Text

Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)
	ML24095A170
Person / Time
Site:	Susquehanna
Issue date:	04/04/2024
From:	Casulli E; Susquehanna, Talen Energy
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	PLA-8110
	Download: ML24095A170 (1)
	v • d • e

April 4, 2024 Edward Casulli Site Vice President Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3795 Fax 570.542.1504 Edward.Casulli@talenenergy.com SUSQUEHANNA STEAM ELECTRIC STATION SUBMITTAL OF UNIT lCYCLE 24 CORE OPERATING LIMITS REPORT PLA-8110 TALEN~

ENERGY 10 CFR 50.4 Docket No. 50-387 Susquehanna Steam Electric Station (SSES) Technical Specification Section 5.6.5 requires that the Core Operating Limits Report (COLR), including any mid-cycle supplements or revisions, be provided upon issuance to the NRC in accordance with 10 CFR 50.4. Pursuant to this requirement, the SSES Unit I Cycle 24 COLR is provided in the attachment.

There are no new or revised commitments contained in this submittal.

Should you have any questions regarding this submittal, please contact Ms. Melisa Krick, Manager-Nuclear Regulatory Affairs, at (570) 542-1818.

E. Casulli

Attachment:

SSES Unit 1 Cycle 24 COLR Copy:

NRC Region I Ms. J. England, NRC Senior Resident Inspector Ms. A. Klett, NRC Project Manager Mr. M. Shields, PA DEP/BRP

Attachment to PLA-8110 SSES Unit 1 Cycle 24 COLR

PL-NF-24-003 Rev. 0 Page 1 of 72 Susquehanna SES Unit 1 Cycle 24 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering March 2024

PL-NF-24-003 Rev. 0 Page 2 of 72 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX REV NO.

AFFECTED SECTIONS DESCRIPTION / PURPOSE OF REVISION FORM NFP-QA-008-2, Rev. 2 0

ALL Issuance of this COLR is in support of Unit 1 Cycle 24 operation.

PL-NF-24-003 Rev. 0 Page 3 of 72 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 24 CORE OPERATING LIMITS REPORT Table of Contents

1.0 INTRODUCTION

......................................................................................................... 4 2.0 DEFINITIONS.............................................................................................................. 5 3.0 SHUTDOWN MARGIN................................................................................................ 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)....................... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR)........................................................... 10 6.0 LINEAR HEAT GENERATION RATE (LHGR)............................................................. 28 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS....................................................................................................... 47 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION......................................... 49 9.0 POWER / FLOW MAP................................................................................................. 68 10.0 OPRM SETPOINTS.................................................................................................... 70

11.0 REFERENCES

............................................................................................................ 71

PL-NF-24-003 Rev. 0 Page 4 of 72

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 24 is prepared in accordance with the requirements of Susquehanna Unit 1, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.

PL-NF-24-003 Rev. 0 Page 5 of 72 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.

2.1 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.

2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height.

2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.

2.4 LHGRFACf is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACf multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.

2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than RATED THERMAL POWER. The LHGRFACp multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions.

2.7 MCPR99.9% is the cycle-specific safety limit MCPR that ensures at least 99.9% of fuel rods are not susceptible to boiling transition.

2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.

2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLHGR limit for the applicable fuel bundle type.

2.8 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR99.9% safety limit is not violated.

2.9 NP is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.

2.10 SP is the OPRM trip setpoint for the peak to average OPRM signal.

2.11 FP is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.

PL-NF-24-003 Rev. 0 Page 6 of 72 3.0 SHUTDOWN MARGIN 3.1 References Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:

a) 0.38% k/k with the highest worth rod analytically determined OR b) 0.28% k/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, R. The adder, R, is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of R is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.

The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.

PL-NF-24-003 Rev. 0 Page 7 of 72 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 References Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUMTM-10 fuel shall not exceed the limit shown in Figure 4.2-1A. The APLHGRs for ATRIUMTM 11 fuel shall not exceed the limit shown in Figure 4.2-1B.

The APLHGR limits in Figures 4.2-1A and 4.2-1B are valid in Two Loop operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. The APLHGR limits for Single Loop operation are provided in Section 8.0.

