ML060950121

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Brunswick, Unit 1 Cycle 16 Core Operating Limits Report, March 2006
ML060950121
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 03/22/2006
From: Aissa M
BWR Fuel Engineering
To:
Office of Nuclear Reactor Regulation
References
BSEP 06-0034 1B21-1081
Download: ML060950121 (31)
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BSEP 06-0034 Enclosure 1 Brunswick Unit 1, Cycle 16 Core Operating Limits Report, March 2006 I--PGN Nuclear Fuels Mgmt. & Safety Analysis B 1 C1 6 Core Operating Limits Report Design Calc. No. 1B21-1081 Page 1, Revision 0 BRUNSWICK UNIT 1, CYCLE 16 CORE OPERATING LIMITS REPORT March 2006 U Prepared By: az2,4 Mourad Aissa Approved By:: _ _ _ _ _Date: __ 2____Date: 3/*Z/C Mikhael A. Blom Supervisor BWR Fuel Engineering PGN Nucld.ar Fuels Mgmt. & Safety Analysis BIC16 Core Operating Limits Report Design Caic. No. 1B21-1081 Page 2, Revision 0 LIST OF EFFECTIVE PAGES Page(s)Revision 1-30 0 PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. lB,21-1081 BIC16 Ccre Operating Limits Report Page 3, Revision 0 TABLE OF CONTENTS Subiect Page Cover.......................................................................................................................................................I List of Effective Pages ...............................

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

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

4 List of F igures ...............................

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

5 Single Loop Operation

...............................

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

6 Feedwater T emperature Reduction

...............................

7 APLHGR Limits ...............................

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

7 RBM Rcd Block Instrumentation Setpoints

...............................

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

8 References

...............................

9 PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. IB21-1081 BIC16 Co:-e Operating Limits Report Page 4, Rexision 0 CAUTION References to COLR Figures or Tables should be made using titles only; Figure and Table numbers may change from cycle to cycle.LIST OF TABLES Table Title Page Table 1: MCPR Limits ...................................................................

10 Table 2: RBM System Setpoints

...................................................................

1 I 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: APLHGR Limit Versus Average Planar Exposure .........................................

20 Figure 9: GE14 Flow-Dependent MAPLHGR Limit, MAPLHGR(F)

.........................................

21 Figure 10: GE14 Power-Dependent MAPLHGR Limit, MAPLHGR(P)

.22 Figure 11: GE14 Flow-Dependent MCPR Limit, MCPR(F) .23 Figure 12: GE14 Power-Dependent MCPR Limit, MCPR(P) .24 Figure 13: Stability 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 III Power/Flow Map: OPRM Operable, Single Loop Operation, 2923 MWI .27 Figure 16: Stability Option HI Power/Flow Map: OPRM Inoperable, Single Loop Operation, 2923 MWt ... 28 Figure 17: Stability Option HI Power/Flow Map: OPRM Operable, FWTR, 2923 MWt ..............................

29 Figure 18: Stability Option HI Power/Flow Map: OPRM Inoperable, FWTR, 2923 MWt ............

................

30 PGN Nucl ar Fuels Mgmt. & Safety Analysis BIC 16 Core Operating Limits Report Design Calc. No. IB21-1081 Page 5, Revision 0 Introduction and Summary This COLR revision was performed to support Brunswick Unit 1, Cycle 16 operation at up to 2923 MMt. The main changes are those associated with the thermal limits and Power-Flow maps.This report provides the values of the power distribution limits and control rod withdrawal block instrumentation setpoints for Brunswick Unit 1, Cycle 16 as required by TS 5.6.5.OPERATING LIMIT REQUIREMENT 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 e:;tablished 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: E ATING LIMIT REQUIREMENT 2 DG Interim Corrective Action Stability Regions TS 3.3.1.1 LCO Conditionj This report conforms to Quality Assurance requirements as specified in Reference

1.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Caic. No. 1B2 1-1081 BIC16 Core Operating Limits Report Page 6, Revision 0 Single Loop Operation Brunswick Unit 1, 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, and 3.2.2. The applicable limits are: LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) Limits: per Reference 1, the Figures 9 andlO 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 1 and Figures II and 12, the MCPR limits presented apply to SLO without modification.

