorporated herein as applicable.

Revision I of this report adds Power/Flow maps to give guidance during Feedwater Temperature Reduction (FXVTR).

This report conforms to Quality Assurance requirements as specified in Reference 1.

Single Loop Operation Brunswick Unit 2, Cycle 16 may operate over the entire MEOD range with Single recirculation Loop Operation (SLO) as permitted by TS 3.4.1 with applicable limits specified in the COLR for TS LCO's 3.2.1, 3.2.2 and 3.3.1.1. The applicable limits are:

LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) Limits: per Reference 1, the Figures 9 and 1o described in the APLHGR Limits section below include a SLO limitation of 0.8 on the MAPLHGR(F) and MAPLHGR(P) multipliers.

LCO 3.2.2, Minimum Critical Power Ratio (MCPR) Limits: per Reference 1, Table I and Figures 11 and 12, the MCPR limits presented apply to SLO without modification.

LCO 3.3.1.1, Reactor Protection System Instrumentation Function 2.b (Average Power Range Monitors Simulated Thermal Power - High) Allowable Value: per footnote b, the -AW offset value is defined in Plant procedures. The current value of 20.5% is used for the B2C16 COLR.

Inoperable Main Turbine Bypass System Brunswick Unit 2, Cycle 16 may operate with an inoperable Main Turbine Bypass System in accordance with TS 3.7.6 with applicable limits specified in the COLR for TS LCO 3.2.1 and 3.2.2.

Three or more bypass valves inoperable renders the System inoperable, although the Turbine Bypass Out-of-Service (TBPOOS) analysis supports operation with all bypass valves inoperable for the entire MEOD range and up to 110F rated equivalent feedwater temperature reduction. The system response time assumed by the safety analyses from event initiation to start of bypass valve opening is 0.10 seconds, with 80% rated bypass flow achieved in 0.30 seconds. The applicable limits are as follows:

LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) Limits: in accordance with Reference 1 as shown in Figure 10, TBPOOS does not require an additional reduction in the MAPLGHR(P) limits between 23% and 26% power, as the Turbine bypass Operable and Inoperable limits are identical.

LCO 3.2.2, Minimum Critical Power Ratio (MCPR) Limits: in accordance with Reference 1, Ok Progress Energy

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 6, Revision 1 TBPOOS does not require an additional increase in the MCPR(P) multiplier between 23% and 26% power, as shown in Figure 12, as the Turbine Bypass Operable and Inoperable limits are identical. TBPOOS requires increased rated power MCPR limits, included in Table 1.

APLHGR Limits The limiting APLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of planar average exposure is given in Figures 1 through 8. These values were determined with the SAFER/GESTR LOCA methodology described in GESTAR-I1 (Reference 2).

Figures 1 through 8 are to be used only when hand calculations are required as specified in the bases for TS 3.2.1. Hand calculated results may not match a POWERPLEX calculation since normal monitoring of the APLHGR limits with POWERPLEX uses the complete set of lattices for each fuel type provided in Reference 3.

The core flow and core power adjustment factors for use in TS 3.2.1 are presented in Figures 9 and

10. For any given flow/power state, the minimum of MAPLHGR(F) determined from Figure 9 and MAPLHGR(P) determined from Figure 10 is used to determine the governing limit.

MCPR Limits The ODYN OPTION A, ODYN OPTION B, and non-pressurization transient MCPR limits for use in TS 3.2.2 for each fuel type as a function of cycle average exposure are given in Table 1. These values were determined with the GEMINI methodology and GEXL-PLUS critical power correlation described in GESTAR-fl (Reference 2), and are consistent with a Safety Limit MCPR of 1.11 specified by TS 2.1.1.2.

The core flow and core power adjustment factors for use in TS 3.2.2 are presented in Figures 11 and

12. For any given power/flow state, the maximum of MCPR(F) determined from Figures 11-1 la and MCPR(P) determined from Figure 12 is used to determine the governing limit.

All MCPR limits presented in Table 1, Figures 11-1 la and Figure 12 apply to two recirculation pump operation and SLO without modification.

RBM Rod Block Instrumentation Setpoints The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation for use in TS 3.3.2.1 (Table 3.3.2.1-1) are presented in Table 2. These values were determined consistent with the bases of the ARTS program and the determination of MCPR limits with the GEMINI methodology and GEXL-PLUS critical power correlation described in GESTAR-I (Reference 2). Reference 8 revised certain of these setpoints to reflect changes associated with the installation of the new PRNM system.

