ML040960082

From kanterella
Revision as of 22:35, 24 March 2020 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
to 1B21-0625, Brunswick, Unit 1, Cycle 15, Core Operating Limits Report.
ML040960082
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 03/01/2004
From: Dresser T, Galen Smith
Progress Energy Carolinas
To:
Office of Nuclear Reactor Regulation
References
1B21-0625, Rev 0
Download: ML040960082 (31)
v • d • e


Text

L PGN Nuclear Fuels Mgmt. & Safety Analysis Design Caic. No. 1B21-0625 B1 C15 Core Operating Limits Report Page 1, Revision 0 BRUNSWICK UNIT 1, CYCLE 15 CORE OPERATING LIMITS REPORT March 2004 Prepared Bjr Date: 3$L/Ao -

Tom Dresser Approved Date: 3< 1 I I

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C1 5 Core Operating Limits Report Page 2, Revision 0 LIST OF EFFECTIVE PAGES Page(s) Revision 1-30 0

PGN Nuclear Fuels Mgmt. &Safety Analysis Design Catc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 3, Revision 0 TABLE OF CONTENTS Subject Page Cover .1..............................

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 Feedwater Temperature Reduction ............................... 7 APLHGR Limits ............................... 7 MCPR Limits ............................... 7 RBM Rod Block Instrumentation Setpoints ............................... 7 Stability Option III ............................ s References ............................... 9

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 81 C1 5 Core Operating Limits Report Page 4, Revision 0 CAUTION References to COLR Figures or Tables should be made using titles only; figure and table numbers may change from cycle to cycle.

LIST OF TABLES Table Title Page Table 1: 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: APLHGR Limit Versus Average Planar Exposure ................................................................... 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 m Power/Flow Map: OPRM Inoperable, Two Loop Operation, 2923 MWt ....... 26 Figure 15: Stability Option m Power/Flow Map: OPRM Operable, Single Loop Operation, 2923 MWt ...... 27 Figure 16: Stability Option m 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

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 5, Revision 0 Introduction and Summary This COLR revision was performed to support Brunswick Unit 1, Cycle 15 operation at up to 2923 MWt. 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 15 as required by TS 5.6.5.

,OPERATIN LI.i 478of s-5 s >.--ir- ,; -X+i1 m 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 HI with an inoperable OPRM scram function, the following is also included in this report:

GLDW BWROG Interim Corrective Action Stability Regions I TS 3.3.1.1 LCO Condition I I This report conforms to Quality Assurance requirements as specified in Reference 1.

PGN Nuclear Fuels Mgmt. &Safety Analysis Design Calc. No. 1B21-0625 B1 C15 Core Operating Limits Report Page 6, Revision 0 Single Loop Operation Brunswick Unit 1, Cycle 15 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 I and Figures 11 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 Simulated Thermal Power - High Allowable Value).

Inoperable Main Turbine Bypass System Brunswick Unit 1, Cycle 15 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 110 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% 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 1 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 Nuclear Fuels Mgmt. &Safety Analysis Design Calc. No. 11B21-0625 B1C15 Core Operating Limits Report Page 7, Revision 0 Feedwater Temperature Reduction A variation within l1F of nominal feedwater temperature has been evaluated as in compliance with normal operating limits. A feedwater temperature reduction of > 10F requires the use of FWTR MCPR limits (Table 1) and Stability Option m limits (Figures 17 and 18).

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-II (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 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-il (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 Figure 11 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 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. 11821-0625 B1C1 5 Core Operating Limits 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 1 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 11 for any listed OPRM 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 15.

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 of the power/flow map above 25% power and below 60% 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/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 and 16) 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 EWTR is prohibited.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 9, Revision 0 References

1) BNP Design Calculation 1B21-0625; "Preparation of the BIC15 Core Operating Limits Report,"

Revision 0, February 2004.

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 14 Cycle 15," Supplement 1, Revision 8, February 2004.
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, Revision 2, "BNP Power/Flow Maps for Stability Option M,"

July 2003.