Various indicators on the Power/Flow maps are provided not as operating limits but rather as a convenience for the operators:

a single loop operation (SLO) Entry Rod Line is shown on the two loop operation maps to avoid regions of instability in the event of a pump trip; a maximum core flow line is shown on the single loop operation maps to avoid vibration problems; and 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 (LCO 3.3.1.1, Reactor Protection System Instrumentation Function 2.b (Average Power Range Monitors Simulatel Thermal Power -High Allowable Value).Inoperable Main Turbine Bvpass Svstem Brunswick Unit 1, 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.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 ME-OD range and up to 110 F rated equivalent feedwater temperature reduction.

The system response time assumed by the safety analyses from event initiation to start of bypass valve opering is 0.10 seconds, with 80% of the bypass flow capacity 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 I as shown in Figure 10, TBPOOS does not require an additional reduction in the MAPLGHR(P) limits, 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 as shown in Figure 12, as the Turbine Bypass Operable and Inoperable limits are identical.

TBPOOS requires increased MCPR limits, included in Table 1.

PGN Nucl -ar Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-1081 BIC16 Core Operating Limits Report Page 7, Revision 0 Feedwater Temperature Reduction A variatizn within 10 0 F of nominal feedwater temperature (NFWT) has been evaluated as in compliarce with normal operating limits. A FWT reduction of >1 0F together with reactor power >30% RTP requires the use of Reduced FWT MCPR limits (Table 1) and Stability Option III limits (Figures 17 and 18). For reactor power < 30% RTP, only NFWT MCPR limits are used.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 I 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 Ihe governing limit. Figure 10 was revised to include updated limits from Reference 1 1 that are based on a 650%o core flow separator for the power range 23% P < 40% RTP.MCPR Limits The Scram Speed MCPR OPTION A, 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(TRACG) methodology and GEXL-PLUS critical power correlation described in GESTAR-II (Reference 2), and are consistent with a Safety Limit MCPR of 1.1 I 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 11 and MCPR(P) determined from Figure 12 is used to determine the governing limit. Figure 12 was revised to include updated limits from Reference 11 that are based on a 65% core flow separator for the power range 23% P < 40% RTP. All MCPR limits presented in Table 1, Figure 1 1 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 to be consistent with the bases of the ARTS program and the determination of MCPR limits with the GEMINI(TRACG) methodology and the GEXL-PLUS critical power correlation described in GESTAR-II (Reference 2). Reference 8 revised certain of these setpoints to reflect changes PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. IB2 1-1081 BIC16 Core Operating Linmits Report Page 8, Revision 0 associated with the installation of the NUMAC PRNM system. The table also includes information regarding required operability of the RBM, consistent with Technical Specification Table 3.3.2.1-1.

Stability Option III Brunswick Unit 1 has implemented BWROG Long Term Stability Solution Option III (Oscillation Power Range Monitor-OPRM) with the methodology 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. If desirable, Table 3 would support higher stability limits for various MCPR operating limits greater than the least limiting Table I AOO OLMCPR values, but the suggested stability setpoints are bounded by Table 1. Table 3 shows that OLMCPR(SS) is never as limiting as Figure 1 1 for any listed OFRM setpoint (Amplitude Setpoint Sp). Table 3 also shows that OLMCPR(2PT) is never as limiting as Table 1 for an OPRM setpoint of 1.13. 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 1.13 for Cycle 16.Per Table 3-2 of Reference 6, an Sp value of 1.13 supports selection of a Confirmation Count Setpoint Np of 15 or less.Six Power/Flow maps for use at up to 2923 MWt (Figures 13-18) were developed based on References 1 and 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. All six maps illustrate the region ofthe power/flow map above 25% power and below 60% drive flow where the system is required to be enabled.The maps supporting an operable OPRM function 2.f (Figures 13, 15 and 17) 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. Figures 13 and 15 differ only in that the Figure 15 that supports SLO, indicates the maximum allowable core flow at 45 Mlbs/h*, 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.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. I1B2 -108I BIC16 Core Operating Limits Report Page 9, Revision 0 References