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NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limts Report Page 7, Revision I Stabilitv Option HI Brunswick Unit 2 has implemented BWROG Long Term Stability Solution Option III (Oscillation Power Range Monitor-OPRM) as described in Reference 4. Plant specific analysis incorporating the Option III hardware is described in Reference 5. Reload validation has been performed in accordance with Reference 6. The resulting stability based MCPR Operating Limit is provided for two conditions as a function of OPRM amplitude setpoint in Table 3. The reload validation calculation demonstrated that reactor stability does not produce the limiting OLMCPR for Cycle 16 as long as the selected OPRM setpoint produces values for OLMCPR(SS) and OLMCPR(2PT) which are less than the corresponding acceptance criteria. Because the acceptance criteria for OLMCPR(SS) is 1.486 and for OLMCPR(2PT) is 1.41, an OPRM setpoint (Amplitude Setpoint Sp) of 1.10 is supported for Cycle 16 without imposing any additional operational restrictions for stability protection. Therefore the OPRM PBDA setpoint limit referenced by function 2.f of Table 3.3.1. 1-1 of Technical Specification 3.3.1.1 is 1.10 for Cycle 16. Per Table 3-2 of Reference 6, an S. value of 1.10 supports selection of a Confirmation Count Setpoint Np of 13 or less.

Six Power/Flow maps for use at up to 2923 MWt (Figures 13-18) were developed based on Reference 7 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. The corresponding Reference 7 maps are simplified and re-formatted to exhibit the appropriate headers for the COLR. Note that the Simulated Thermal Power (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. The analytic STP limits illustrated in Reference 7 have been revised to the corresponding nominal trip setpoint limits for the COLR. A single loop operation (SLO) Entry Rod Line has been added to the nominal feedwater temperature two loop operation maps as an additional operator aid. All six maps illustrate the region of the power/flow map above 25% power and below 60% flow where the OPRM system is required to be enabled.

The maps supporting an operable OPRM function 2.f (Figures 13, 15 and 17) show Scram Avoidance Regions, which is not a licensing requirement but is an operator aid to illustrate where the OPRM system is reasonably likely to generate a scram to avoid an instability event. Figures 13 and 15 differ only in that the Figure 15 that supports SLO, indicates the maximum allowable core flow at 45 Mlbs/hr, and has the Simulated Thermal Power (STP) scram and rod block limits appropriately reduced for SLO. 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. Figure 17 differs from Figure 13 by extending the existing regions to provide additional stability protection during FWTR. Intentional operation with SLO and FWTR is prohibited.

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NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Umits Report Page 8, Revision 1 The maps (Figures 14, 16 and 18) supporting an inoperable OPRM function 2.f show the BWROG-94078 Interim Corrective Actions stability regions required to support LCO Condition I.

Both figures also include a 5% Buffer Region around the Immediate Exit Region as an operator aid.

Figures 14 and 16 differ only in that the Figure 16 that supports SLO, indicates the maximum allowable core flow at 45 Mlbs/hr, and has the STP scram and rod block limits appropriately reduced for SLO. Figure 18 differs from Figure 14 by extending the existing regions to provide additional stability protection during FWTR. Intentional operation with SLO and FWTR is prohibited.

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NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 9, Revision 1 References

1) BNP Design Calculation 2B21-1045; "Preparation ofthe B2C16 Core Operating Limits Report,"

Revision 1, January 2004.

2) NEDE-24011-P-A; "General Electric Standard Application for Reactor Fuel," (latest approved version).
3) NEDC-31624P, "Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit 2 Reload 15 Cycle 16," Supplement 2, Revision 8, January 2003.
4) NEDO-31960-A, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology,"

November 1995.

5) GE-NE-C51-00251-00-01, Revision 0, "Licensing Basis Hot Bundle Oscillation Magnitude for Brunswick I and 2," March 2001.
6) NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application," August 1996.
7) Design Calculation OB21-1015, Revision 2, "BNP Power/Flow Maps." July 2003.
8) Design Calculation 2C51-0001 Revision 1, "BNP Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (2-C51-APRM 1 through 4 Loops and 2-C51-RBM-A and B Loops," August 8, 2001.
9) EMF-2168(P), "Brunswick ATRIUM-10 Lead Qualification Assemblies Safety Analysis,"

Revision 0, March 1999.