0.0, 12.5 15000, 12.5 67000, 6.9 4.0 6.0 8.0 10.0 12.0 14.0 16.0 0

10000 20000 30000 40000 50000 60000 70000 Average Planar Linear Heat Generation Rate Limit (kw/ft)

Average Planar Exposure (MWD/MTU)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION ATRIUMTM-10 FUEL FIGURE 4.2-1A SSES UNIT 1 CYCLE 24 REFERENCE T.S. 3.2.1 USED IN DETERMINING MAPRAT PL-NF-24-003 Rev. 0 Page 8 of 72 I

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0, 12.0 20000, 12.0 60000, 9.0 69000, 7.2 4.0 6.0 8.0 10.0 12.0 14.0 16.0 0

10000 20000 30000 40000 50000 60000 70000 Average Planar Linear Heat Generation Rate Limit (kw/ft)

Average Planar Exposure (MWD/MTU)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION ATRIUMTM 11 FUEL FIGURE 4.2-1B SSES UNIT 1 CYCLE 24 REFERENCE T.S. 3.2.1 USED IN DETERMINING MAPRAT PL-NF-24-003 Rev. 0 Page 9 of 72 I

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PL-NF-24-003 Rev. 0 Page 10 of 72 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 References Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 5.2 Description The MCPR99.9% Safety Limit is 1.07 for Two Loop operation and 1.09 for Single Loop operation.

The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRIUMTM-10 and ATRIUMTM 11) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.

a)

Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 5.2-1:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 5.2-2:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel b)

Main Turbine Bypass Inoperable Figure 5.2-3:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 5.2-4:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel c)

EOC-RPT Inoperable Figure 5.2-5:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 5.2-6:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel d)

Backup Pressure Regulator Inoperable Figure 5.2-7:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 5.2-8:

Power Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel e)

One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed

PL-NF-24-003 Rev. 0 Page 11 of 72 Figure 5.2-9:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 5.2-10:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop operation and are applicable to both ATRIUMTM-10 and ATRIUMTM 11 Fuel.

The MCPR limits for Single Loop operation are provided in Section 8.0.

5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.

Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.

PL-NF-24-003 Rev. 0 Page 12 of 72 Main Turbine Bypass / EOC-RPT /

Backup Pressure Regulator Operable

30.0, 1.95 35.0, 1.84 35.1, 1.53 40.0, 1.49 40.1, 1.37 108.0, 1.22 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 30 40 50 60 70 80 90 100 110 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-1 SSES UNIT 1 CYCLE 24 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME A

B

REFERENCE:

T.S. 3.2.2 USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 13 of 72

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26.01, 2.40 40, 1.99 50, 1.99 60, 1.87 70, 1.78 80, 1.67 90, 1.58 100, 1.53 26.01, 2.18 40, 1.88 50, 1.81 60, 1.72 70, 1.61 80, 1.55 90, 1.50 100, 1.42 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 3.2 3.4 3.6 3.8 4.0 10 20 30 40 50 60 70 80 90 100 MCPR Operating Limit Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-2 SSES UNIT 1 CYCLE 24 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES A

B

REFERENCE:

T.S. 3.2.2 USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C

CURVE C:

26, 2.53 23, 2.61 CURVE B:

26, 2.57 23, 2.61 CURVE A:

26, 2.57 23, 2.61 A

B PL-NF-24-003 Rev. 0 Page 14 of 72 DD I

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PL-NF-24-003 Rev. 0 Page 15 of 72 Main Turbine Bypass Inoperable

30, 1.95 40, 1.78 40.1, 1.56 108, 1.34 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 30 40 50 60 70 80 90 100 110 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-3 SSES UNIT 1 CYCLE 24 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME A

B

REFERENCE:

T.S. 3.7.6 and 3.2.2 USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 PL-NF-24-003 Rev. 0 Page 16 of 72