1) BNP Design Calculation 11B21-1081; "Preparation of the BlCl6 Core Operating Limits Report," Revision 0, March 2006.2) NED13-2401 1-P-A; "General Electric Standard Application for Reactor Fuel," (latest approved versicn).3) NEDC-31624P, "Loss-of-Coolant Accident Analysis Report for Brunswick Steam Electric Plant Unit ] Reload 15 Cycle 16," Supplement 1, Revision 9, December 2005.4) 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 0B21-1015, Revision 5, "BNP Power/Flow Maps for Stability Option III," February 2006.8) Design Calculation IC51-0001 Revision 2, "BNP Power Range Neutron Monitoring System Setpoint Uncertainty and. Scaling Calculation (I-C51-APRM I through 4 Loops and 1 -C5 :1 -RBM-A and B Loops," October 2003).9) NED]E,-32906P-A, Revision 1, "TRACG Application for Anticipated Operational Occunrences (AO0) Transient Analyses," April 2003.10) GE-NE-0000-0022-8180-RO, "Brunswick Nuclear Station TRACG Implementation for Reload Licensing Transient Analysis," February 2004.1) GE-'NE-0000-0036-9469-R0, Revision 0, "Brunswick 1 and 2 Off-Rated Analyses Below the PLU Power Level," June 2005. (Supplemented by GE-NE-0000-0051-4200-RO, "Brunswick Unit 1 and 2 Power Dependent Limits Below P-Bypass at 65% Core Flow", March 2006).

PGN Nuclear Fuels Mgmt. & Safety Analysis BlC16 Core Operating Limits Report Design Calc. No. IB 21-1081 Page 10, Revision 0 Table 1 MCPR Limits Pressurization Transient MCPR Limits 100% Power OLMCPR Turbine Feedwater Scram Exposure Range: Exposure Range: Bypass Temperature Fuel Type Speed System Normal? MCPR BOC to EOR-4130 MWd/MT Operable?

Option EOR -4130 MWd/MT to EOC Operable Normal GE14 A 1.52 1.56 B 1.34 1.38 Operable Reduced GE14 A 1.52 1.56 B 1.34 1.38 Inoperab'e Normal GE14 A 1.61 1.61 B 1.43 1.43 Inoperab'e Reduced GE14 A 1.70 1.70 B 1.52 1.52 This Table is referred to by Technical Specifications 3.2.2, 3.4.1 and 3.7.6.

PGN Nuclear Fuels Mgmt. & Safety Analysis BIC16 Core Operating Limits Report Design Calc. No. IB2 1-1081 Page 11, Revision 0 Table 2 RBM System Setpoints Setpointa Trip Setpoint Allowable Value Lower Power Setpoint (LPSP ) 27.7 29.0 Intermediate Power Setpoint (IPSP ) 62.7 64.0 High Power Setpoint (HPSP ) 82.7 5 84.0 Low Trip Setpoint (LTSPc) 114.1 114.6 Intermediate Trip Setpoint (ITSPc) 108.3 5 108.8 High Trip Setpoint (HTSPC) 104.5 105.0 RBM Time Delay (td2)N 2.0 seconds 2.0 seconds a RBM Operability requirements are not applicable:

(1) if MCPR 2 1.70; or (2) if MCPR a 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).\

PGN Nuclear Fuels Mgmt. & Safety Analysis BIC 16 Core Operating Limits Report Design Calc. No. IB21-1081 Page 12, Revision 0 Table 3 PBDA Setpoints OPRM Setpoint OLMCPR(SS)

OLMCPR(2PT) 1.05 1.2093 1.0914 1.06 1.2302 1.1103 1.07 1.2519 1.1298 1.08 1.2743 1.1501 1.09 1.2975 1.1711 1.10 1.3216 1.1928 1.11 1.3455 1.2144 1.12 1.3702 1.2367 1.13 1.3959 1.2598 1.14 1.4225 1.2839 1.15 1.4502 1.3089 Acceptance Criteria Off-rated OLMCPR @ Rated Power 45% Flow OLMCPR PDBA Setpoint Setpoint Value Amplitude Sp 1.13 1.14 1.15 Confirmation Count Np 15 16 16 This Table is referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1 -1).

PGN Nuclear Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1 B21 -1OE.1 Page 13, Revision 0 Figure 1 Fuel Type GE14-PIODNAB416-17GZ-1OOT-150-T-2496 (GE14)Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0/1This Figure is Referred To By ITechnical Specification 3.2.1 _7 9.0 1-4§-_j 8.0 I 0~7L< 7.0, Exposure Limit (GWd/Mt) (kW/ft)0.00 9.27 0.22 9.33 1.10 9.44 2.20 9.59 3.31 9.76 4.41 9.93 5.51 10.11 6.61 10.30 7.72 10.50 8.82 10.71 9.92 10.91 11.02 11.12 12.13 11.31 13.23 11.36 14.33 11.35 15.43 11.34 16.53 11.31 18.74 11.23 22.05 11.03 27.56 10.60 33.07 10.12 38.58 9.49 44.09 8.91 49.60 8.37 55.12 7.87 60.63 6.53 64.27 4.88\Permissible