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NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 10, Revision 0 Table 1 MCPR Limits (EOC-RPT Not Required)

Steady State, Non-pressurization Transient MCPR Limits Fuel Type Exposure Range: BOC - EOC GE13 and GE14 1.32 Atrium-1 0 1.47 Pressurization Transient MCPR Limits, OLMCPR (100%P): Turbine Bypass System Operable Normal and Reduced Feedwater Temperature, Exposure Range MCPR Fuel Type BOC to EOFPC-2948 MWd/MT EOFPC-1448 MWd/MT Option EOFPC- to to EOC 2948 MWd/MT EOFPC-1448 MWdIMT GE13 1.39 1.40 1.45 A GE14 1.52 1.53 1.63 Atrium-10 1.55 1.56 1.61 GE13 1.34 1.35 1.37 B GE14 1.41 1.42 1.46 Atium-10 1.49 1.50 1.52 Pressurization Transient MCPR Limits, OLMCPR (100%P): Turbine Bypass System Inoperable MCPR Normal and Reduced Feedwater Temperature Option Fuel Type BOC to EOC GE13 1.46 A GE14 1.64 Atrium-1 0 1.62 GE13 1.38 B GE14 1.47 Atrium-1 0 1.54 This Table is referred to by Technical Specifications 3.2.2, 3.4.1 and 3.7.6.

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NGG Nuclear Fuels Mgmt. & Safety Analysis Design Cac. No. 2B21-1045 B2C16 Core Operating Limits Report Page I1, Revision 0 Table 2 RBM System Setpoints Setpointaa Trip Setpoint ] Allowable Value Lower Power Setpoint (LPSP ) 27.7

  • 29.0 Intermediate Power Setpoint (P S Pb) 62.7 l 64.0 High Power Setpoint (HPSP) 82.7 84.0 Low Trip Setpoint (LTSPC)
  • 114.1 114.6 Intermediate Trip Setpoint (ITSP)
  • 108.3 l 108.8 High Trip Setpoint (HTSPC)
  • 104.5
  • 105.0 RBM Time Delay (td2) *2.0 seconds 2.0 seconds RBM Operability requirements are not applicable:

(1) if MCPR 2 1.70; or (2) if MCPR 2 1.45 and thermal power 2 90% Rated Thermal Power.

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.

This Table is referred to by Technical Specification 3.3.2.1 (Table 3.3.2.1-1).

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NGG Nuclear Fuels Mgmt. & Safety Analysis Design CaIc. No.2821-1045 B2C16 Core Operating Limits Report Page 12, Revision 0 Table 3 PBDA Setpoints OPRM Setpoint OLMCPR(SS) OLMCPR(2PT) 1.05 1.267 1.197 1.06 1.302 1.230 1.07 1.339 1.265 1.08 1.378 1.302 1.09 1.420 1.341 1.10 1.464 1.383 1.11 1.509 1.425 1.12 1.556 1.470 1.13 1.607 1.518 1.14 1.661 1.569 1.15 1.719 1.623 Acceptance Criteria Off-rated OLMCPR @ Rated Power 45% Flow OLMCPR PDBA Setpoint Setpoint Value Amplitude Sp 1.10 Confirmation Count Np 13 This Table is referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-1).

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NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1045 B2C16 Core Operating Limits Report Page 13, Revision 0 Figure 1 C Progress Energy Fuel Type GE13-P9DTB403-7G6.07G5.0-10OT-146-T (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 This Figure is Referred To By 13.0 __

-- - _- Technical Specification 3.2.1 12.0 _ _ ___ __

11.0

=~~~~ Ie 7 Exposure (GWdIMT) 0.00 Limit (kW/ft) 10.44 N

\

10.0 .- 0.22 10.51 Permissible -4 1.10 10.61 Region of 2.20 10.74 Operation 3.31 10.88 I I 4.41 11.02 CD 5.51 11.17 9.0 A

-J 6.61 11.32 a: 7.72 11.48 8.82 11.62 9.92 11.73 11.02 11.85 8.0 _ 13.78 11.86 16.53 11.86 19.29 11.76 7.0 - j..