8) Design Calculation 1C51-0001 Revision 2, "BNP Power Range Neutron Monitoring System Setpoint Uncertainty and Scaling Calculation (1-C51-APRM I through 4 Loops and 1-C5 1-RBM-A and B Loops," October 2003
9) NEDE-32906P-A, Revision 1, "TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analyses," April 2003.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 10, Revision 0 Table 1 MCPR Limits This Table is referred to by Technical Specifications 3.2.2, 3.4.1 and 3.7.6.

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C1 5 Core Operating Limits Report Page 11, Revision 0 Table 2 RBM System Setpoints I

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

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 12, Revision 0 Table 3 PBDA Setpoints OPRM Set~6int ISS)~OLMCP2PT)l 1.05 1.2136 1.1343 1.06 1.2355 1.1548 1.07 1.2582 1.1760 1.08 1.2817 1.1980 1.09 1.3062 1.2209 1.10 1.3316 1.2447 1.11 1.3568 1.2682 1.12 1.3830 1.2927 1.13 1.4101 1.3181 1.14 1.4384 1.3445 1.15 1.4679 1.3720 AcseptanceCritn a' '7Of:OeDOLMCPR@  :  ;

45 4iRta oer ~

This Table is referred to by Technical Specification 3.3.1.1 (Table 3.3.1.1-1).

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 13, Revision 0 Figure 1 Fuel Type GE1 3-P9DTB405-5G6.017G5.0-1 OOT-1 46-T-2378 (GE1 3)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 14.0 13.0 12.0 11.0 1 10.0

%I-

-J I

Mj 9.0

-J IL 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 (GWd/MT)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Caic. No. 1B21-0625 B1 C1 5 Core Operating Limits Report Page 14, Revision 0 Figure 2 Fuel Type GE13-P9DTB402-13G6.O/lG2.0-10OT-146-T-2379 (GE13)

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

n 10.0 Ci a-M:

9.0 8.0 7.0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 AVERAGE PLANAR EXPOSURE (GWdWMT)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design CaIc. No. 1B21 -0625 BI C1 5 Core Operating Limits Report Page 15, Revision 0 Figure 3 Fuel Type GEl 4-P1 ODNAB416-17GZ-1 OOT-1 50-T-2496 (GE1 4)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 - p- p- p- p- p mipppm pm pm pm pm 11.0 -l l r.~4----- I I This Figure is Referred To By l Technical Specification 3.2.1

- P-

/ Exposure (GWdlMt)

Limit (kW/ft) x 10.0*

0.00 0.22 9.27 9.33

\

9.0 7 1.10 2.20 3.31 4.41 9.44 9.59 9.76 9.93 5.51 10.11 6.61 10.30 7.72 10.50 I.-~ 8.82 10.71 9.92 10.91

8.0 11.02 11.12 12.13 11.31 a- 13.23 11.36

-i 14.33 11.35 15.43 11.34 Permissible I 7.0 16.53 11.31 18.74 11.23 Region of 22.05 11.03 Operation 27.56 10.60 33.07 10.12 I I 6.0' 38.58 9.49 44.09 8.91 49.60 8.37 55.12 7.87 60.63 6.53 5.0 6427 4.88 j

II II II II 4.0 -l I mim-*-m-*-m*m *m hmirm 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 Design CaIc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 16, Revision 0 Figure 4 Fuel Type GEI 4-P1 ODNAB425-1 6GZ-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 9.0

-i 8.0 a-AS 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 Design Calc. No. 1 B21-0625 B1 C1 5Core Operating Limits Report Page 17, Revision 0 Figure 5 Fuel Type GE14-PIODNAB438-12G6.0-1OOT-150-T-2498 (GE14)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 11.0 10.0 9.0 r-C, 8.0

-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)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 18, Revision 0 Figure 6 Fuel Type GE14-PlODNAB413-16GZ-10OT-150-T-2660 (GE14)

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

_3 8.0 C,

3:x

-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)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 BI C1 5 Core Operating Limits Report Page 19, Revision 0 Figure 7 Fuel Type GE1 4-PI ODNAB429-1 8GZ-1 OOT-1 50-T-2661 (GE1 4)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure Pp 12.0 - Pm - - - - - I - m p P P .

A - - A - A A .

