BSEP 03-0168, Cycle 14 Core Operating Limits Report

Cycle 14 Core Operating Limits Report

ML033580584
Person / Time
Site:	Brunswick
Issue date:	12/17/2003
From:	O'Neil E Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 03-0168
Download: ML033580584 (33)

Text

Progress Energy DEC 1 7 2003 SERIAL: BSEP 03-0168 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Brunswick Steam Electric Plant, Unit No. 1 Docket No. 50-325fLicense No. DPR-71 Unit 1, Cycle 14 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 Progress Energy Carolinas, Inc.'s Brunswick Steam Electric Plant (BSEP),

Unit 1. 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 1, Cycle 14 Core Operating Limits Report December 2003, Revision 2, is enclosed.

The revised BSEP, Unit 1 report incorporates power-flow maps for operation with reduced final feedwater temperatures. The revised report supersedes the report submitted by letter dated May 31, 2002 [i.e., ADAMS Accession Number ML021560418].

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 Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461

Document Control Desk BSEP 03-0168 / Page 2 WRM/wrm

Enclosure:

Brunswick Unit 1, Cycle 14 Core Operating Limits Report December 2003, Revision 2 cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. 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 27626-05 10

BSEP 03-0168 Enclosure Brunswick Unit 1, Cycle 14 Core Operating Limits Report December 2003, Revision 2

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No. 1121-0604 Page 1, Revision 2 BRUNSWICK UNIT 1, CYCLE 14 CORE OPERATING LIMITS REPORT December 2003 I

E Prepared By:

Approved By:

Charles Stroule Date:

121 I1M S3 Date: Z-I 3

CQdL(S O' George E. Smith Supervisor BWR Fuel Engineering

CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No. 1 B21-0604 Page 2, Revision 2 LIST OF EFFECTIVE PAGES Page(s) 1 - 2 3

4 - 5 6 -7 8 - 9 10 -24 25 -26 27 -28 29 - 30 Revision 2

1 2

1 2

1 2

1 2

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1 21-0604 B1C14 Core Operating Limits Report Page 3, Revision 1 TABLE OF CONTENTS Subject Page Cover................................................................................................................................................

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

2 Table of Contents.............................

3 List of Tables.............................

4 List of Figures.............................

4 Introduction and Summary..............................

5 Single Loop Operation.............................

6 Inoperable Main Turbine Bypass System..............................

6 APLIlGR Limits.............................

7 MCPR Limits.............................

7 RBM Rod Block Instrumentation Setpoints.............................

7 Stability Option III.............................

8 References.............................

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CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Caic. No. 1 B21-0604 B1C14 Core Operating Limits Report Page 4, Revision 2 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 Pase Table 1:

MCPR Limits...................................................................

10 Table 2:

RBM System Setpoints....................................................................

11 Table 3:

PBDA Setpoints...................................................................

12 LIST OF FIGURES Figure Title or Description Page Figure 1:

APLHGR Limit Versus Average Planar Exposure...................................................................

13 Figure 2:

APLHGR Limit Versus Average Planar Exposure...................................................................

14 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:

Not Used...................................................................

20 Figure 9:

GE13 and GE14 Flow-Dependent MAPLHGR Limit, MAPLHGR(F).......................................... 21 Figure 10: GE13 and GE14 Power-Dependent MAPLHGR Limit, MAPLHGR(P)........................................ 22 Figure 11: GE13 and GE14 Flow-Dependent MCPR Limit, MCPR(F).......................................................... 23 Figure 12: GE13 and GE14 Power-Dependent MCPR Limit, MCPR(P)......................................................... 24 Figure 13: Stability Option m Power/Flow Map: OPRM Operable, Two Loop Operation, 2923 MWt......... 25 Figure 14: Stability Option I Power/Flow Map: OPRM Inoperable, Two Loop Operation, 2923 MWt....... 26 Figure 15: Stability Option Im Power/Flow Map: OPRM Operable, Single Loop Operation, 2923 MNVt...... 27 Figure 16: Stability Option m Power/Flow Map: OPRM Inoperable, Single Loop Operation, 2923 MWt.... 28 Figure 17: Stability Option I Power/Flow Map: OPRM Operable, FWTR, 2923 MWt............................... 29 Figure 18: Stability Option mH Power/Flow Map: OPRM Inoperable, FWTR, 2923 MWt............................. 30

CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No. 1 B21-0604 Page 5, Revision 2 Introduction and Summary CAUTION References to COLR Figures or Tables should be made using titles only; figure and table numbers may change from cycle to cycle.