22.05 27.56 33.07 38.58 44.09 11.54 11.15 10.85 10.39 9.88 L ____

49.60 9.42 55.12 9.01 60.63 8.64 6.0 64.29 8.41 5.0 _-

I I i . 1.

.- . . a . . .

0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1045 B2C16 Core Operating Limits Report Page 14, Revision 0 Figure 2 Progress Energy Fuel Type GE13-P9DTB403-5G6.017G5.0- OOT-146-T (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 13.0 ___ _ ___ -j This Figure is Referred To By Technical Specification 3.2.1 12.0 11.0 Exposure Limt (GWdIMT) (kWlft) 0.00 10.65 Permissible 10.0 3:7-: 0.22 10.72 Pemissbl of_ ___ _

I- 1.10 10.85 Region of 2.20 11.00 Operation 3.31 11.12 4.41 1125 0

-J . 5.51 11.38 - -

I 9.0 6.61 11.52 or1 7.72 11.66 8.82 11.81 9.92 11.95 11.02 12.05 8.0 13.78 12.04 16.53 11.97 19.29 11.79 22.05 11.54 27.56 11.13 7.0 33.07 10.57 - - --

38.58 10.10 44.09 9.68 49.60 9.29 55.12 8.94 60.63 8.60 . .

6.0 64.48 8.36 5.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT)

Design Caic. 2B21 -1045 NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1045 B2C16 Core Operating Limits Report Page 14a, Revision 0 Figure 2a CQ Progress Energy Fuel Type Atrium-10 Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 13.0 12.0 11.0 i 10.0

= 9.0

-J 8.0 7.0 6.0 5.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design CaIc. 2B21-1045 B2C16 Core Operating Limits Report Page 15, Revision 0 Figure 3 C Progress Energy Fuel Type GE14-PIODNAB398-13GZ-1OOT-150-T-2417 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 This Figure is Referred To By ITechnicalSpecification 3.2.1 12.0 11.0 -U

6. ISI I I 7

10.0 A: Exposure (GWd/MT) 0.00 0.22 Umit (kW/ft) 9.70 9.78 1.10 9.89 2.20 10.05 9.0 3.31 10.22 4.41 10.35

- 5.51 10.47 6.61 10.60 7.72 10.73 CD 8.0 8.82 10.83

-J 9.92 10.89 a- 11.02 10.96 12.13 11.02 13.23 11.02 PermisIible 14.33 10.97 Region of 7.0 15.43 10.93 Operation 16.53 10.89 18.74 10.78 22.05 10.54 27.56 10.08 6.0 _-i33.07 9.64 38.58 9.21 44.09 8.75 49.60 8.27 55.12 7.75 61.30 5.43 5.0 i - 61.88 4.86 4.0 .I. l I 0 5 10 15 20 25 30 35 40 45 50 55 60 65 AVERAGE PLANAR EXPOSURE (GWd/MT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Catc. 2B21-1045 B2C16 Core Operating Limits Report Page 16, Revision 0 Figure 4 Cj Progress Energy Fuel Type GE14-PIODNAB399-16GZ-10OT-150-T-2418 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 12.0 .-. -J -< -- js Figure is Referred To By Tchnical Specification 3.2.1 11.0 -- fa- ii7I 10.0 ;7Z Exposure (GWd/MT)

Limt (KV/if)

\

0.00 9.65 0.22 9.73 5- 1.10 9.86 2.20 10.07 I-9.0 I 3.31 4.41 10.27 10.45

- Perissible 5.51 10.58 Region of 6.61 10.69 Operation 7.72 10.78

-j 8.82 10.86 8.0- 9.92 10.94 0t 11.02 11.02 12.13 13.23 14.33 11.11 11.14 11.12

__ __ ___n__~~~~~~~~

7.0 - 15.43 11.11 16.53 11.10 18.74 11.06 22.05 10.90 27.56 10.51 33.07 10.09 6.0 38.58 9.53 44.09 9.02 49.60 8.41 55.12 7.84 60.63 6.44 5.0 - 64.11 4.87 4.0 I I I I I I

I h-I I-0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Caic. 2B21-1045 B2C16 Core Operating Limits Report Page 17, Revision 0 Figure 5 a Progress Energy Fuel Type GE14-PIODNAB420-18GZ-10OT-150-T-2572 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 12.0 11.0 10.0 9.0 I-8.0