This Figure is Referred To By 11.0 Technical Specification 3.2.1 _

- - p- p- p Exposure Limit 10.0 lGWdIMt) (kW/ft) 0.00 8.89 1.10 9.05 2.20 9.16 X<-

3.31 9.29 4.41 9.43 9.0 I 5.51 9.55 k 6.61 9.68 7.72 9.81 8.82 9.94 9.92 10.08

i 8.0 rr I- 11.02 12.13 10.23 10.28 rM

-I 7.0 13.23 14.33 15.43 15.99 10.31 10.34 10.37 10.39 II Permissible Region of - _

16.53 10.41 Operation 18.74 10.49 21.09 10.53 22.05 10.55 6.0 27.56 10.35 33.07 9.89 38.58 9.43 44.09 8.95 49.60 8.45 5.0 1 55.12 7.92 _ _ _ __V 60.63 5.83 62.51 4.97 4.0 h I- U U I I I I I I I 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 Design Calc. No. 1B21-0625 B1 C1 5 Core Operating Limits Report Page 20, Revision 0 Figure 8 Fuel Type GE1 4-PI ODNAB437-1 2G6.0-1 OOT-1 50-T-2662 (GE1 4)

Average Planar Linear Heat Generation Rate (APLHGR) Limit Versus Average Planar Exposure 12.0 - - - - .- .-

. n This Figure is Referred To By 11.0* Technical Specification 3.2.1 -

I I I I I 10.0 _- 7k Exposure (GWdIMt)

Limit (kWlft) 0.00 9.06 9.0

/ 1.10 2.20 3.31 4.41 9.20 9.31 9.43 9.55 5.51 9.68 6.61 9.81 7.72 9.95

i 8.0- 8.82 10.09 9.92 10.23 tr 11.02 10.38 a- 12.13 10.45 IL 1323 10.48 Permissible 14.33 10.51 7.0 _-i 15.43 10.54 - Regionof _ -

15.99 10.55 Operation 16.53 10.56 18.74 10.56 21.09 10.49 6.0 I- 22.05 27.56 33.07 38.58 10.47 10.20 9.87 9.42

_I _

44.09 8.95 5.0 _- 49.60 8.45 4 55.12 7.91 60.63 5.56 62.02 4.91 4.0 - I I- S- S- I- I- I- I- I-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 Design CaIc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 21, Revision 0 Figure 9 GE13 and GE14 Flow-Dependent MAPLHGR Limit, MAPLHGR(F) 1.10 I. . .

1.05 I I I I This Figure is Referred To By I

I I II IIT k I I I IWO LOOP I

I uperation Limit II t..

Technical Specifications 1.00 _ -

3.2.1, 3.4.1 and 3.7.6

- __ . I I .

I I 0.95 -

II II Max Flow = 102.5%_

107%

1*

I 6/

a 0.90 112%

117%

I

-N 9 1* 9

/ / /A - t - .914. -

LL IL

< 0.85 4. - 4-I 1-4 I

4. - I -- I 4.

/-

/,

4-e - 4..

_ ingle Loop Operation Limit -

-7 7 7l VlT-TJ J

_Xt7-_I1-F TV 2

0 I 0.80

/ / / S U.

= 0.75 ci aQ0.6 MAPLHGR(F) = MAPFACF

  • MAPLHGRSTD MAPLHGRSTD = Standard MAPLHIGR limits MAPFACp(F) = Minimum (1.0, AFWcI100+BF)

Wc = % Rated Core Flow

, 0.60 f _ _ AF And BF Are Fuel Type Dependent Constants Given Below:

Max Core Flow 0.55

(% 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 30 0 355 40 4 45 5 5 45 50 55 60 65

. 707 7 75 80

. 85

. 90 95

. . 1 100 105 110 Core Flow (%Rated)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21 -0625 B1C15 Core Operating Limits Report Page 22, Revision 0 Figure 10 GE13 and GE14 Power-Dependent MAPLHGR Limit, MAPLHGR (P) 1.05 P  ! Y -  !

1.00 I I I I 1.

_This Figure is Referred To By_

Technical Specifications 0.95 3.2.1, 3.4.1 and 3.7.6 _ i i l P i i i 0.90 II I I I /0-10 0.85 Two Loop Operation I-E. 0.80 - o, I o 0.75 7ingle Loop Operation Limit' 0.70 qM 0.