COLR Revision 1 was performed to support operation at up to 2923 MWt. The main changes made in Revision 1 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 1, Cycle 14 as required by TS 5.6.5.

'L oI'- :-

-'EP Average Planar Linear Heat Generation Rate (APLHGR) limits TS 5.6.5.a I (with associated core flow and core power adjustment factors)

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

Period Based Detection Algorithm (PBDA) Setpoint for Function 2.f of TS 3.3.1.1, TS 5.6.5.a.3 Oscillation Power Range Monitor (OPRM)

Allowable Values and power range setpoints for Rod Block Monitor Upscale TS 5.6.5.a.4 Functions of TS 3.3.2.1 Per TS 5.6.5.b and 5.6.5.c, these values have been determined using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met. The limits specified in this report support single 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 11 with an inoperable OPRM scram function, the following is also included in this report:

lOPERAG IMIT REQIiEMlNT BWROG Interim Corrective Action Stability Regions I TS 3.3.1.1 LCO Condition I l I

Revision 2 of this report adds Power/Flow maps to give guidance during Feedwater Temperature Reduction (FWTR).

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

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1 B21-0604 B1C14 Core Operating Limits Report Page 6, Revision 1 Sinele Loop Operation Brunswick Unit 1, Cycle 14 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 I, the Figures 9 and 1 0 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 I I 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 5% developed for the initial installation of Stability Option III is used for the BIC14 COLR.

Inoperable Main Turbine Bypass System Brunswick Unit 1, Cycle 14 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.

Two 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 11 0F 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% bypass flow achieved in 0.30 seconds. The applicable limits are as follows:

LCO 3.2., Average Planar Linear Heat Generation Rate (APLHGR) Limits: in accordance with Reference I as shown in Figure 10, TBPOOS does not require an additional reduction in the MAPLGIR(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, 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 MCPR limits, included in Table 1.

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CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0604 B1C14 Core Operating Umits Report Page 7, Revision 1 APL11GR 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 I through 7. These values were determined with the SAFER/GESTR LOCA methodology described in GESTAR-fl (Reference 2).

Figures I through 7 are to be used only when hand calculations are required as specified in the bases for TS 3.2.1. Hand calculated results may not match a POWERPLEX calculation since normal monitoring of the APLHGR limits with POWERPLEX uses the complete set of lattices for each fuel type provided in Reference 3.

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

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

MCPR Limits The ODYN OPTION A, ODYN OPTION 13, 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-I (Reference 2), and are consistent with a Safety Limit MCPR of 1.12 specified by TS 2.1.1.2.

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

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

All MCPR limits presented in Table 1, Figure 11 and Figure 12 apply to two recirculation pump operation 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-I1 (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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CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1 B21-0604 B1C14 Core Operating Limits Report Page 8, Revision 2 Stability Option III Brunswick Unit 1 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 14 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 1.50 and for OLMCPR(2PT) is 1.40, an OPRM setpoint (Amplitude Setpoint Sp) of 1.15 is supported for Cycle 14 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 1.15 for Cycle 14. Per Table 3-2 of Reference 6, an Sp value of 1.15 supports selection of a Confirmation Count Setpoint Np of 16 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 ImI 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 simply re-formatted (no change in data) to exhibit the appropriate headers for the COLR.

All six maps illustrate the region of the power/flow map above 25% power and below 60% flow where the system is required to be enabled. A single loop operation (SLO) Entry Rod Line has been added to the two loop operation maps as an additional operator aid.

The maps supporting an operable OPRM function 2.f (Figures 13, 15 and 17) show the same Scram Avoidance Region, 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.

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.

