PLA-7934, Submittal of Cycle 21 Core Operating Limits Report PLA-7934
| ML21090A240 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/31/2021 |
| From: | Cimorelli K Susquehanna, Talen Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-7934 | |
| Download: ML21090A240 (105) | |
Text
TALEN~
Kevin Cimorelli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3795 Fax 570.542.1504 Kevin.Cimorelli@TalenEnergy.com ENERGY March 31, 2021 Attn: Document Control Desk 10 CFR 50.4 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION SUBMITTAL OF UNIT 2 CYCLE 21 CORE OPERATING LIMITS REPORT PLA-7934 Docket No. 50-388 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 2 Cycle 21 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.
K. Cimorelli
Attachment:
SSES Unit 2 Cycle 21 COLR Copy: NRC Region I Mr. C. Highley, NRC Sr. Resident Inspector Ms. S. Goetz, NRC Project Manager Mr. M. Shields, PADEP/BRP
Attachment to PLA-7934 SSES Unit 2 Cycle 21 COLR
PL-NF-21-003 Rev. 0 Page 1 of 103 Susquehanna SES Unit 2 Cycle 21 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering March 2021
PL-NF-21-003 Rev. 0 Page 2 of 103 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX REV AFFECTED NO. SECTIONS DESCRIPTION / PURPOSE OF REVISION 0 ALL Issuance of this COLR is in support of Unit 2 Cycle 21 operation.
FORM NFP-QA-008-2, Rev. 2
PL-NF-21-003 Rev. 0 Page 3 of 103 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 21 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) .............................................................. 38 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ......................................................................................................... 67 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION .......................................... 69 9.0 POWER / FLOW MAP................................................................................................... 99 10.0 OPRM SETPOINTS ...................................................................................................... 101
11.0 REFERENCES
.............................................................................................................. 102
PL-NF-21-003 Rev. 0 Page 4 of 103
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 21 is prepared in accordance with the requirements of Susquehanna Unit 2, 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-21-003 Rev. 0 Page 5 of 103 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.
2.6 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 MCPR 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-21-003 Rev. 0 Page 6 of 103 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-21-003 Rev. 0 Page 7 of 103 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.
SSES UNIT 2 CYCLE 21 16.0 REFERENCE T.S. 3.2.1 14.0 USED IN DETERMINING MAPRAT 0.0, 12.5 15000, 12.5 12.0 Average Planar 10.0 8.0 Linear Heat Generation Rate Limit (kw/ft) 67000, 6.9 6.0 4.0 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS PL-NF-21-003 AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION ATRIUMTM-10 FUEL Rev. 0 FIGURE 4.2-1A Page 8 of 103
SSES UNIT 2 CYCLE 21 16.0 REFERENCE T.S. 3.2.1 14.0 USED IN DETERMINING MAPRAT 0, 12.0 20000, 12.0 12.0 Average Planar 10.0 60000, 9.0 8.0 Linear Heat Generation Rate Limit (kw/ft) 69000, 7.2 6.0 4.0 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS PL-NF-21-003 AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION ATRIUMTM 11 FUEL Rev. 0 FIGURE 4.2-1B Page 9 of 103
PL-NF-21-003 Rev. 0 Page 10 of 103 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 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 5.2-1A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-1B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel Figure 5.2-2A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-2B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel b) Main Turbine Bypass Inoperable Figure 5.2-3A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-3B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel Figure 5.2-4A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-4B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel c) EOC-RPT Inoperable Figure 5.2-5A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-5B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel
PL-NF-21-003 Rev. 0 Page 11 of 103 Figure 5.2-6A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-6B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel d) Backup Pressure Regulator Inoperable Figure 5.2-7A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-7B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel Figure 5.2-8A: Power Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-8B: Power Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-9A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-9B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel Figure 5.2-10A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 5.2-10B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel The MCPR limits in Figures 5.2-1A/5.2-1B through 5.2-10A/5.2-10B are valid for Two Loop operation.