_Region of Operation 6.0 1 5.0 1 4.0--S -P -S -S --S -S -S -0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

PGN Nuclear Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design CaIc. No. 1B21-10831 Page 14, Revision 0 Figure 2 Fuel Type GEl 4-PI ODNAB425-16GZ-1 OOT-1 50-T-2497 (GE1 4)Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 N -N N I N N I I I N

  • S This Figure is Referred To By f Technical Specification 3.2.1 l l --l- l4-l//9.0 I-i I-_M 8.0-J Exposure Limit (GWd/Mt) (kW/ft)0.00 9.26 0.22 9.33 1.10 9.43 2.20 9.57 3.31 9.72 4.41 9.88 5.51 10.04 6.61 10.21 7.72 10.34 8.82 10.48 9.92 10.58 11.02 10.70 12.13 10.81 13.23 10.80 14.33 10.79 i15.43 10.79 116.53 10.79 18.74 10.77 22.05 10.65 27.56 10.28 33.07 9.84 38.58 9.39 44.09 8.92 49.60 8.42 55.12 7.89 60.63 5.67 62.29 4.91 Permissible Region of --Operation I I\7.0 4-i 6.0 Il 5.0 4-4.0* -N -N S N I S S 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

PGN Nuclea- Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1B21-1 011 Page 15, Revision 0 Figure 3 Fuel Type GE14-PlODNAB438-12G6.0-10OT-150-T-2498 (GE14)Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0.-, 0-J 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)

PGN Nuclear Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1B21-1081 Page 16, Revision 0 Figure 4 Fuel Type GE14-PIODNAB413-16GZ-IOOT-150-T-2660 (GE14)Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 -9.0 E=M -2 8.0 CD z 0~7.0 6.0 5.0 4.0-N -S -* -* -N -N -N -N -N -N -N -N -N -N- --& -A -This Figure is Referred To By Technical Specification 3.2.1 If I t i Exposure Limit (GWd/Mt) (kW/ft)0.00 9.57 1.10 9.66 2.20 9.77 3.31 9.92 4.41 10.08 5.51 10.26 6.61- 10.44 7.72 10.59 8.82 10.74 9.92 10.87 11.02 11.00 12.13 11.12 13.23 11.15 14.33 11.16 15.43 11.16 15.99 11.16 16.53 11.16 18.74 11.13'21.09 11.02 22.05 10.98 27.56 10.57 33.07 10.15 38.58 9.65 44.09 9.12 49.60 8.59 55.12 8.04 60.63 6.48 63.50 5.18 64.16 4.88 K~I Pernissible Region of -\ I Operation I~ I I 4-N -N p -N * -N -N -* -N -N -0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWd/MT)

PGN Nuclear Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1B21-1081 Page 17, Revision 0 Figure 5 Fuel Type GE14-PIODNAB429-18GZ-IOOT-150-T-2661 (GE14)Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 11.0 -10.0 -9.0 -8.0-a-3 7.0 a--~ ~ ~ , i , .-P .P This Figure is Referred To By Technical Specification 3.2.1 _/l/I I I Exposure Limit (GWd/Mt) (kW/ft)0.00 8.89 1.10 9.05 2.20 9.16 3.31 9.29 4.41 9.43 5.51 9.55 6.61 9.68 7.72 9.81 8.82 9.94 9.92 10.08 11.02 10.23 12.13 10.28 13.23 10.31 14.33 10.34 15.43 10.37 15.99 10.39 16.53 10.41 18.74 10.49 21.09 10.53 22.05 10.55 27.56 10.35 33.07 9.89 38.58 9.43 44.09 8.95 49.60 8.45 55.12 7.92 60.63 5.83 62.51 4.97_i *--Permissible Region of Operation 6.0 1 5.0 1 I i I I 4.0-4 S *- ----~ m -~I 0 5 10' 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/MT)55 60 65 70 PGN Nuclear Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1B21-1 0l1 Page 18, Revision 0 Figure 6 Fuel Type GE14-PIODNAB437-12G6.0-10OT-150-T-2662 (GE14)Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0* a .a * -* -.-.-.-.-.-.-.-.-S -This Figure is Referred To By 1 Technical Specification 3.2.1 l --l-l l l 4-7k-,. --I. --10.0 l-/9.0 I.-E 0:-i C, 8.0 -7.0 Exposure Limit (GWd/Mt) (kW/ft)0.00 9.06 1.10 9.20 2.20 9.31 3.31 9.43 4.41 9.55 5.51 9.68 6.61 9.81 7.72 9.95 8.82 10.09 9.92 10.23 11.02 10.38 12.13 10.45 13.23 10.48 14.33 10.51 15.43 10.54 16.00 10.55 16.53 10.56 18.74 10.56 21.09 10.49 22.05 10.47 27.56 10.20 33.07 9.87 38.58 9.42 44.09 8.95 49.60 8.45 55.12 7.91 60.63 5.56 62.02 4.91\N\*Permissible Region of Operation 6.0 5.0 4.0 4 S