"' 0.60 4- _ -_ - -i- ll_

I I I 0

Xa. 0.65 4s IA_ Core Flow < 50%

I MAPLHGR(P) = MAPFACP

Turbine Bypass MAPLHGRSm = Standard MAPLHGR Umits 0

a'I Operable or I 0 0.50 C!.

Inoperable For P < 23%:

r - -I No Thermal Umits Monitoring Required 0.

-r--l- For 23% < P < 26%:

D.0.50 For Core Flow c 50% & Turbine Bypass Operable or Inoperable MAPFACp = 0.567 + 0.0157 (P-26%)

For Core Flow > 50% & Turbine Bypass Operable or Inoperable 0.45 - Core Flow > 50% MAPFACp = 0.433 + 0.0063 (P-26%)

, Turbine Bypass For P 2 26%

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

0.40- n Inoperable 0.35 I I I i I I I I i i I 0.30 I I I I I I I 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)

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21-0625 B1C15 Core Operating Limits Report Page 23, Revision 0 Figure 11 GE13 and GE14 Flow-Dependent MCPR Limit, MCPR(F) 1.80 1.70 For Wc (% Rated Core Flow) > 40%,

MCPR(F) = Max (1.24, AFWSIOO+Bp)

Max Core Flow

(% Rated) AF BP 1.60 _____ 102.5 - 0.592 1.717 107.0 - 0.608 1.760 112.0 - 0.625 1.812 117.0 -0.656 1.877 IL

a. 1.50 0

_ _ _ 7- 7 1-II-N 1.40* Max Flow= 117%

1y KN - -

This Figure is Referred To By Technical Specification 3.2.2, 3.4.1 and 3.7.6 112%/ /

I 107%

102.5%n 1.30 I  % I I m m ----

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

PGN Nuclear Fuels Mgmt. & Safety Analysis Design Calc. No. 1B21 -0625 B1C15 Core Operating Limits Report Figure 12 Page 24, Revision 0 GE13 and GE14 Power - Dependent MCPR Limit, MCPR (P) r -IrTiI 1

3.80 -

3.70 - OLMCPR - - - -= =

3.60 - Rated MCPR Multiplier (Kp) 3.50 _

3.40 - 5%

_--l C~ore Flow > 50% r_

S 3.30 Turbine Bypass ,-

V ~'3.20 Inoperableor I 1Operable Operating Umit MCPR:

Q 3.10 - InoperablOLMCPR(P) = Kp*OLMCPR(100)

VI u 3.00 - For P < 23%:

0 No Thermal Umits Monitoring Required

- 2.90-IL 2.80 For 23%<PCPByPAss: Where PYPASS=26%

Q. Turbine Bypass Operable or Inoperable O 2.70-J 2.60__ For Core Flow > 50%

° 2'50 - =OLMCPR(P)= [3.13+ 0.0900(26% - P)]

2.50 -Cr 0Core lw<5 Flow < 50% For CoreFlow < 50%

2.40 Turbine Bypass OLMCPR(P) -[2.34 + 0.0700(26% - P)J 2.30 - Operable or Inoperable For 26% < P < 45%:

N 2.20 - _ Kp= 1.28 + 0.0135 (45% - P)

Al 2.10 - For 45% < P < 60%:

a.

O 2.00 Kp = 1.18+ 0.00667 (60% - P)

L 1.90- For60% <P

_ 1.80I Kp= 1.00 + 0.00450 (100% - P) n 1.70 0

1.60 1.50

=-

rl=

21 4 0 _===

I-1.20 -This Figure is Referred To By c 1.3 _ _ _ _Technical Specification_

ar 1.20 _ ~__3.2.2, 3.4.1, 3.7.6_

1.10-1.00 -

20 2130 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

PBYPASS

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 13 Design Calc. No. 11B21-0625 BIC15 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 and the Technical Requirements Manual Specification 3.3 M inim um M axim um I PMSPcrm(M APRM STP Scram ELL L Co re (IC F)