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-21-003 Rev. 0 Page 12 of 103 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 21 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 30, 2.39 2.4 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 35, 2.24 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.1 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 USED IN DETERMINING MFLCPR 1.9 MCPR Operating Limit 1.8 1.7 1.6 40, 1.51 1.5 A B
1.4 1.3
REFERENCE:
T.S. 3.2.2 108, 1.25 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-1A Page 13 of 103
SSES UNIT 2 CYCLE 21 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.4 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 30, 2.23 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.1 35, 2.08 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 USED IN DETERMINING MFLCPR 1.9 MCPR Operating Limit 1.8 1.7 1.6 40, 1.51 1.5 A B
1.4 1.3
REFERENCE:
T.S. 3.2.2 108, 1.25 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-1B Page 14 of 103
SSES UNIT 2 CYCLE 21 4.0 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.2 ALL SCRAM INSERTION TIMES 23, 3.03 3.0 C 26, 2.92 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE 2.8 PER SR 3.7.6.1 AND 3.7.6.2 2.6 26.01, 2.49 USED IN DETERMINING MFLCPR MCPR Operating Limit 2.4 40, 2.14 2.2 50, 2.10 26.01, 2.27 2.0 60, 1.87 A
1.8 40, 1.90 50, 1.84 80, 1.61 60, 1.77 1.6 B 100, 1.55 1.4
REFERENCE:
T.S. 3.2.2 80, 1.53 100, 1.44 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-2A Page 15 of 103
SSES UNIT 2 CYCLE 21 4.0 3.8 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES 3.2 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE 2.8 PER SR 3.7.6.1 AND 3.7.6.2 23, 2.65 2.6 26, 2.57 23, 2.57 USED IN DETERMINING MFLCPR C 26, 2.46 MCPR Operating Limit 2.4 2.2 26.01, 2.12 2.0 40, 1.91 50, 1.91 26.01, 2.02 60, 1.75 1.8 A
80, 1.69 40, 1.84 50, 1.84 60, 1.74 1.6 B 100, 1.53 1.4
REFERENCE:
T.S. 3.2.2 80, 1.53 100, 1.41 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-2B Page 16 of 103
PL-NF-21-003 Rev. 0 Page 17 of 103 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 21 2.5 LEGEND 30, 2.39 2.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.3 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 35, 2.24 2.2 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.1 USED IN DETERMINING MFLCPR 2.0 1.9 1.8 MCPR Operating Limit 45, 1.73 1.7 A B 1.6 1.5 1.4 108, 1.41
REFERENCE:
T.S. 3.7.6 and 3.2.2 1.3 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-3A Page 18 of 103
SSES UNIT 2 CYCLE 21 2.5 LEGEND 2.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.3 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 30, 2.23 2.2 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.1 35, 2.08 USED IN DETERMINING MFLCPR 2.0 1.9 1.8 MCPR Operating Limit 45, 1.73 1.7 A B 1.6 1.5 1.4 108, 1.41
REFERENCE:
T.S. 3.7.6 and 3.2.2 1.3 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-3B Page 19 of 103
SSES UNIT 2 CYCLE 21 4.3 LEGEND 4.1 CURVE A: CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 26, 3.32 INSERTION TIME 3.9 23, 3.47 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.7 CURVE B: CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 26, 3.23 A
3.5 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 3.38 B 3.3 CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR C REALISTIC AVERAGE SCRAM INSERTION TIME 3.1 CURVE C: D 26, 3.01 23, 3.18 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE 2.9 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.7 CURVE D:
26, 2.92 26.01, 2.58 USED IN DETERMINING MFLCPR 23, 3.09 2.5 MCPR Operating Limit 40, 2.27 2.3 50, 2.22 26.01, 2.30 2.1 60, 2.00 1.9 A 40, 1.93 80, 1.73 1.7 50, 1.85 100, 1.73 60, 1.77 B 100, 1.55 1.5 80, 1.55
REFERENCE:
T.S. 3.7.6 and 3.2.2 1.3 10 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-4A Page 20 of 103
SSES UNIT 2 CYCLE 21 4.3 LEGEND 4.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.9 INSERTION TIME CURVE A: CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.7 26, 3.17 23, 3.41 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.5 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME A
3.3 CURVE B: B CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 26, 3.07 REALISTIC AVERAGE SCRAM INSERTION TIME 23, 3.31 3.1 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE 2.9 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 CURVE C:
C 26, 2.56 2.7 23, 2.77 D USED IN DETERMINING MFLCPR 2.5 MCPR Operating Limit CURVE D:
26, 2.46 26.01, 2.26 2.3 23, 2.67 40, 2.03 2.1 50, 2.03 60, 1.92 26.01, 2.08 A 1.9 80, 1.79 40, 1.89 50, 1.89 1.7 100, 1.73 60, 1.79
REFERENCE:
T.S. 3.7.6 and 3.2.2 B 100, 1.53 1.5 80, 1.55 1.3 10 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-4B Page 21 of 103
PL-NF-21-003 Rev. 0 Page 22 of 103 EOC-RPT Inoperable
SSES UNIT 2 CYCLE 21 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 30, 2.39 INSERTION TIME 2.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 35, 2.24 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.1 USED IN DETERMINING MFLCPR 2.0 1.9 MCPR Operating Limit 1.8 1.7 1.6 40, 1.51 1.5 A B 1.4
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 1.3 108, 1.25 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-5A Page 23 of 103
SSES UNIT 2 CYCLE 21 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 30, 2.23 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.1 35, 2.08 USED IN DETERMINING MFLCPR 2.0 1.9 MCPR Operating Limit 1.8 1.7 1.6 40, 1.51 1.5 A B 1.4 1.3
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 108, 1.25 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-5B Page 24 of 103
SSES UNIT 2 CYCLE 21 4.3 LEGEND 4.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.9 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.7 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.5 CURVE C: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 3.04 3.3 23, 3.15 CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR C REALISTIC AVERAGE SCRAM INSERTION TIME 3.1 D SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE 2.9 CURVE D: PER SR 3.7.6.1 AND 3.7.6.2 26, 2.92 23, 3.03 2.7 26.01, 2.61 USED IN DETERMINING MFLCPR 2.5 MCPR Operating Limit 40, 2.29 2.3 50, 2.22 26.01, 2.27 60, 2.05 2.1 A
1.9 80, 1.82 100, 1.79 40, 1.90 1.7 50, 1.84 60, 1.77 B 100, 1.53 1.5
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 80, 1.53 1.3 10 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-6A Page 25 of 103
SSES UNIT 2 CYCLE 21 4.3 4.1 LEGEND CURVE A:
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.9 INSERTION TIME 26, 2.77 23, 2.85 3.7 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.5 CURVE C: CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 26, 2.66 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 2.77 3.3 CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME 3.1 CURVE B:
26, 2.57 2.9 23, 2.65 A SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE C PER SR 3.7.6.1 AND 3.7.6.2 2.7 CURVE D:
B 26, 2.46 D USED IN DETERMINING MFLCPR 2.5 23, 2.57 MCPR Operating Limit 26.01, 2.35 2.3 40, 2.12 50, 2.12 60, 2.11 A 80, 2.11 2.1 26.01, 2.04 100, 1.93 1.9 40, 1.87 50, 1.87 1.7 60, 1.77
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 B 1.5 100, 1.50 80, 1.54 1.3 10 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-6B Page 26 of 103
PL-NF-21-003 Rev. 0 Page 27 of 103 Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 21 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.4 30, 2.39 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 35, 2.24 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.1 2.0 USED IN DETERMINING MFLCPR 1.9 MCPR Operating Limit 1.8 1.7 1.6 40, 1.51 1.5 A
B 1.4 1.3
REFERENCE:
T.S. 3.7.8 and 3.2.2 108, 1.25 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-7A Page 28 of 103
SSES UNIT 2 CYCLE 21 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.4 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 30, 2.23 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.1 35, 2.08 2.0 USED IN DETERMINING MFLCPR 1.9 MCPR Operating Limit 1.8 1.7 1.6 40, 1.51 1.5 A
B 1.4 1.3
REFERENCE:
T.S. 3.7.8 and 3.2.2 108, 1.25 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-7B Page 29 of 103
SSES UNIT 2 CYCLE 21 4.0 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.2 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES 23, 3.03 3.0 C 26, 2.92 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.8 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.6 26.01, 2.49 USED IN DETERMINING MFLCPR 2.4 26.01, 2.47 40, 2.20 MCPR Operating Limit 2.2 50, 2.10 40, 2.18 60, 1.90 2.0 50, 1.99 A 1.8 60, 1.90 80, 1.68 1.6 B 100, 1.55 80, 1.54 100, 1.44 1.4
REFERENCE:
T.S. 3.7.8 and 3.2.2 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-8A Page 30 of 103