-j CL 7.0 6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 AVERAGE PLANAR EXPOSURE (GWd/MT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1045 B2C16 Core Operating Limits Report Page 18, Revision 0 Figure 6 C Progress Energy Fuel Type GE14-PI ODNAB41 9-6G7.017G6.013G2.0-1 OOT-1 50-T-2573 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 9.0 I--

3 8.0 0

M

-j 7.0 6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE GWdIMT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design Calc. 2B21-1045 B2C16 Core Operating Limits Report Page 19, Revision 0 Figure 7 C2 Progress Energy Fuel Type GE1 4-PI ODNAB425-3G7.01 4G6.0/I G2.0-1 OOT-1 50-T-2574 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 9.0 i

_j 8.0 7.0 6.0 5.0 4.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

NGG Nuclear Fuel Mgmt. & Safety Analysis Design CaIc. 2B21-1045 B2C16 Core Operating Limits Report Page 20, Revision 0 Figure 8 C Progress Energy Fuel Type GE14-PIODNAB439-12G6.0- OOT-150-T-2575 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 This Figure is Referred To By 11.0 Technical Specification 3.2.1

  • 10.0 2.

K~

K Exposure Umit (GWdIMT) (kW/ft) 0.0 9.68 9.0 1 _ 0.22 9.72 \K 1.10 9.79 2.20 9.89 3.31 9.99

- 4.41 10.09 qr: 5.51 10.20 6.61 10.31 8.0 1 7.72 10.43 Permissible 8.82 10.55 Region of 9.92 10.67 Operation

-J! 11.02 10.79 0-12.13 10.92 13.23 10.93 I I 7.0 14.33 10.92 15.43 10.90 16.53 10.88 18.74 10.81 22.05 10.60 27.56 10.18 6.0 - 33.07 9.76 38.58 9.32 44.09 8.87 49.60 8.37 55.12 7.83 60.63 5.54 5.0 i 62.06 4.88 4.0 I 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 21, Revision 0 Figure 9 Progress Energy Flow-Dependent MAPLHGR Limit, MAPLHGR(F) 1.10

,1 I I I I This Figure is Referred To By _

1.05 ITwO I nn OnrnfiOn I-11,mitI Technical Specifications i i i - .

3.2.1 and 3.4.1 I/

1.00 M x Flo Nv= 02.5' 0.95 1120_\

0.90 IL 11i Lt l

- 0.85

__ _ _ S S S _ _o Si e Loop Operation *im 0

rU 0.80 co LL 7- T Z - r , -i .-

t~~~~~~~~~~~~~L 1-a 2:= 0.70 V

a.

0.75 fi -/ - II C 0.65 10 OF /

/

F ir 4 4- 44. MAPLHGR(F) = MAPFACF

  • MAPLHGRSTD

/ / MAPLHGRsTD = Standard MAPLHGR Liits 0.60 .S

/ 4 . 4_

MAPFACF(F) = Minimum (1.0, AFVc/100+BF)

W = % Rated Core Flow AF And BF Are Fuel Type Dependent Constants Given Below:

0.55 . . . __

Max Core Flow

(% Rated) AF BF 102.5 0.6784 0.4861 0.50 107.0 0.6758 0.4574 112.0 0.6807 0.4214 117.0 0.6886 0.3828 0.45 0.40 I I I I I I I I I I 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 Core Flow (% Rated)

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 22, Revision 0 Figure 10 C2 Progress Energy Power-Dependent MAPLHGR Limit, MAPLHGR (P) 1.00 This Figure is Referred To By 0.95 Technical Specifications _ -

3.2.1

  • 3.4.1 and 3.7.6J 0.90 0.85 Two Loop Operation Limit n-U.