CP&L Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1 B21-0604 B1 C1 4 Core Operating Limits Report Page 9, Revision 2 References

1) BNP Design Calculation lB21-0604; "Preparation of the BlC14 Core Operating Limits Report,"

Revision 2.

2) NEDE-2401 1-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 1 Reload 13 Cycle 14," Supplement 1, Revision 7, March 2002.

4) NEDO-31960-A, "BWR Owners Group Long-Term Stability Solutions Licensing Methodology,"

November 1995.

5) GE-NE-C51-00251-00-01, Revision 0, "Licensing Basis Hot Bundle Oscillation Magnitude for Brunswick 1 and 2," March 2001.

6) NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application," August 1996.

7) Design Calculation OB21-1015, "BNP Power/Flow Maps," Revision 2.

8) Design Calculation C51-0001 Revision 1, "BNP Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (1-C51-APRM 1 through 4 Loops and 1-C51-RBM-A and B Loops," July 2001.

CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Umits Report Design Calc. No. 1B21-0604 Page 10, Revision 1 Table 1 MCPR Limits Steady State, Non-pressurization Transient MCPR Limits Fuel Type Exposure Range: BOC - EOC GE13 and GE14 1.26 Pressurization Transient MCPR Limits, OLMCPR (100%P):

Turbine Bypass System Operable Normal and Reduced Feedwater Temperature Exposure Range:

Exposure Range:

MCPR Option Fuel Type BOO to EOFPC-2026 EOFPC-2026 MWd/IMT to EOC MWdIMT A

GE13 1.43 1.49 GE14 1.56 1.68 B

GE13 1.38 1.41 GE14 1.45 1.51 Pressurization Transient MCPR Limits, OLMCPR (100%P):

Turbine Bypass System Inoperable Normal and Reduced Feedwater Temperature MCPR Option Fuel Type BOO to EOC A

GE13 1.50 GE14 1.69 B

GE13 1.42 GE14 1.52 This Table is referred to by Technical Specifications 3.2.2, 3.4.1 and 3.7.6.

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No.1 B21-0604 Page 11. Revision 1 Table 2 RBM System Setpoints Setpoint Trip Setpoint Allowable Value Lower Power Setpoint (LPSPb) 27.7

• 29.0 Intermediate Power Setpoint (IPSPb) 62.7

• 64.0 High Power Setpoint (HPSPb) 82.7

• 84.0 LowTrip Setpoint (LTSPC)

• 114.1

• 114.6 Intermediate Trip Setpoint (ITSPC)

• 108.3

• 108.8 High Trip Setpoint (HTSPC) 104.5

• 105.0 td2

< 2;0 seconds

• 2.0 seconds RBM Operability requirements are not applicable:

(1) if MCPR 2 1.70; or (2) if MCPR 2 1.40 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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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Umits Report Design Calc. No. 1B21-0604 Page 12, Revision 1 Table 3 PBDA Setpoints OPRM Setpoint OLMCPR(SS)

OLMCPR(2PT) 1.05 1.207 1.127 1.06 1.226 1.144 1.07 1.244 1.162 1.08 1.264 1.180 1.09 1.284 1.199 1.10 1.304 1.218 1.11 1.325 1.237 1.12 1.345 1.256 1.13 1.367 1.276 1.14 1.389 1.297 1.15 1.412 1.319 Acceptance Criteria Off-rated OLMCPR @

Rated Power 45% Flow OLMCPR PDBA Setpoint Setpoint Value Amplitude Sp 1.15 Confirmation Count Np 16 This Table is referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-1).

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No. 1 B21-0604 Page 13, Revision 1 Figure 1 Fuel Type GEI 3-P9DTB403-5G6.017G5.0-1 OOT-1 46-T (GEl 3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 12.0 11.0 Z'

10.0

j0:a 9.0 8.0 7.0 0

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

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No. 1 B21-0604 Page 14, Revision I Figure 2 Fuel Type GE13-P9DTB403-7G6.017G5.0-10OT-146-T (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 12.0 11.0

! 10.0 I-

-C j

9.0

-j0 8.0 7.0 6.0 0

5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT) a cP&L ar k

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CP&L Nuclear Fuels Mgmt.Safety Analysis B1C14 Core Operating Limits Report Design Calculation No. 1B21-0604 Page 15, Revision 1 Figure 3 Fuel Type GE13-P9DTB405-5G6.017G5.0-lOUT-146-T (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 13.0 12.0 11.0 Ad 10.0 J