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26.01, 2.42 40, 2.01 50, 1.99 60, 1.90 70, 1.80 80, 1.72 90, 1.64 100, 1.64 26.01, 2.23 40, 1.88 50, 1.83 60, 1.72 70, 1.65 80, 1.60 90, 1.57 100, 1.51 1.3 1.5 1.7 1.9 2.1 2.3 2.5 2.7 2.9 3.1 3.3 3.5 3.7 3.9 4.1 4.3 10 20 30 40 50 60 70 80 90 100 MCPR Operating Limit Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-4 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.7.6 and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME B

USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 C

CURVE D:

26, 2.62 23, 2.69 CURVE C:

26, 2.62 23, 2.69 D

CURVE B:

26, 3.04 23, 3.26 CURVE A:

26, 3.04 23, 3.26 A

B PL-NF-24-003 Rev. 0 Page 17 of 72 DD I

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PL-NF-24-003 Rev. 0 Page 18 of 72 EOC-RPT Inoperable

30.0, 1.95 35.0, 1.84 35.1, 1.53 40.0, 1.49 40.1, 1.37 108.0, 1.22 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 30 40 50 60 70 80 90 100 110 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-5 SSES UNIT 1 CYCLE 24 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME A

B

REFERENCE:

T.S. 3.3.4.1 and 3.2.2 USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 19 of 72

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26.01, 2.40 40, 2.01 50, 2.01 60, 1.88 70, 1.79 80, 1.79 90, 1.79 100, 1.69 26.01, 2.18 40, 1.88 50, 1.81 60, 1.72 70, 1.61 80, 1.58 90, 1.53 100, 1.51 1.3 1.5 1.7 1.9 2.1 2.3 2.5 2.7 2.9 3.1 3.3 3.5 3.7 3.9 4.1 4.3 10 20 30 40 50 60 70 80 90 100 MCPR Operating Limit Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-6 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.3.4.1 and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME B

USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C

D CURVE C:

26, 2.53 23, 2.61 CURVE D:

26, 2.53 23, 2.61 CURVE B:

26, 2.57 23, 2.61 CURVE A:

26, 2.57 23, 2.61 B

A PL-NF-24-003 Rev. 0 Page 20 of 72 DD I

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PL-NF-24-003 Rev. 0 Page 21 of 72 Backup Pressure Regulator Inoperable

30.0, 1.95 35.0, 1.84 35.1, 1.53 40.0, 1.49 40.1, 1.37 108.0, 1.22 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 30 40 50 60 70 80 90 100 110 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-7 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.7.8 and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME B

USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 22 of 72

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26.01, 2.40 40, 2.05 50, 1.99 60, 1.87 70, 1.78 80, 1.67 90, 1.58 100, 1.53 26.01, 2.22 40, 1.99 50, 1.93 60, 1.78 70, 1.61 80, 1.55 90, 1.50 100, 1.42 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 3.2 3.4 3.6 3.8 4.0 10 20 30 40 50 60 70 80 90 100 MCPR Operating Limit Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-8 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.7.8 and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES B

USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C

CURVE A:

26, 2.57 23, 2.61 CURVE B:

26, 2.57 23, 2.61 CURVE C:

26, 2.53 23, 2.61 B

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PL-NF-24-003 Rev. 0 Page 24 of 72 One TSV or TCV Closed

30.0, 2.03 40.0, 1.85 40.1, 1.59 108.0, 1.37 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 30 40 50 60 70 80 90 100 110 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*

TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-9

Operation with one TSV or TCV closed is only supported at power levels 75% rated power SSES UNIT 1 CYCLE 24 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME A

B

REFERENCE:

T.S. 3.2.2 and TRM 3.3.7 USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 25 of 72

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MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-10 SSES UNIT 1 CYCLE 24 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES A

B

REFERENCE:

T.S. 3.2.2 and TRM 3.3.7 USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C

B A

CURVE A:

26, 2.57 23, 2.61 CURVE B:

26, 2.57 23, 2.61 CURVE C:

26, 2.53 23, 2.61 PL-NF-24-003 Rev. 0 Page 26 of 72

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PL-NF-24-003 Rev. 0 Page 27 of 72 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Position Average Scram Time to Position (seconds) 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5

2.700 3.440 Average Scram Insertion Time Realistic Maximum Allowable

PL-NF-24-003 Rev. 0 Page 28 of 72 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 References Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 6.2 Description The maximum LHGR for ATRIUM'-10 and ATRIUM' 11 fuel shall not exceed the LHGR limits determined from Figure 6.2-1A and Figure 6.2-1B, respectively.