IL 0.80 E

0 v 0.75 U. Lingel Loop Operation Limit _ -

IL Cu

_ 0.70 W

-J 4-0.65 o_

0. MAPLHGR(P) = MAPFACp

It MAPLHGRsTD = Standard MAPLHGR Limits 0

B. 0.60 I Core Flow -1 For P < 23%:

a. 50% I No Thermal Limits Monitoring Required I For 23% < P < 26%:

Turbine BypassI 0.55 -- ! Operable or U For Core Flow s 50% & Turbine Bypass Operable or Inoperable

_, l Inoperable MAPFACP = 0.567 + 0.0157 (P-26%)

, ~~ 1~ ~l 1~lI l For Core Flow > 50% % Turbine Bypass Operable or Inoperable MAPFACP = 0.433 + 0.0063 (P-26%)

0.50 For P > 26%:

MAPFACP = 1.0 + 0.005224 (P-1 00%)

lCore Flow > 50%l 0.45 lTurbine Bypass l Operable or Inoperable 0.40 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2821-1045 B2C16 Core Operating Limits Report Page 23, Revision 0 Figure 11 C~j Progress Energy GE13 and GE14 Flow-Dependent MCPR Limit, MCPR(F) 1.80 1.75 1.70 1.65 1.60 1.55 1.50 Q. 1.45 1.40 1.35 1.30 LI 1.25 I 1.20 1.15 1.10 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 115 120 Core Flow (% Rated)

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2621-1045 B2C16 Core Operating Limits Report Page 23a, Revision 0 Figure Ila C2 Progress Energy Atrium-10 Flow-Dependent MCPR Limit, MCPR(F) 1.80 1.75 1.70 1.65 1.60 1.55 1.50 M 1.45 1.40 1.35 1.30 1.25 1.20 1.15 1.10 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 115 120 Core Flow (% Rated)

NGG Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Page 24, Revision 0 Figure 12 aj Progress Energy Power - Dependent MCPR Limit, MCPR (P) 3.800n

__Rff I I 3.700 M I -I-4-f-+ 4-II I I I I ______

3.600 Ii' I 11.  ; I_,  ; _ Rated MCPR Multiplier (Kp) -t *,- I-,

I I I I I I I 3.500 - Core Flow >

l l l l l

l l l l l l l l l l I I I I I 3.400- 50% 1

-'7 1 Turbine Bypass [

co N

3.300

-- X -l .

Operable or l

. ~ ..- Operating Limit MCPR(P) = KOperating Limit MCPR(100)

V 3.200 IL For P<23%:

VI 3.100 . ~I I I No Thermal Limits Monitoring Required 4v)

N cm No Limits Specified 3.000 10 Where 26%

a-0 2.900 For 23% < P < PBYPASS: P8YPASS =

Kp = Maximum of 1.535 or KPLP 2.800 For Core Flow S50% & Turbine Bypass Operable or Inoperable, 0

Core Flow < 50% KPLP = [2.34 + 0.0700 (26% - P)] I OLMCPR(100) 2.700 Turbine Bypass For Core Flow > 50% & Turbine Bypass Operable or

-j 0 2.600 Operable or Inoperable, Inoperable KPU = [3.12 + 0.0933 (26% - P)] I OLMCPR(100)

. 2.500 2.400 2.300 It_IIi For 26% < P < 45%:

Kp = 1.28 + 0.0134 (45% - P) 2.200 . I I For 45% < P < 60%:

Kp = 1.15 + 0.00867 (60% - P)

Co 2.100 N For P>60%:

Al Kp = 1.00 + 0.00375 (100% - P) 2.000 I-

.- 1.900 0

1.800 4-1.700 E 1.600

- 1.500 Th-_ is Figure is Referred To By Technical Specification 1.400 _ - - = - == -3.2.2, 3.4.1, 3.7.6

  • a 1.300 1.200 1.100 1.000 I 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 PBYPAS Power (% Rated)

NGG Nuclear Fuels Mgmt. Safety Analysis Figure 13 Design Caic. No. 2B21-1045 B2C16 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 25, Revision 0 OPRM Operable, Two Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 1jj Progress Energy and the Technical Requirements Manual Specification 3.3 120.0 M Inim urn M axIm urn (M ELLL) (IC F)

Core Core 110.0 P ow r Flow, flowr,

% M Ibe/hr M Ibsthr 00 7 .19 80.47 99 75.04 80.47 100.0 I 98 73.89 80.47 97 72.75 80.47 96 71.81 80.47 95 70.49 80.47 90.0 94 69.36 80.47 93 68.25 80.47 92 67.13 60.47 92 66.07 60.47 80.0 90 64.93 80.47 89 63.83 80.47 68 82.74 80.47 87 61.6 0.1I 70.0 86 0.5 60.6 0 L.

85 59.50 60.70 84 56.43 60.79 0 63 5737 0.90 3.