O 9.0 L

-j 8.0 7.0 6.0 5.0 0

5 10 15 20 25 30 35 40 45 50 55 AVERAGE PLANAR EXPOSURE (GWdIMT)

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CP&L Nuclear Fuels Management Safety Analysis B1C14 Core Operating Limits Report Design CaIc. No. 1121-0604 Page 16, Revision 1 Figure 4 Fuel Type GE13-P9DTB402-13G6.0/I1G2.0-10OT-146-T (GE13)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 13.0 12.0 11.0 E 10.0 CD

-j CL 9.0 8.0 7.0 0

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

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No. 1 B21-0604 Page 17, Revision 1 Figure 5 Fuel Type GE14-PlODNAB416-17GZ-1OOT-150-T-2496 (GE14)

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

C:

-J a.

9.0 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)

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No. 1B21-0604 Page 18, Revision 1 Figure 6 Fuel Type GE14-PIODNAB425-16GZ-10OT-150-T-2497 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 2:

I-S 0L 9.0 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 (GWdIMT)

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Caic. No. 1B21-0604 Page 19, Revision I Figure 7 Fuel Type GE14-PlODNAB438-12G6.0-1OOT-150-T-2498 (GE14)

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

E C,

-J

'1 9.0 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)

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Cale. No 1B21-0604 Page 20, Revision 1 I

Figure 8 is Not Used I

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No. 1B21-0604 Page 21, Revision 1 Figure 9 GE13 and GE14 Flow-Dependent MAPLHGR Limit, MAPLHGR(F) 1.10 1.05 1.00 0.95 0.90 0IL tL

< 0.85 0

'I 0.80 IL W,

I 0.75 a.

a 0.70 a)

M 0.65 0

U: 0.60 0.55 0.50 0.45 0.40 F

.I I I I I

I

_ This Figure is Referred To By Technical Specifications 3.2.1 and 3.4.1 I -

I -

. -

A Two Loop Operation Limit 9,

I I I I I I I I Max Flow = 102.5%

i f I 1

107% -

112% -

117% ~

I I N

/

1. 1

/

/

'K

/

E t

tI 4- -**--

t -**

I-r

4-1

t I

4-7/ /

_ Single Loop Operation Limit I-

_ -7T' 7

MAPLIiGR(F) = MAPFAQ

• MAPLI]GRM MAPLIIGRsTD = Standard MAPLIIGR Limits A A MAPFACF(F) = Minimum (1.0, AFWCIIOO+BF)

Wc = % Rated Core Flow AF And BF Are Fuel T)yp Depcndent Constants Given Below:

Max CorC Flow

(% Rated)

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

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design CaIc. No. 1B21-0604 Figure 10 Page 22, Revision I GE13 and GE14 Power-Dependent MAPLHGR Limit, MAPLHGR (P) 1.05 1.00 0.95 0.90 0.85 n.

V E

0.80 2

0.75 (U

L-a 0.70

-jG-

< 0.65 r_

0.60 a.

0.55 a,

0 0.50 0.45 0.40 0.35 0.30 Ths Fiureis Referred'T y_

Technical Specifications 3.2.1, 3.4.1 and 3.7.6 ToLop Operation UXUfT~

-w-

_ Single Loop Operation Limit I i Core Flow < 50%

MAPLHGR(P) = MAPFACp

• MAPLHGRSTr Turbine Bypass I MAPLHGRsTD = Standard MAPLHGR Limits Operable or Inoperable For P < 23%:

No Thermal Limits Monitoring Required 1

T-T_ r For 23% < P < 26%:

For Core Flow < 50% & Turbine Bypass Operable or Inoperable

-II I

MAPFACp = 0.567 + 0.0157 (P-26%)

l> 50%

For Core Flow > 50% & Turbine Bypass Operable or Inoperable Bypas ore ow

_MAPFACP = 0.433 + 0.0063 (P-26%)