The LHGR limits in Figures 6.2-1A and 6.2-1B are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.

To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided in the following figures:

a)

Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 6.2-2:

Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 6.2-3:

Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel b)

Main Turbine Bypass Inoperable Figure 6.2-4:

Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 6.2-5:

Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel c)

EOC-RPT Inoperable Figure 6.2-6:

Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 6.2-7:

Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel d)

Backup Pressure Regulator Inoperable Figure 6.2-8:

Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel

PL-NF-24-003 Rev. 0 Page 29 of 72 Figure 6.2-9:

Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel e)

One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-10:

Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 6.2-11:

Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 and ATRIUMTM 11 Fuel The LHGR limits in Figures 6.2-1A/6.2-1B are valid for both Two Loop and Single Loop operation and are fuel type specific. The LHGR limit multipliers in Figures 6.2.2 through 6.2.11 are valid for both Two Loop and Single Loop operation and are applicable to both ATRIUMTM-10 and ATRIUMTM 11 Fuel.

0.0, 13.4 18900, 13.4 74400, 7.1 4.0 6.0 8.0 10.0 12.0 14.0 16.0 0

10000 20000 30000 40000 50000 60000 70000 80000 Linear Heat Generation Rate Limit (kw/ft)

Pellet Exposure (MWD/MTU)

LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE ATRIUMTM-10 FUEL FIGURE 6.2-1A SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 USED IN DETERMINING FDLRX PL-NF-24-003 Rev. 0 Page 30 of 72 I

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10000 20000 30000 40000 50000 60000 70000 80000 Linear Heat Generation Rate Limit (kw/ft)

Pellet Exposure (MWD/MTU)

LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE ATRIUMTM 11 FUEL FIGURE 6.2-1B SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 USED IN DETERMINING FDLRX PL-NF-24-003 Rev. 0 Page 31 of 72 D

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PL-NF-24-003 Rev. 0 Page 32 of 72 Main Turbine Bypass / EOC-RPT /

Backup Pressure Regulator Operable

30.0, 0.46 50.0, 0.72 86.4, 1.00 108.0, 1.00 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 Flow Dependent LHGR Multiplier Total Core Flow (MLB/HR)

FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-2 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 33 of 72 I

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POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-3 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 LEGEND CURVE A: BASE CURVE CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR A

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30, 0.42 108, 1.00 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 30 40 50 60 70 80 90 100 110 Flow Dependent LHGR Multiplier Total Core Flow (MLB/HR)

FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-4 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 and 3.7.6 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 PL-NF-24-003 Rev. 0 Page 36 of 72 I

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POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-5 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 and 3.7.6 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 LEGEND CURVE A: BASE CURVE CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR A

B PL-NF-24-003 Rev. 0 Page 37 of 72 D

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PL-NF-24-003 Rev. 0 Page 38 of 72 EOC-RPT Inoperable

30.0, 0.46 50.0, 0.72 86.4, 1.00 108.0, 1.00 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 Flow Dependent LHGR Multiplier Total Core Flow (MLB/HR)

FLOW DEPENDENT LHGR LIMIT MULTIPLIER EOC-RPT INOPERABLE ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-6 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 and 3.3.4.1 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 39 of 72 I

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POWER DEPENDENT LHGR LIMIT MULTIPLIER EOC-RPT INOPERABLE ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-7 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 and 3.3.4.1 USED IN DETERMINING FDLRX LEGEND CURVE A: BASE CURVE CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR A

B SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 40 of 72 I

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PL-NF-24-003 Rev. 0 Page 41 of 72 Backup Pressure Regulator Inoperable

30.0, 0.46 50.0, 0.72 86.4, 1.00 108.0, 1.00 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 Flow Dependent LHGR Multiplier Total Core Flow (MLB/HR)