0 60.0 82 56.31 a1.05 Im 81 5 .25 81.21 80 54.20 81.36 79 53.16 81.52 50.0 78 77 52.12 51.08 81.67 81.83 76 50.05 81.9 75 49.02 82.13 40.0 74 73 48.00 46.9 8229 82.44 72 45.96 82.6o 71 44.95 82.75 82.91 30.0 70 69 43.94 42.94 63.06 68 41.94 83.21 67 40.95 83.37 I 66 396 8e 3.52 20.0 65 38.97 63.68 i 64 37.99 83.83 63 37.01 83.99 Il 62 36.04 84.14 10.0 1 35.06 84.29 60 34.10 84.45 59 33.13 64.60 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

NGG Nuclear Fuels Mgmt. Safety Analysis Figure 14 Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 26, Revision 0 OPRM Inoperable, Two Loop Operation, 2923 MWt s Figure supports Improved Technical Specification 3.3.1.1 1C! Progress Energy and the Technical Requirements Manual Specification 3.3 120.0 Minimum M aximum (M ELLL) (iCF)

Core Core 110.0 Power Flow. Flow, Mibsghr M lbsfhr 100 76.19 80.47 100.0 99 75.04 80.47 98 73.89 80.47 97 72.75 80.47 96 71.61 80.47 90.0 95 94 70.49 69.36 80.47 80.47 93 68.25 80.47 92 67.13 80.47 80.0 91 90 '

66.03 64.93 80.47 80.47 89 63.83 80.47 88 62.74 80.47 70.0 87 86 61.66 60.58 80.51 80.60 85 59.50 80.70 84 58.43 80.79 i

0 a.

60.0 83 82 57.37 56.31 60.90 81.05 81 55.25 81.21 80 54.20 81.36 79 53.16 81.52 50.0 78 52.12 81.67 77 51.08 81.83 76 50.05 81.98 75 49.02 82.13 40.0 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 30.0 70 43.94 82.91 69 42.94 83.06 20.0 11i

-t. 68 67 66 41 .94 40.95 39.96 83.21 83.37 83.52 10.0

!
Natural
,. Circulation

,- .; Line ,.

4 ,

I 28% Minimum Pump Speed

_  :'1::

I

' 1

~

' 1' '

65 64 63 62 38.97 37.99 37.01 36.04 83.68 83.83 83.99 84.14 0.0 U I -

_11-~'~ i )Z'Ht F 4t I

U I -

. b . . 'I_

J .; l- *,-' 1", .:, , : .., ,

  • - -i i -

I-,!-,

. i i- I t *,,,-,

!+

I_

61 60 59 58_

35.0 6 34.10 33.13 32.17 84 .29 84.45 84.60 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 %CoreFlow

NGG Nuclear Fuels Mgmt. Safety Analysis Figure 15 Design Calc. No. 2821-1045 B2C16 Core Operating Limits Report Stability Option il Power/Flow Map Page 27, Revision 0 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 ~2 Progress Energy 120.0 MInimum M aximum (M ELLL) tC F )

Cor. Core 110.0 Power Flow, F low,

% M bslhr M bs/hr 100 76.19 80.47 100.0 99 98 75.04 73.89 60.47 80.4 7 97 72.75 80.47 e6 71.61 80.47 95 70.49 80.47 90.0 94 69.36 80.47 93 68.25 80.47 92 87.13 80.47 91 66.03 80.47 80.0 S0 64.93 80.47 89 63.83 80.4 7 88 62.74 80.47 87 61.66 80.5 1 70.0 85 60.58 80.60 85 59.50 80.70 5, 84 58.43 80.79 83 57.37 80.90 0 60.0 82 5 6.31 81.05

. 81 55.25 8 1.2 1 80 54.20 8 1 .36 79 53.16 81.52 50.0 78 52.12 8 1.6 7 77 51.08 81 .83 76 50.05 8 1 .98 75 49.02 82.13 40.0 74 48.00 82.29 73 46.98 82.44 72 45.96 82.60 71 44.95 8 2.7 5 30.0 70 69 43.94 42.94 82.91 83.06 B8 41.94 8 3.2 1 1"

67 40.95 83.37 20.0 66 65 39.96 38.97 83.52 8 3.6 8 64 37.99 83.83 63 37.01 83.99 10.0 62 61 36.04 35.06 84.1 4 84.29 60 34.10 84.45 59 33.13 84.60 58 32.17 64.70 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 Mibs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %CoreFlow