/ Z Turbine Bypass For 26% < P < 87.5%

S Operable or MAPFACp = 1.0 + 0.005224 (P-100%)

Inoperable For P > 87.5%

l l

MAPFACp = 1.0 I 1 1 C l~~i I 1 I I I I I I 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Cafc. No. 1 B21-0604 Page 23, Revision 1 Figure 1 1 GE13 and GE14 Flow-Dependent MCPR Limit, MCPR(F) 1.80 1.70 1.60 IL a

1.50

E 1.40 1.30 1.20 20 30 40 50 60 70 80 90 100 110 120 Core Flow % Rated)

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CP&L Nuclear Fuels Mgmt. & Safety Analysis B1C14 Core Operating Limits Report Design Calc. No. I B21-0604 Figure 12 Page 24, Revision 1 GE13 and GE14 Power-Dependent MCPR Limit, MCPR (P) 3.80 3.70 3.60 -

3.50 3.40 S

3.30J to('4 v

3.20 9L VI 3.10 to C 3.00 2.90 i

2.80 IL o

2.70 o

2.60-2.50 2.40 2.30 2.20 Al 2.10 tL 2.00 E. 1.90 1.80 1.70 1.60 o

1.50 cL 1.40 1.30 Ca c:

1.20 1.10 1.00

-OLMCPR I

t j4=

l-Rated MCPR Multiplier (Kp)

I I

I I

I I

jf_J-L___

Core Flow > 50%1 Turbine Bypass Operable or I-Inoperable I

I I

I I

I I~

IT-l

\\~ *,lCore Flow < 50%]

Turbine Bypass Operable or Inoperable

-z<=~~-

Operating Limit MCPR(P) = Kp4Operating Limit MCPR(100)

For P < 23%:

No Thermal Limits Monitoring Required No Limits Specified For 23% <P < PypAss:

Where PBypAss = 26%

For Core Flo > 50% & Turbine Bypass Operable or Inoperable OLMCPR(P)= [ 3.15+ 0.0933(26% - P)]

For CoreFlow < 50% & Turbine Bypass Operable or Inoperable OLMCPR(P) = [2.36 + 0.0700(26% - P)]

For 26%<P<45%:

Kp= 1.28 + 0.0134 (45% - P)

For 45% < P < 60%:

Kp = 1.15 + 0.00867 (60% - P)

For 60% < P < 87.5%

Kp = 1.00 + 0.00375 (100% - P)