SSES UNIT 2 CYCLE 21 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.2 ALL SCRAM INSERTION TIMES 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.8 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 2.65 2.6 26, 2.57 23, 2.57 USED IN DETERMINING MFLCPR C 26, 2.46 MCPR Operating Limit 2.4 2.2 26.01, 2.25 40, 2.00 2.0 50, 1.92 40, 1.98 60, 1.79 1.8 A 50, 1.92 80, 1.69 60, 1.78 1.6
REFERENCE:
T.S. 3.7.8 and 3.2.2 B 100, 1.53 1.4 80, 1.53 100, 1.41 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-8B Page 31 of 103
PL-NF-21-003 Rev. 0 Page 32 of 103 One TSV or TCV Closed
SSES UNIT 2 CYCLE 21 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 30, 2.39 INSERTION TIME 2.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.1 40, 2.09 2.0 USED IN DETERMINING MFLCPR 1.9 1.8 45, 1.70 1.7 MCPR Operating Limit A
1.6 B 1.5 108, 1.43 1.4 1.3
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 1.2 30 40 50 60 70 80 90 100 110 PL-NF-21-003 Total Core Flow (MLB/HR)
Rev. 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*
Page 33 of 103 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-9A
SSES UNIT 2 CYCLE 21 2.6 2.5 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.4 INSERTION TIME 2.3 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 30, 2.23 2.2 2.1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 40, 1.93 USED IN DETERMINING MFLCPR 1.9 1.8 45, 1.70 1.7 MCPR Operating Limit A
1.6 B 1.5 108, 1.43 1.4 1.3
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 1.2 30 40 50 60 70 80 90 100 110 PL-NF-21-003 Total Core Flow (MLB/HR)
Rev. 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*
Page 34 of 103 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-9B
SSES UNIT 2 CYCLE 21 4.0 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.2 ALL SCRAM INSERTION TIMES 23, 3.03 3.0 C 26, 2.92 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE 2.8 PER SR 3.7.6.1 AND 3.7.6.2 2.6 26.01, 2.49 USED IN DETERMINING MFLCPR MCPR Operating Limit 2.4 40, 2.14 2.2 A 50, 2.10 26.01, 2.27 2.0 60, 1.87 1.8 40, 1.90 75, 1.68 B 50, 1.84 60, 1.77 1.6 75, 1.59 1.4
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 1.2 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 5.2-10A Page 35 of 103
SSES UNIT 2 CYCLE 21 4.0 3.8 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES 3.2 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE 2.8 PER SR 3.7.6.1 AND 3.7.6.2 23, 2.65 2.6 26, 2.57 23, 2.57 USED IN DETERMINING MFLCPR MCPR Operating Limit 2.4 C 26, 2.46 2.2 26.01, 2.12 2.0 40, 1.91 A 50, 1.91 26.01, 2.02 60, 1.75 1.8 40, 1.84 B 50, 1.84 75, 1.71 60, 1.74 1.6 75, 1.58 1.4
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 1.2 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED Rev. 0 TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 5.2-10B Page 36 of 103
PL-NF-21-003 Rev. 0 Page 37 of 103 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable
PL-NF-21-003 Rev. 0 Page 38 of 103 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 6.2-2A: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-2B: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel Figure 6.2-3A: Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-3B: Power-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel b) Main Turbine Bypass Inoperable Figure 6.2-4A: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-4B: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel Figure 6.2-5A: Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-5B: Power-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel
PL-NF-21-003 Rev. 0 Page 39 of 103 c) EOC-RPT Inoperable Figure 6.2-6A: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-6B: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel Figure 6.2-7A: Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-7B: Power-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel d) Backup Pressure Regulator Inoperable Figure 6.2-8A: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-8B: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel Figure 6.2-9A: Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-9B: Power-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-10A: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-10B: Flow-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel Figure 6.2-11A: Power-Dependent LHGR Limit Multiplier for ATRIUMTM-10 Fuel Figure 6.2-11B: Power-Dependent LHGR Limit Multiplier for ATRIUMTM 11 Fuel The LHGR limits and LHGR limit multipliers in Figures 6.2-1A/6.2-1B through 6.2-11A/6.2-11B are valid for both Two Loop and Single Loop operation.