C ore POPRMoEabledRegion P ow or Flow Flow, APRM STP Rod Block oo

% 7 619 907 100 .0 .0 o cRegion  : 98 a _9 75 04 73.89 80 .47 80.47 97 72.75 80.47 9 7 1 .91 8 0.4 7 90.0 \5 70.49 90.47 94 69.3e 80.47 93 968 .25 80 .47 92 9 7.1 3 8 0.4 7 80.0 9911__ 6.03 80 .47 693.8 3 8 0.4 7 8 692.74 80.47 70.0 _ .; ..... 87s 880 81 90.58a 80 .51 80.8 95 59.50 80.70 9 :4 58.43 90.78 57 .3 7 I. o 60.0 83 92 896.31 80.90 91.'05 81 55,235 81 .2 1 90 5 42 0 981.36 79 5 3.186 91.5 2 50.0 798 52.12 81 .6 7 77 51 .098 81 .83 78 5 0.0 5 81 .99a

____75 489.03 92.13 40.0 MELLLLie . 74 48 00 82 29 n73 48.89 82 .44 72 45.8 82.80 71 44.95 8 2.7 5 30.0 __: _ __ 70 43.9 4 83 .91 89 4 2 .84 9 3.08 68 4 1.84 9 3.2 17

4 0 .95 4 83 .3

__ _ / __ _000__

_ __ __8 es__ 39.986 83.52 20.0 65 38.97 83.68 Natural J !l ,r' .  : . ' .' 64 3 7.~99 83.83 Circulation 100____ L 63 80.0 2

1

37. 01 396.0 4 35.06 83.9 9 4.14 84.29 35% Minimum Pump Speed 90 3 4. 1 0 84.45 Minimum Power Line 58 3 3.1 3 8 4. 0 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 Figure 14 Design Calc. No. 1B21-0625 B1 C1 5 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 M Inim um M axim urn (M ELLL) (ICF)

Core Core 110.0 Power Flow, Flow, A M Ibs/hr M lbslhr 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 8 0.47 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 0

84 58.43 80.79 83 57.37 80.90 C 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 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 68 41.94 83.21 67 40.95 83.37 20.0 66 39.96 83.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 10.0 62 61 36.04 35.06 84.14 84.29 60 34.10 84.45 59 33.13 84.60 0.0 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 Figure 15 Design CaIc. No. 1B21-0625 B1C15 Core Operating Limits Report Stability Option IlIl 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 3.3 120.0 M Inim um M axim um (M ELLL) (ICF)

Cora Core 110.0 Power Flow, Flow,

% M Ibs/hr M lbslhr 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 60.47 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 60.0 83 82 57.37 58.31 80.90 81.05 81 55.25 81.21 80 54.20 81.36 79 53.16 81.52 50.0 78 52.12 81.87 77 51.06 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 68 41.94 83.21 67 40.95 83.37 20.0 66 39.96 63.52 65 38.97 83.68 64 37.99 83.83 63 37.01 83.99 10.0 62 61 36.04 35.06 84.14 84.29 60 34.10 84 .45 59 33.13 84.60 0.0 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 CUv3

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 16 Design Caic. No. 1B21-0625 BIC15 Core Operating Limits Report Stability Option IlIl Power/Flow Map Page 28, Revision 0 I OPRM Inoperable, Single Loop Operation, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 120.0 110.0 100.0 90.0 80.0 70.0 0

C. 60.0 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 t

PGN Nuclear Fuels Mgmt. Safety Analysis Figure 17 Design Cabc. No. 11B21-0625 1BIC1 5 Core Operating Limits Report Stability Option Ill Power/Flow Map Page 29, Revision 0 IThis OPRM Operable, FWTR, 2923 MWt Figure supports Improved Technical Specification 3.3. 1.1 and the Technical Requirements Manual Specification 3.3 120.0 - nIiurnMai r (M E L LL IIC F) 1.0- STP Scram JJP.0RM Enabled Region ]P _________APRM APMSPPdBoc o wear

¶ C ore Flow.