For 87.5% < P < 100%

Kp = 1.00 + 0.0020 (100% - P) i

~~~i i~Y I

I I

I I

This Figure is Referred To By Technical Specification 3.2.2, 3.4.1, 3.7.6

_~~~~~~~

I I

I I

I I

I I

I_

20 25 30 35 40 45 50 PBYPASS 55 60 65 70 75 80 85 90 95 100 Power % Rated)

A CP&L

,. t9gU t-eW:

.r.

NGG Nuclear Fuels Mgmt. Safety Analysis B1C14 Core Operating Limits Report Figure 13 Stability Option IlIl Power/Flow Map Design Cale. No. 1B21-0604 Page 25, Revision 2 OPRM Operable, Two Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 110.0 100.0 90.0 80.0 70.0 0

li 60.0 50.0 40.0 30.0 20.0 10.0 0.0 I*

I

.I 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 BIC14 Core Operating Limits Report Figure 14 Stability Option IlIl Power/Flow Map Design Calc. No. 1B21-0604 Page 26, Revision 2 OPRM Inoperable, Two Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 0

0.

120.0 110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 Minimum IM ELLL)

Core Power Flow.

M Ibethr 100 76.19 09 75.04 98 73.89 97 72.75 96 71.61 95 70.49 94 69.36 93 66.25 92 67.13 91 6.03 90 64.93 89 63.63 88 62.74 87 81.86 6 6 6 o.

5 6 85 59.50 84 58.43 8s 57.37 82 56.31 e1 55.25 80 54.20 79 53.16 7

52.12 77 51.08 76 50.05 75 49.02 74 48.00 73 4.98 72 4.96 71 44.96 70 43.94 69 42.94 6e 41.94 67 40.95 6e 39.9 65 38.97 84 37.99 63 37.01 62 36.04 e1 35.06 6o 34.10 59 33.13 58 32.17 P41 etlmum fIC F )

C or.

flow.

M Ib/ehi 80.4 7 60.47 80.4 7 80.47 80.47 80.47 80.47 80.47 80.47 80.47 80.47 80.47 80.51 80.60 60.70 80.79 80.90 81.08 81.21 81.67 81.83 81.98 62.13 82.29 82.44 82.60 82.75 82.91 83.06 83.21 83.37 83.52 82.68 83.83 83.99 84.14 84.29 84.45 84.60 84.70 a 0,.

r '

I 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

CP&L Imuclear Fuels Mgmt. Safety Analysis B1C14 Core Operating Limits Report Figure 15 Stability Option IlIl Power/Flow Map Design Calc. No. 1B21-0604 Page 27, Revision 1 120.0 110.0 100.0 90.0 80.0 70.0 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 tH R. J l

APIRM STPcram 1

rmviae Region I

i s.*'

t

,i

__ ill mit I',,I i

,,,I.:I

.. lti'4l',i,!l 4~gF LI '.*i 11.

. 1 I;~~

.PRi -

...io. ; ! ! i~~ T~! 1i~

444 Caurl 28% Minimum Pump S mum V

PCl.T'1T Un

t-

.1 1

-~45 Mlblhr Max Core Flow 0

60.0 Minimum Mailmum (M LLLI (ICP)

Core Core Power

Plow, Plow, M Ibl/hr M lbshr 100 76.19 a0.47 99 75.04 80.47 98 73.89 80.47 97 72.75 0.47 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 60.47 90 64.93 80.47 9

63.83 80.47 86 62.74 80.47 87 61.66 80.51 66 60.58 80.80 65 59.50 90.70 84 58.43 60.79 3

57.37 0.90 82 56.31 61.05 81 55.25 81.21 80 54.20 81.36 79 53.16 81.52 78 52.12 81.67 77 51.08 81.83 76 50.05 81.98 75 49.02 62.13 74 46.00 62.29 73 46,98 62.44 72 45.96 e2.60 71 44.95 92.75 70 43.94 82.91 e9 42.94 83.06 8

41.94 83.21 67 40.95 83.37 6

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 84.29 60 34.10 84.45 59 33.13 84.60 58 32.17 84.70 50.0 40.0 30.0 20.0 10.0 0.0 0.0 7.7 15.4 23.i 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 j CP&L A

R.

e Oeru E ~ ' &-J 90 100 110 120 %CoreFlow

CP&L Nuclear Fuels Mgmt. Safety Analysis Figure 16 Design CaIc. No. 1B21-0604 BIC14 Core Operating Limits Report Stability Option il Power/Flow Map Page 28, Revision 1 OPRM Inoperable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120 M Inim um M aIm u m T.

tv

~~h~'

ore Coro 1 10 t4 AR SPSca 90 Bu-fer Region/<4++

SP Rok se 71.6l 80.47

.vgg B -

Immedlate Ex4 X

g W

K R

9 i f l 4 -s l Z 1

t s 1 6~~~~9 6.03 80.4*7 80

• . I A

1 uI C A S

i **SE.

i

I gig;;

I1.UStl~

l 90 64.6 80.4 t.L 60

- m X

m g g

3

[l-!![

1 i

s l [-

8i 8-.3 0.47 700 S.t I

I 'I 88" 82.7 I I 25 80.7 5% Buffer Region, STP Rod 7 ~~~~~~~~~~~~~~~~~7 1.6 8 0.451 Block il t--[

ll i

85 5

80. 7 g Circula9on g X t [li i S4 §0tg Ninirnurn Power Une w W B 5

7 0

9 80 3

.9 3x'ki-H L

80 5 '2 3

1. 7 diate Exit n~r, i

4,lji aI;I I *..44.

7 53 81.5 4.j 4.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

I 75~~~~~~~~~~~~4.

49.02 621 0

7.7 15.4 23.1 30.8 7480 8

9 4 7 0.4t 73 43.58 2

8.4 Region A Manual SCRAM i.OPM-abedegin

'I

. t1H 944 830 iet; lzt i' 1.4 rt'ril.

68 4.4 32 10 ip 12%Mnmm upSed174 Mbh a

oeFlw8 60 41 70 -

• HiN as d

50 64.29 0

7.7 15.4a23.1 30.8 38.5 46.2 5.9 6

63 77 87

9.

h Cr F

o 20 30 40 50 70 80 ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~:

J 100 110 120%C2ore1

.low