SSES UNIT 2 CYCLE 21 16.0 14.0
REFERENCE:
T.S. 3.2.3 0.0, 13.4 18900, 13.4 USED IN DETERMINING FDLRX 12.0 10.0 8.0 74400, 7.1 Linear Heat Generation Rate Limit (kw/ft) 6.0 4.0 0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWD/MTU)
PL-NF-21-003 LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE ATRIUMTM-10 FUEL Rev. 0 FIGURE 6.2-1A Page 40 of 103
SSES UNIT 2 CYCLE 21 16.0 14.0 0, 13.6 21000, 13.6
REFERENCE:
T.S. 3.2.3 USED IN DETERMINING FDLRX 12.0 53000, 10.2 10.0 8.0 6.0 Linear Heat Generation Rate Limit (kw/ft) 4.0 80000, 3.5 2.0 0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWD/MTU)
PL-NF-21-003 LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE ATRIUMTM 11 FUEL Rev. 0 FIGURE 6.2-1B Page 41 of 103
PL-NF-21-003 Rev. 0 Page 42 of 103 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 21 1.10 1.00 108, 1.00 80, 1.00 0.90 0.80 0.70 40, 0.64 0.60
REFERENCE:
T.S. 3.2.3 Flow Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 30, 0.42 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 0 ATRIUMTM-10 FUEL FIGURE 6.2-2A Page 43 of 103
SSES UNIT 2 CYCLE 21 1.10 1.00 108, 1.00 80, 1.00 0.90 0.80 0.70 40, 0.64 0.60
REFERENCE:
T.S. 3.2.3 Flow Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 30, 0.43 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 0 ATRIUMTM 11 FUEL FIGURE 6.2-2B Page 44 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 100, 1.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 0.90 A
0.80 0.70 26.01, 0.64
REFERENCE:
T.S. 3.2.3 0.60 Power Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 26, 0.49 B
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 23, 0.42 26, 0.45 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 23, 0.35 0.30 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ATRIUMTM-10 FUEL Rev. 0 FIGURE 6.2-3A Page 45 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 100, 1.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 0.90 A
0.80 0.70 26.01, 0.65 0.60
REFERENCE:
T.S. 3.2.3 Power Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 26, 0.43 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES B ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 26, 0.40 23, 0.37 0.30 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ATRIUMTM 11 FUEL Rev. 0 FIGURE 6.2-3B Page 46 of 103
PL-NF-21-003 Rev. 0 Page 47 of 103 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 21 1.10 1.00 100, 0.98 108, 1.00 0.90 0.80 0.70 0.60 40, 0.55
REFERENCE:
T.S. 3.2.3 and 3.7.6 Flow Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 0.40 30, 0.37 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE Rev. 0 ATRIUMTM-10 FUEL FIGURE 6.2-4A Page 48 of 103
SSES UNIT 2 CYCLE 21 1.10 1.00 100, 0.97 108, 1.00 0.90 0.80 0.70 0.60 40, 0.56
REFERENCE:
T.S. 3.2.3 and 3.7.6 Flow Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 0.40 30, 0.39 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE Rev. 0 ATRIUMTM 11 FUEL FIGURE 6.2-4B Page 49 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 94.99, 0.96 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 0.90 100, 0.90 95, 0.90 0.80 80, 0.83 A
0.70 0.60 Power Dependent LHGR Multiplier 26.01, 0.59
REFERENCE:
T.S. 3.2.3 and 3.7.6 0.50 26, 0.49 B USED IN DETERMINING FDLRX 23, 0.42 0.40 26, 0.40 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 23, 0.35 0.30 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE Rev. 0 ATRIUMTM-10 FUEL FIGURE 6.2-5A Page 50 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 94.99, 0.97 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 0.90 100, 0.90 80, 0.91 95, 0.90 0.80 A
0.70 26.01, 0.65 0.60 Power Dependent LHGR Multiplier
REFERENCE:
T.S. 3.2.3 and 3.7.6 0.50 USED IN DETERMINING FDLRX 26, 0.43 B
0.40 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS 23, 0.37 26, 0.37 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 23, 0.33 0.30 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE Rev. 0 ATRIUMTM 11 FUEL FIGURE 6.2-5B Page 51 of 103
PL-NF-21-003 Rev. 0 Page 52 of 103 EOC-RPT Inoperable
SSES UNIT 2 CYCLE 21 1.10 80, 1.00 1.00 108, 1.00 0.90 0.80 0.70 40, 0.64 0.60
REFERENCE:
T.S. 3.2.3 and 3.3.4.1 Flow Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 30, 0.42 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER EOC-RPT INOPERABLE Rev. 0 ATRIUMTM-10 FUEL FIGURE 6.2-6A Page 53 of 103
SSES UNIT 2 CYCLE 21 1.10 80, 1.00 1.00 108, 1.00 0.90 0.80 0.70 40, 0.64 0.60
REFERENCE:
T.S. 3.2.3 and 3.3.4.1 Flow Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 30, 0.43 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER EOC-RPT INOPERABLE Rev. 0 ATRIUMTM 11 FUEL FIGURE 6.2-6B Page 54 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 100, 1.00 0.90 0.80 A 80, 0.83 0.70 0.60 Power Dependent LHGR Multiplier 26.01, 0.59
REFERENCE:
T.S. 3.2.3 and 3.3.4.1 0.50 26, 0.49 USED IN DETERMINING FDLRX B
23, 0.42 0.40 26, 0.40 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 0.35 0.30 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER EOC-RPT INOPERABLE Rev. 0 ATRIUMTM-10 FUEL FIGURE 6.2-7A Page 55 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 100, 0.99 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 0.90 80, 0.91 0.80 A 0.70 26.01, 0.65 0.60 Power Dependent LHGR Multiplier
REFERENCE:
T.S. 3.2.3 and 3.3.4.1 0.50 USED IN DETERMINING FDLRX 26, 0.43 B
0.40 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 23, 0.37 26, 0.37 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 0.33 0.30 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER EOC-RPT INOPERABLE Rev. 0 ATRIUMTM 11 FUEL FIGURE 6.2-7B Page 56 of 103
PL-NF-21-003 Rev. 0 Page 57 of 103 Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 21 1.10 80, 1.00 1.00 108, 1.00 0.90 0.80 0.70 40, 0.64 0.60
REFERENCE:
T.S. 3.2.3 and 3.7.8 Flow Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 30, 0.42 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 ATRIUMTM-10 FUEL FIGURE 6.2-8A Page 58 of 103
SSES UNIT 2 CYCLE 21 1.10 80, 1.00 1.00 108, 1.00 0.90 0.80 0.70 40, 0.64 0.60
REFERENCE:
T.S. 3.2.3 and 3.7.8 Flow Dependent LHGR Multiplier USED IN DETERMINING FDLRX 0.50 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 30, 0.43 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 ATRIUMTM 11 FUEL FIGURE 6.2-8B Page 59 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 100, 1.00 0.90 0.80 A
0.70 26.01, 0.64 0.60 Power Dependent LHGR Multiplier
REFERENCE:
T.S. 3.2.3 and 3.7.8 0.50 26, 0.49 B USED IN DETERMINING FDLRX 26, 0.45 23, 0.42 0.40 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 0.35 0.30 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 ATRIUMTM-10 FUEL FIGURE 6.2-9A Page 60 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 100, 1.00 0.90 0.80 A 0.70 26.01, 0.65 0.60 Power Dependent LHGR Multiplier
REFERENCE:
T.S. 3.2.3 and 3.7.8 0.50 USED IN DETERMINING FDLRX 26, 0.43 B
0.40 26, 0.40 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 0.37 0.30 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 ATRIUMTM 11 FUEL FIGURE 6.2-9B Page 61 of 103
PL-NF-21-003 Rev. 0 Page 62 of 103 One TSV or TCV Closed
SSES UNIT 2 CYCLE 21 1.10 1.00 108, 0.95 0.90 0.80 0.70 0.60
REFERENCE:
T.S. 3.2.3 and TRM 3.3.7 Flow Dependent LHGR Multiplier 40, 0.52 0.50 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 30, 0.35 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED*