M lb slhr C ore Flow, M lbslhr I0 1olok0 7 6.19 80.4 7 100.0 Scram Aodance99 Avoidance Region 9873.89 7 5.04 80.4 7 90.4 7 97 72.~75 80.4 7 96 71 .81 8 0.4 7 90.0 ___a 95__7 0 .4 7 93 6825 8.47 92 8 7.1 3 8 0.47 800L__ __6__ __6_918 90a

.0 3 64 .9 3 8 0.4 7 8 0.4 7 89 83.8 3 80.47 88 02.74 80.4 7 8010'00-7 61.88 80.51 70.0 868 80.5 8 8 0.6 0 85 59.50 80.70

  • 8 4 58.4 3 8 0.7 9 83 5 7.3 7 80.90 60082 586.3 1 81 .0 5 81 5 5.2 5 Si.2 1 80 5 4.2 0 81.3 6 79 5 3.186 81 .5 2 50.0 78 5 2.1 2 81 .87 77 51.~08a 81 .83 76 5 0.0 5 81 .98

______idLin 75 4 9.0 2 82.13 40.0 MELLL Line --- 74 73 468.00 48.988 82.2 9 a82.4 4 72 4 5.986 8 2 .60 71 4 4.5 8 2.7 5

3. _ _ _ __ _ _ _ _ _ _ _70 8009 4 3 94 4 2.9 4 8 2.9 1 8 3.086 68 41.94 83.21 67 4 0.956 8 3.3 7 3 9.986 83.52 20.0 _ _ _ _ ___ _ _ _ _ __ _ _ _ _ _8 66__

85 38.97 8 3.6 8 8aua 4 3 7.9 9 83.83 63 3 7.0 1 83.99 Cicuato ____6 2 3 6.0 4 84.14 35% Minimum Pump Speed 80 3 4.1 0 8 4.4 5 Minimum Power Line 59 33.13 8 4.680 11 1 ~ 58 3 2.1 7 8 4.7 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

PIGN Nuclear Fuels Mgmt. Safety Analysis Figure 18 Design CaIc. No. 1B21-0625 B1 C1 5 Core Operating Limits Report Stability Option III Power/Flow Map Page 30, Revision 0 OPRM Inoperable, FWTR, 2923 MWt This Figure supports Improved Technical Specification 3.3.1.1 and the Technical Requirements Manual Specification 3.3 M inim um Maximum (M ELLL) (IC F) 110.0 _____ Cor Cor 5% Buffer Region APRM STP Rod Block  % M lb slhr Milbslhr I0. .Oo1 00 76.1 9 6 0.4 7 799 7 5.0 4 8 0.47 98 73.89 0.4 7 97 7 2.75 80.4 7 96 7 1.6 1 8 0.4 7 90.0 -95 7 0.4 9 8 0.4 7 Regio A- Manual SCRAMJ94 69:.386 0:4 7 92 687.1 3 8 0.4 7 80.0 91 688.0 3 8 0.4 7 90 6 4.9 3 8 0.4 7 LO,89 63.83 8 0.4 7 88 82.7 4 8 0.4 7 70.0 87 81.88 8 0.5 1 86 80.58 8 0.8 0

  • 85 5 9.5 0 8 0.7 0 84 5 8.4 3 8 0.7 9 o 60.0 0.82 83 5 7.3 7 5 6.3 1 80.90 81 .0 5 aeCg81 5 5.2 5 81 .21 80 5 4.2 0 81 .36 50078 _F_

__ __ _79 77 5 3.186 5 2.1 2 5 1.0 8 81.52 81,.67 81.8 3 SLO 'Entr Rod Line In 76 5 0.0 5 81.98 40.0 IVEL n'75 49.0 2 8 2.1 3 73 4 6.98 82.4 4 72 45.96 8 2.6 0

_ _ _ _ _ _ _ _ _ _ _ _71 4 4.9 5 8 2.7 5 30.0 70 423.9 4 8 2.9 1 69 4 2.9 4 8 3.0 6 68 41.94 8 3.2 1 87 4 0.9 5 8 3.3 7 20.0 66 3 9.96 83.52 Ntrl65 38.97 8 3.6 8 64 3 7.9 9 83.83

.02 6 3 6.0 4 8 4.1 4 35% Minimum Pump Speed Minimum Power Line3 06 4.29 0.0 __7__ 32_______ 4___

7__

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 s0 60 70 8o 90 100 110 120 %Core Flow

BSEP 04-0037 Enclosure 2 0000-0016-6502-SRLR, Revision 0, Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 1 Reload 14 Cycle 15, February 2004

Retrieved from "https://kanterella.com/w/index.php?title=ML040960082&oldid=2684921"