NGG Nuclear Fuels Mgmt. Safety Analysis Figure 16 Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 28, Revision 0 OPRM Inoperable, Single Loop Operation, 2923 MWt Tis Figure supports Improved Technical Specification 3.3.1.1 Cj Progress Energy and the Technical Requirements Manual Specification 3.3

- r

________________________________________________________________ M Inim urn M axlm urn 120.0 (M ELLL) eC F Core Core Power Flow, Flow, 110.0  % M bsihr M lbsthr 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 60.58 80.60 85 59.50 80.70 S. 84 58.43 80.79 0,

83 57.37 80.90 0 60.0 82 81 56.31 55.25 81 .05 8 1 .21

. s0 54.20 81.36 79 53.16 81 .52 50.0 78 52.12 8 1 .67 77 51.08 81.83 76 50.05 a1.98 75 49.02 82.13 40.0 74 73 48.00 46.98 82.29 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 83.21 67 40.95 83.37 66 39.96 83.52 20.0 65 38.97 8 3 .6 a 64 37.99 83.83 63 37.01 8 3.99 e2 36.04 84.14 10.0 61 35.06 84.29 60 34.10 84.45 59 33.13 84.60 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

NGG Nuclear Fuels Mgmt. Safety Analysis Figure 17 Design Calc. No. 2B21-1045 B2C16 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 29, Revision 1 OPRM Operable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 7 1j Progress Energy 120.0 110.0 I Powor M Inim urn (M ELLL)

Core Flow.

M irm um 1IC F)

Core Flow,

%r, M lbohr M tb.Ihr 00 76.19 80 .47 100.0 99 98 75.04 73.89 80.47 80 .47 97 72.75 80.47 go 71.1 80 .47 95 70.49 80.47 90.0 94 69.36 80.47 93 6e.25 80.47 92 67.13 80.47 91 6.03 80.47 80.0 90 64.93 80.47 89 63.83 80.47 a8 62.74 80.47 87 61.66 80.51 70.0 8e 60.58 80.60 85 59.50 80.70 84 58.43 80.79 83 57.37 80.90 0 60.0 82 81 56.31 55.25 81 .05 81 .21 80 54.20 81 .36 79 53.16 81 .52 50.0 78 77 52.12 51.08 81.67 81.83 76 50.05 81.98 75 49.02 82.13 74 46.00 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 83.0e 68 41.94 83.21 67 40.95 83.37 86 39.96 83.52 20.0 5 38.97 83.68 64 37 .99 83.83 63 37.01 83.99 62 36.04 84 .14 10.0 61 35.06 84.29 0 34.10 84 .45 59 33.13 84.60 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

NGG Nuclear Fuels Mgmt. Safety Analysis Figure 18 Design CaIc. No. 2B21-1045 B2C16 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 30, Revision 1 OPRM Inoperable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 Progress Energy and the Technical Requirements Manual Specification 3.3 120.0 Minimum Maximum (M ELLL) (IC F)

Core Core 110.0 Power flow, Flow, M bslhr M bslhr 76.19 80.47 100.0 99 98 75.04 73.89 80.47 80.47 97 72.75 80.47 96 71.61 80.47 95 70.49 80.47 90.0 1

94 69.36 80.47 93 68.25 80.47 i 92 67.13 80.47 9' 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 a6 60.58 80.60 L. 85 59.50 80.70 84 58.43 60.79 3 83 57.37 80.90 0 60.0 82 56.31 81.05

. 81 55.25 81.21 80 54.20 81.36 79 53.16 81.52 50.0 78 52.12 81.67 l1 77 51.06 81.83 76 50.05 81.98 75 49.02 82.13 40.0 74 48.00 82.29 iI 73 46.98 82.44 72 45.96 82.60 71 44.95 82.75 30.0 70 69 43.94 42.94 82.91 83.06 68 41.94 83.21 67 40.95 83.37 20.0 I 66 65 39.96 38.97 83.52 83.68 64 37.99 83.83 63 37.01 83.99 10.0 82 61 36.04 35.06 84.14 84.29 60 34.10 84.45 59 33.13 84.60 84.70 0.0 58 32.17 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 MIbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 %CoreFlow

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