ATRIUMTM-10 FUEL Rev. 0 FIGURE 6.2-10A
- Operation with one TSV or TCV closed is only supported at power levels 75% rated power Page 63 of 103
SSES UNIT 2 CYCLE 21 1.10 1.00 108, 0.94 0.90 0.80 0.70 0.60
REFERENCE:
T.S. 3.2.3 and TRM 3.3.7 Flow Dependent LHGR Multiplier 40, 0.52 0.50 USED IN DETERMINING FDLRX SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.40 30, 0.37 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
PL-NF-21-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED*
Rev. 0 ATRIUMTM 11 FUEL FIGURE 6.2-10B
- Operation with one TSV or TCV closed is only supported at power levels 75% rated power Page 64 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 0.90 75, 0.88 0.80 A 0.70 26.01, 0.64 0.60 Power Dependent LHGR Multiplier
REFERENCE:
T.S. 3.2.3 and TRM 3.3.7 0.50 26, 0.49 B USED IN DETERMINING FDLRX 26, 0.45 0.40 23, 0.42 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 0.35 0.30 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED ATRIUMTM-10 FUEL Rev. 0 FIGURE 6.2-11A Page 65 of 103
SSES UNIT 2 CYCLE 21 1.10 LEGEND CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 0.90 75, 0.89 0.80 A 0.70 26.01, 0.65 0.60 Power Dependent LHGR Multiplier
REFERENCE:
T.S. 3.2.3 and TRM 3.3.7 0.50 USED IN DETERMINING FDLRX 26, 0.43 B SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 0.40 26, 0.40 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 0.37 0.30 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED ATRIUMTM 11 FUEL Rev. 0 FIGURE 6.2-11B Page 66 of 103
PL-NF-21-003 Rev. 0 Page 67 of 103 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-21-003 Rev. 0 Page 68 of 103 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value(1) 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 107.6 107.2 (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 MCPR (2,3,4)
(% of Rated) 28 and < 90 < 1.76 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-21-003 Rev. 0 Page 69 of 103 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 8.2-2A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-2B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel Figure 8.2-3A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-3B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel b) Main Turbine Bypass Inoperable Figure 8.2-4A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-4B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel
PL-NF-21-003 Rev. 0 Page 70 of 103 Figure 8.2-5A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-5B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel c) EOC-RPT Inoperable Figure 8.2-6A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-6B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel Figure 8.2-7A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-7B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel d) Backup Pressure Regulator Inoperable Figure 8.2-8A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-8B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel Figure 8.2-9A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-9B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-10A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-10B: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel Figure 8.2-11A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM-10 Fuel Figure 8.2-11B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUMTM 11 Fuel The MCPR limits in Figures 8.2-2A/8.2-2B through 8.2-11A/8.2-11B 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
PL-NF-21-003 Rev. 0 Page 71 of 103 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.