  • S a 9 a 9 a p a I a p a S a; x 0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/MT)55 60 65 70 PGN Nuclear Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1B21-1OE1 Page 19, Revision 0 Figure 7 Fuel Type GE14-PlODNAB407-16GZ-10OT-150-T-2853 (GE14)Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 F I-M=i it 0~9.0 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)

PGN Nuclear Fuels Mgmt. & Safety Analysis B1 C1 6 Core Operating Limits Report Design Calc. No. 1B21-1081 Page 20, Revision 0 Figure 8 Fuel Type GE14-PIODNAB425-18GZ-10OT-150-T-2854 (GE14)Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 11.0 10.0 9.0 3 8.0 7.0 0~6.0 5.0 4.0 CI 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdIMT)

PGN Nuclea' Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1B21-1 031 Page 21, Revisior, 0 Figure 9 GE14 Flow-Dependent MAPLHGR Limit, MAPLHGR(F) 1.10 1.05 1.00 I I I I_ This Figure is Referred To By Technical Specifications 3.2.1, 3.4.1 and 3.7.6 ITwo Loop Operation Limit t/-I I = I I I 1 I I 0.95 _.fI Max Fl l02.5% -_107% -112% -117% -/K 1-11/-III Ilk c 0.90 0.8 U-a-< 0.85 n 12 C 0.80 U-=0.75 W 0~= 0.70 0 EL M a 0.65 0 C i0 0.60 0.55 0.50 0.45 0.40 K/-I -I I i --///00>0_ *_ ._ ._ .-j -.]-FSingle Loop Operation Limitj-2n--7-.rT7n

.1 MAPLHGR(F)

= MAPFACF

= Standard MAPLHGR Limits MAPFACF(F)

= Minimum (1.0, AFWC/IOO+BF)

Wc = % Rated Core Flow----AF And BF Are Fuel Type Dependent Constants Given Below: Max Core Flow-(% Rated) A F BF 102.5 0.6784 0.4861 107.0 0.6758 0.4574 112.0 0.6807 0.4214 117.0 0.6886 0.3828 I j 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 Core Flow (% Rated)

PGN Nuclear Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1B21-1081 Figure 10 Page 22, Revision 0 GE14 Power-Dependent MAPLHGR Limit, MAPLHGR (P)1.05 1.00 I I I j This Figure is Referred To By Technical Specifications 3.2.1, 3.4.1 and 3.7.6 0.954-i i I I I i I 1.W I I I 1 I I 0.90-0 0.85'U-CL<, 0.80 2 0.75 (U IL 0 0.70 I-j a.< 0.65 0 0.60-a)CL 0 0.55 I-0 a- 0.50.0.45*0.40 0.35 n qrn--+ -4 4 + -4 4 + -4 .4 -+ -_ --rTw Loop Operation r N 1\1 2<'~1 i Single Loop Operation Limit j*-1--*1- , -i -.I! -I- -I --I- -'Core Flow < 65% Turbine.-i Bypass Operable or Inoperable

--- -Th- f>4Z-I011 I I I I -I I ' 't I!;r--~ Core Flow > 65% -Turbine 1 Bypass Operable or Inoperable L MAPLHGR(P)

MAPFACp

  • MAPLHGRSTD MAPLHGRSTD

= Standard MAPLHGR Limits:orP<23%: No Thermal Limits Monitoring Required:or 23% s P < 26% & Turbine Bypass Operable or noperable:

For Core Flow < 50%: MAPFACp= 0.567 + 0.0157 (P-26%)For Core Flow < 65%: MAPFACp= 0.495 + 0.0130 (P-26%)For Core Flow > 65%: MAPFACp= 0.433 + 0.0063 (P-26%):or 26% s P < 40% & Turbine Bypass Operable or noperable:

For Core Flow 565%: MAPFACp = 1.0 + 0.005224 (P-100%)For Core Flow > 65%: MAPFACp = 0.634 + 0.0035 (P.40%)For P? 40%: MAPFACp = 1.0 + 0.005224 (P-100%)/4r I I I I I Core Flow < 50% -Turbine Bypass Operable or Inoperable

_0I_,-:-____-__-_-__-__-_J,:Core Flow < 65% -Turbine:Bypass Operable or Inoperable

aI---1----I----I----

\ Core Flow > 65% -Turbine l Bypass Operable or Inoperable I I 1 1 I I1.......-I V.V 20 24 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)Pbypass (26%)

PGN Nuclea Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1B21-1081 Page 23, Revision 0 Figure 11 GE14 Flow-Dependent MCPR Limit, MCPR(F)1.80 1.70 1.60 U-EL 1.50 1.40 1.30 1.20 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

PGN Nuclear Fuels Mgmt. & Safety Analysis B1C16 Core Operating Limits Report Design Calc. No. 1B21-1081 Page 24, Revision 0 Figure 12 GE14 Power -Dependent MCPR Limit, MCPR (P)r V a.vi N vI 0 M 04-J 0_i 0 Al a.-0 2'-J 0 0 a, C.)3.8000 3.7000 3.6000 3.5000 3.4000 3.3000 3.2000 3.1000 3.0000 2.9000 2.8000 2.7000 2.6000 2.5000 2.4000 2.3000 2.2000 2.1000 2.0000 1.9000 1.8000 1.7000 1.6000 1.5000 1.4000 1.3000 1.2000 1.1000 1.0000 OLMCPR Rated MCPR Multiplier (Kp),Core Flow > 65% -Turbine ' Operating Limit MCPR:---Bypass Operable or Inoperable OLMCPR(P)

= KpOLMCPR(100)

__ __ _ _ For P < 23%: No Thermal Limits Monitoring Required Core Flow < 65% -Turbine Bypass Operable or Inoperable For 23% < P < 26% & Turbine Bypass Operable\ _ _ -or Inoperable:

\ -__ -For Core Flow < 50%:[I r OLMCPR(P)=

[ 2.34+ 0.0700(26%

-P)]Core Flow < 50% -Turbine For Core Flow < 65%:* Byass perble r IoperbleOLMCPR(P)=

12.74+ 0.0967(26%

-P)]Bypass Operable or Inoperable rl For Core Flow > 65%:-_... .OLMCPR(P)=

[ 3.13+ 0.0900(26%

-P)]_\ --- L -- I l- -J-,K 7 Core Flow > 65% -Turbine

For Core Flow s 65%: OLMCPR(P)

= 1.88 + 0.0129 (40% -P),,__ ___ _ For Core Flow > 65%: OLMCPR(P)

= 2.10 + 0.0157 (40% -P)For 40s P < 45%: Kp= 1.28 + 0.0135 (45% -P)For 45% < P < 60%:lCore Flow < 65% -Turbine Kp = 1.18+ 0.00667 (60% -P)Bypass Operable or Inoperable For P 2 60%:----_ _ _ Kp =1.00 + 0.00450 (100% -P)l_ l_ l l l- l l l llThis Figure is Referred To By Technical Specification 3.2.2, 3.4.1, 3.7.6 Ii. ..j. .i. 2 20 21 30 Pbypass (26%)35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 13 Design Calc. No. 1B21-1081 B1C16 Core Operating Limits Report Stability Option III Power/Flow Map Page 25, Revision 0 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 "ll , (M ELLL) (IC F)APMT~rmC ore Co.re P owear F low, Flo.w, 110.0----