~~~~~~

1~~~~~~i 3

NGG Nuclear Fuels Mgmt. Safety Analysis Figure 17 Design Caic. No. 1 B21-0604 BIC14 Core Operating Limits Report Stability Option I Power/Flow Map Page 29, Revision 2 OPRM Operable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 ii.

I-Yk*"

h i~~~~~s~~t~~4.lh TV II~~~'~~"~

M nimurm Maeximumn

?"

Jr', 1~~~~~~~~~~~~~~~~4'-

~~~~~~(M EL LL)

(IC F) 100 0 ~~~~~~~~m tt+/-L~~

,~

r~

i.ti AR T

o lc M lb aIh r M lb a Ih v 4~~~- ~~~~t~~~1 14 4

9.3 8.4 800 90 64.93 80.47~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

076.

0.

7000 0 4

O:

hi..

I 84 58.4U-380 9 PI 4 ~

~

4~+/- 4

~~41-4.

-iA' 1

,.~.i fl:

+.i 65.0 1

40 0 MELLL Line

______~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~7049 o4

~~~' ~~~~~"

. ~~~~~~~~

72 4~~~~~056 82.60 70 4.94 3

62.91

--4 0"4f7a.

67 0.543.7 Scra

--i +4 f~~~~~~~~~~~~~~~~~~~

a 6

3 9 83.83 m

_Avoidance Reg6a 30 839 44 HI~~~.4' 1' 4 40 T1 1

506 842 70.0

44 4--" t

.4 A.

~

~

~

60 4.0 8.4 56~~~~~~~~~~~~~~~~~~~~~~~~~~~~~a 321 7 84.70 00 7.7 154 231 308 385 462 53.9 61.6~4-69 7

47 94 Mb/h"r~o 0

10 20 30 40 S0 60 70 80 90 100 110 120 %Core Flow

NGG Nuclear Fuels Mgmt. Safety Analysis B1C14 Core Operting Limits Report Figure 18 Stability Option IlIl Power/Flow Map Design Caic. No 1B21-0604 Page 30, Revision 2 OPRM Inoperable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120 I

3 0

0.

++-

Til

.?i f i-l - Ji M I I u

M stXit u r (M 211.1)

(ICF 4 !

APRM STP Scram Core Core l~~~~~~~~~~iwl~~~~~~~~~~~~

ai wt a r°

Flow, la~.

A

'a 2

APRM STP Rod Block s

M lbehr M lb*/hr 9oo 727 80.4 7 g5 704 80.4 7 94 _ i. t.;,7 8 9 8 0.4 7 4A..

9 66.03 8 0.4 7

. *"i i t. 1

.. ; t l 1 1 i.i.

R4 tq t.t,$

a843 5

7.3 8 0 9 0.7

+, o o,;

_s~nLi~i_77 51.08 81.83

_ : i ; ' n.1 !..... 1 ti j, rJ j-;3 0

O.:7 402at

,7 80.05 81.9 i4 d

72 4 5 8280

~~-j I

92

a. ;-

-:-;j4j>;_

71 4

a20 75 70 4394 82t.9 9

0.9

83. 7 1W'

' ?"~ 8 '.

tt "4

j*

~

8 27 4.8 83.27

'j.4 64 37.99 8S3.830,4

.Minimum Power Lne $= i.+t.t 33.t839 6_

...=e=.....

.s 36.4 80 41

.t:31A*~. -

60s Xi~t!

• 34.*

eo 34.0to 84.45 58 327 8.70 61.6 69.3 77 84.7 92.4 Mlbs/hr Core Flow t

0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 0

10 20 30 40 50 60 70 80 90 100 110 120

% Core Flow