FLOW DEPENDENT LHGR LIMIT MULTIPLIER BACKUP PRESSURE REGULATOR INOPERABLE ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-8 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 and 3.7.8 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 42 of 72 I

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POWER DEPENDENT LHGR LIMIT MULTIPLIER BACKUP PRESSURE REGULATOR INOPERABLE ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-9 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 and 3.7.8 USED IN DETERMINING FDLRX LEGEND CURVE A: BASE CURVE CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR A

B SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 43 of 72

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PL-NF-24-003 Rev. 0 Page 44 of 72 One TSV or TCV Closed

30, 0.40 108, 1.00 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 30 40 50 60 70 80 90 100 110 Flow Dependent LHGR Multiplier Total Core Flow (MLB/HR)

FLOW DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED*

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-10

Operation with one TSV or TCV closed is only supported at power levels 75% rated power SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 and TRM 3.3.7 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 45 of 72 I

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POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 6.2-11 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.2.3 and TRM 3.3.7 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 LEGEND CURVE A: BASE CURVE CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR A

B PL-NF-24-003 Rev. 0 Page 46 of 72 I

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PL-NF-24-003 Rev. 0 Page 47 of 72 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 References Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a)

Low Power Range Setpoint, b)

Intermediate Power Range Setpoint, c)

High Power Range Setpoint, d)

Low Power Range - Upscale, e)

Intermediate Power Range - Upscale, and f)

High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.

The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.

PL-NF-24-003 Rev. 0 Page 48 of 72 Table 7.2-1 RBM Setpoints Function Allowable Value(1)

Nominal Trip Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 117.4 117.0 High Power Range - Upscale 105.6 105.2 (1)

Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of RATED THERMAL POWER. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.

Table 7.2-2 RBM System Operability Requirements Thermal Power

(% of Rated)

MCPR (2,3,4) 28 and < 90

< 1.78 90 and < 95

< 1.47

> 95

< 1.68 (2)

Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and one TCV/TSV closed.

(3)

Applicable to both Two Loop and Single Loop Operation.

(4)

Applicable to both ATRIUM-10 and ATRIUM 11 Fuel.

PL-NF-24-003 Rev. 0 Page 49 of 72 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 References Technical Specification 3.2.1, 3.2.2, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 8.2 Description APLHGR The APLHGR limit for ATRIUMTM-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1A. The APLHGR limit for ATRIUMTM 11 fuel shall be equal to the APLHGR Limit from Figure 8.2-1B.

The APLHGR limits in Figures 8.2-1A and 8.2-1B are valid in Single Loop operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.

Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUMTM-10 and ATRIUMTM 11) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.

a)

Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 8.2-3:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel b)

Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel c)

EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel

PL-NF-24-003 Rev. 0 Page 50 of 72 d)

Backup Pressure Regulator Inoperable Figure 8.2-8:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 8.2-9:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel e)

One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-10:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel Figure 8.2-11:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 and ATRIUMTM 11 Fuel The MCPR limits in Figures 8.2-2 through 8.2-11 are applicable to both ATRIUMTM-10 and ATRIUMTM 11 Fuel, are valid only for Single Loop operation, and support power levels up to 67.2% RATED THERMAL POWER and core flows up to 52 Mlbm/hr. These conditions conservatively bound Single Loop Operation in accordance with Technical Specification 3.4.1.

Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.

RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.

0, 10.00 15000, 10.00 67000, 5.60 4.00 6.00 8.00 10.00 12.00 14.00 16.00 0

10000 20000 30000 40000 50000 60000 70000 Average Planar Linear Heat Generation Rate Limit (kw/ft)

Average Planar Exposure (MWD/MTU)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - SINGLE LOOP OPERATION ATRIUMTM-10 FUEL FIGURE 8.2-1A SSES UNIT 1 CYCLE 24 REFERENCE T.S. 3.4.1 and 3.2.1 USED IN DETERMINING MAPRAT PL-NF-24-003 Rev. 0 Page 51 of 72 I

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10000 20000 30000 40000 50000 60000 70000 Average Planar Linear Heat Generation Rate Limit (kw/ft)