----- _APRM STP Rod Bock % M lb elh r M abs h r 17 0 0 7 681 9 1 A .7 600.' 9 9 7 1 .6 4 0 .4 7 30.073.89 0.95 397 8360.687 9 3 6 8 80.4 7 6W 3 I I 92 671 89047 2 1 3 6.0 8.084 6100 0 06 4 9 8428 60 2 341 840.457 5 33 13 84.60 s ntt 2 58 321 8470 70.0 H4 I I 86 61 35 08 840.290 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 C~t PGN Nuclear Fuels Mgmt. Safety Analysis Figure 14 Design Calc. No. 1B21-1081 B1C16 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 26, Revision 0 OPRM Inoperable, Two Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 1 4 1 IT. I J ~ V 44A 1 ' M 1 g 4 I:ii l lR .b APMT~rm(M EL LL) (IC F)100ore C ore 10.-!.T1 1 0 .X0 X 3lP o w e r Flow, Flow, APRM STP Rod; % M lbalhr M lbl -h r 1 76.1 9.1 847 100.0 99 7 .0 4 8 0.4 7 98 73 .8 9 8 0.4 7 90.0 90 63 8 3 .47 87 671.66 80.5 9006 60.58 8 0.80 85al 59.30 80 .470 38 5 8.43 80.479 2 6760.0 0 4 8001 5.20 3 810.367 5.78 63.12 81.67 70087 61.086 81.83 86t ~ 6 50.05 8 180.98 85I 5 49.502 820.130 40.0 Region80.7 73 467.398 820.44 72 5.965 82.60 30.0 egionB2- Imediae Exi 6la 7 40.5 316 83.372 20.0am ojI 0.5.10.075 369.042 842.143 0.0 o 58ImeiaeE 1 3.17 842.705 30.0 77 1. 31 3. 85 4. 39 16 6..00 4.79. 0Mb 4h Core Flow.9 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow PGN Nuclear Fuels Mgmt. Safety Analysis B1C16 Core Operating Limits Report Figure 15 Stability Option III Power/Flow Map Design Calc. No. 1 B21-1081 Page 27, Revision 0 OPRM Operable, Single Loop Operation, 2923 MWt I This Figure supports Improved Technical Specification 3.3.1.1and the Technical Requirements Manual Specification 3.3 3: 0 0.1 120.0 110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 Minim um M axim um (M ELLL) (ICF)C ore C ore Power Fiow, Fiow,% M ib shr M Ibs/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 80.70 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 81.52 78 52.12 81.67 77 51.08 81.83 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 83.21 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 84.29 60 34.10 84.45 59 33.13 84.60 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 PGN Nuclear Fuels Mgmt. Safety Analysis B1C16 Core Operating Limits Report Figure 16 Stability Option IlIl Power/Flow Map Design Calc. No. 1B21-1081 Page 28, Revision 0 OPRM Inoperable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1and the Technical Requirements Manual Specification 3.3 0 a.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 M inim um Maximum (MELLL) (IC F)C o re C o re Power Flow, Flow,% M Ibslhr M lb./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 90.47 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 80.70 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 81.52 78 52.12 81.67 77 51.08 81.83 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 83.21 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 84.29 60 34.10 84.45 59 33.13 84.60 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 PGN Nuclear Fuels Mgmt. Safety Analysis B1C16 Core Operating Limits Report Figure 17 Stability Option IlIl Power/Flow Map Design Calc. No. 1 B21-1081 Page 29, Revision 0 OPRM Operable, FWTR, 2923 MWt I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 I a 120.0 110.0 100.0 90.0 80.0 70.0 0 0.60.0 M Inim um M axim um (M EL L L) (IC F )C ore C ore P o w 9 r Flow, F lo w,# M lbalhr, M Ibalhr 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 80.70 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 81.52 78 52.12 81.67 77 51.08 81.83 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 83.21 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 84.29 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 23.1 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 C PGN Nuclear Fuels Mgmt. Safety Analysis B1C16 Core Operating Limits Report Figure 18 Stability Option IlIl Power/Flow Map Design Cale. No. 1 B21-1081 Page 30, Revision 0 OPRM Inoperable, FWTR, 2923 MWt I This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 31 I I~120.0 100.0 90.0 .80.0 ( ~ ~ ~ ~ ~ ~ ~ ~ ~ HL. 1 .a,_li T1 70.0 60.0-50.0 40.0 r o A -Manual SCRAM 300 Reon B -Immediate Exi 20.0 10.0 0.0 I -0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 M inim um M axim um (M ELLL) (IC F)Core Core Power Flow, Flow,% M Ib*/hr M ibslhr 100 76.19 8 0.47 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 .70 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 81.52 78 52 .12 81.67 77 51 .08 81 .83 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 .21 67 40 .95 83 .37 66 39 96 83.52 65 38.97 83.6 8 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 .70l _ _ _ _ ..._ ...84.7 92.4 Mlbs/hr Core Flow 0 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow c' U

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