Average Planar Exposure (MWD/MTU)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - SINGLE LOOP OPERATION ATRIUMTM 11 FUEL FIGURE 8.2-1B SSES UNIT 1 CYCLE 24 REFERENCE T.S. 3.4.1 and 3.2.1 USED IN DETERMINING MAPRAT PL-NF-24-003 Rev. 0 Page 52 of 72 I

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PL-NF-24-003 Rev. 0 Page 53 of 72 Main Turbine Bypass / EOC-RPT /

Backup Pressure Regulator Operable

30.0, 1.95 35.0, 1.84 35.1, 1.53 40.0, 1.49 40.1, 1.37 52.0, 1.34 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 30 35 40 45 50 55 60 65 70 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-2 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1 and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME USED IN DETERMINING MFLCPR B

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 54 of 72 I

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26.01, 2.42 40, 2.01 50, 2.01 60, 2.01 67.2, 2.01 26.01, 2.20 40, 2.01 50, 2.01 60, 2.01 67.2, 2.01 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 3.2 3.4 3.6 3.8 4.0 10 20 30 40 50 60 70 80 MCPR Operating Limit Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-3 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1 and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 B

C A

CURVE A:

26, 2.59 23, 2.63 CURVE B:

26, 2.59 23, 2.63 CURVE C:

26, 2.55 23, 2.63 B

PL-NF-24-003 Rev. 0 Page 55 of 72

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PL-NF-24-003 Rev. 0 Page 56 of 72 Main Turbine Bypass Inoperable

30, 1.95 40, 1.78 40.1, 1.56 52, 1.52 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 30 35 40 45 50 55 60 65 70 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-4 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME USED IN DETERMINING MFLCPR B

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 PL-NF-24-003 Rev. 0 Page 57 of 72

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26.01, 2.44 40, 2.04 50, 2.01 60, 2.01 67.2, 2.01 26.01, 2.25 40, 2.01 50, 2.01 60, 2.01 67.2, 2.01 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 3.2 3.4 3.6 3.8 4.0 4.2 4.4 10 20 30 40 50 60 70 80 MCPR Operating Limit Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-5 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 B

C D

CURVE D:

26, 2.64 23, 2.71 CURVE C:

26, 2.64 23, 2.71 CURVE B:

26, 3.06 23, 3.28 CURVE A:

26, 3.06 23, 3.28 B

A PL-NF-24-003 Rev. 0 Page 58 of 72

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PL-NF-24-003 Rev. 0 Page 59 of 72 EOC-RPT Inoperable

30, 1.95 35, 1.84 35.1, 1.53 40, 1.49 40.1, 1.37 52, 1.34 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 30 35 40 45 50 55 60 65 70 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-6 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME USED IN DETERMINING MFLCPR B

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 60 of 72 D D I

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26.01, 2.42 40, 2.03 50, 2.03 60, 2.01 67.2, 2.01 26.01, 2.20 40, 2.01 50, 2.01 60, 2.01 67.2, 2.01 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 3.2 3.4 3.6 3.8 4.0 4.2 4.4 10 20 30 40 50 60 70 80 MCPR Operating Limit Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-7 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 D

B C

CURVE C:

26, 2.55 23, 2.63 CURVE D:

26, 2.55 23, 2.63 CURVE B:

26, 2.59 23, 2.63 CURVE A:

26, 2.59 23, 2.63 A

B PL-NF-24-003 Rev. 0 Page 61 of 72 I :

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PL-NF-24-003 Rev. 0 Page 62 of 72 Backup Pressure Regulator Inoperable

30, 1.95 35, 1.84 35.1, 1.53 40, 1.49 40.1, 1.37 52, 1.34 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 30 35 40 45 50 55 60 65 70 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-8 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME B

USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 63 of 72

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26.01, 2.42 40, 2.07 50, 2.01 60, 2.01 67.2, 2.01 26.01, 2.24 40, 2.01 50, 2.01 60, 2.01 67.2, 2.01 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 3.2 3.4 3.6 3.8 4.0 10 20 30 40 50 60 70 80 MCPR Operating Limit Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-9 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES B

USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C

A B

CURVE B:

26, 2.59 23, 2.63 CURVE A:

26, 2.59 23, 2.63 CURVE C:

26, 2.55 23, 2.63 PL-NF-24-003 Rev. 0 Page 64 of 72 J

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PL-NF-24-003 Rev. 0 Page 65 of 72 One TSV or TCV Closed

30, 2.03 40, 1.85 40.1, 1.59 52, 1.55 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 3.0 30 35 40 45 50 55 60 65 70 MCPR Operating Limit Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-10 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1, 3.2.2, and TRM 3.3.7 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME USED IN DETERMINING MFLCPR B

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 PL-NF-24-003 Rev. 0 Page 66 of 72

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MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUMTM-10 AND ATRIUMTM 11 FUEL FIGURE 8.2-11 SSES UNIT 1 CYCLE 24

REFERENCE:

T.S. 3.4.1, 3.2.2, and TRM 3.3.7 A

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES USED IN DETERMINING MFLCPR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 B

C A

B CURVE A:

26, 2.59 23, 2.63 CURVE B:

26, 2.59 23, 2.63 CURVE C:

26, 2.55 23, 2.63 PL-NF-24-003 Rev. 0 Page 67 of 72

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PL-NF-24-003 Rev. 0 Page 68 of 72 9.0 POWER / FLOW MAP 9.1 References Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power / Flow map, Figure 9.1.

If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power / Flow map is considered an immediate exit region.

If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power /

Flow map is considered an immediate scram region.

Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.

11.0 100 90

Purpose:

Initial/ Date:

UMIIYIY REGKiNI IFOPI' INOPERABLEIMMEDIAlELY SCRAM IAW Am!CABLE PROCEDURE.

IF Of'RM 0PERAll1.E IMMEDiATELY EXITIAW APPLICABLE PROCEDURE.

RESJBIQJEDREGION IF ABOV!ii-MEIJ.LA BOI.JNDARY, IMMEDIAlELY IOOTIAWAPPUCABLE PROCEDURE.

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Figure 9.1 80 SSES Unit 1 Cycle 24 Power/ Flow Map 90 PL-NF-24-003 Rev. 0 Page 69 of 72 100 120 110 100 90 80 70 60 50 40 30 20 10 0

110

PL-NF-24-003 Rev. 0 Page 70 of 72 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR99.9% Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:

SP

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PL-NF-24-003 Rev. 0 Page 71 of 72

11.0 REFERENCES

11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

2. EMF-2361(P)(A), Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP, May 2001.

3. EMF-2292(P)(A), Revision 0, ATRIUM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

4. XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.

5. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.

6. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.

7. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,

September 1986.

8. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.

9. EMF-2209(P)(A), Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.

10. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),

RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.

11. EMF-2158(P)(A), Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2, Siemens Power Corporation, October 1999.

12. EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis -

Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

PL-NF-24-003 Rev. 0 Page 72 of 72

13. NEDO-32465-A, BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, August 1996.

14. ANF-1358(P)(A), Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.

15. BAW-10247PA, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA, Inc., April 2008.

16. ANP-10340P-A, Revision 0, Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods, Framatome Inc., May 2018.

17. ANP-10335P-A, Revision 0, ACE/ATRIUM-11 Critical Power Correlation, Framatome Inc., May 2018.

18. ANP-10300P-A, Revision 1, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios, Framatome Inc., January 2018.

19. ANP-10332P-A, Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios, Framatome Inc., March 2019.

20. ANP-10333P-A, Revision 0, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA),

Framatome Inc., March 2018.

21. ANP-10307PA, Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA, Inc., June 2011.

22. BAW-10247P-A Supplement 1P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 1:

Qualification of RODEX4 for Recrystallized Zircaloy-2 Cladding, AREVA Inc.,

April 2017.

23. BAW-10247P-A Supplement 2P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 2:

Mechanical Methods, Framatome Inc., August 2018.

PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)

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1.0 INTRODUCTION

11.0 REFERENCES

1.0 INTRODUCTION

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