SSES UNIT 2 CYCLE 21 16.00 REFERENCE T.S. 3.4.1 and 3.2.1 14.00 USED IN DETERMINING MAPRAT 12.00 0, 10.00 15000, 10.00 Average Planar 10.00 8.00 Linear Heat Generation Rate Limit (kw/ft) 6.00 67000, 5.60 4.00 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU)
PL-NF-21-003 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - SINGLE LOOP OPERATION Rev. 0 ATRIUMTM-10 FUEL FIGURE 8.2-1A Page 72 of 103
SSES UNIT 2 CYCLE 21 16.00 REFERENCE T.S. 3.4.1 and 3.2.1 14.00 USED IN DETERMINING MAPRAT 12.00 Average Planar 0, 9.60 20000, 9.60 10.00 8.00 60000, 7.20 Linear Heat Generation Rate Limit (kw/ft) 6.00 69000, 5.76 4.00 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU)
PL-NF-21-003 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - SINGLE LOOP OPERATION Rev. 0 ATRIUMTM 11 FUEL FIGURE 8.2-1B Page 73 of 103
PL-NF-21-003 Rev. 0 Page 74 of 103 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 30, 2.39 2.4 35, 2.24 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 USED IN DETERMINING MFLCPR 1.8 MCPR Operating Limit 1.6 A B 40, 1.51 52, 1.46 1.4 1.2
REFERENCE:
T.S. 3.4.1 and 3.2.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 8.2-2A Page 75 of 103
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 30, 2.23 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 35, 2.08 2.0 USED IN DETERMINING MFLCPR 1.8 MCPR Operating Limit 1.6 A B 40, 1.51 52, 1.46 1.4 1.2
REFERENCE:
T.S. 3.4.1 and 3.2.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 8.2-2B Page 76 of 103
SSES UNIT 2 CYCLE 21 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES 3.2 23, 3.06 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.0 26, 2.95 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C
2.8 USED IN DETERMINING MFLCPR 2.6 26.01, 2.52 MCPR Operating Limit 2.4 40, 2.17 2.2 A 50, 2.13 26.01, 2.30 2.0 60, 1.90 40, 1.93 B 67.2, 1.81 1.8 50, 1.87 60, 1.80 67.2, 1.72 1.6
REFERENCE:
T.S. 3.4.1 and 3.2.2 1.4 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Rev. 0 ATRIUMTM-10 FUEL FIGURE 8.2-3A Page 77 of 103
SSES UNIT 2 CYCLE 21 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES 3.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.0 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 23, 2.68 USED IN DETERMINING MFLCPR 2.6 26, 2.60 23, 2.60 26, 2.49 C
MCPR Operating Limit 2.4 2.2 26.01, 2.15 A 67.2, 2.06 2.0 26.01, 2.06 B 40, 2.06 1.8 1.6
REFERENCE:
T.S. 3.4.1 and 3.2.2 1.4 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
Rev. 0 ATRIUMTM 11 FUEL FIGURE 8.2-3B Page 78 of 103
PL-NF-21-003 Rev. 0 Page 79 of 103 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 30, 2.39 2.4 35, 2.24 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.2 USED IN DETERMINING MFLCPR 2.0 1.8 A MCPR Operating Limit B
52, 1.69 45, 1.73 1.6 1.4
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
Rev. 0 ATRIUMTM-10 FUEL FIGURE 8.2-4A Page 80 of 103
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 30, 2.23 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.2 35, 2.08 USED IN DETERMINING MFLCPR 2.0 1.8 MCPR Operating Limit A B 52, 1.69 45, 1.73 1.6 1.4
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
Rev. 0 ATRIUMTM 11 FUEL FIGURE 8.2-4B Page 81 of 103
SSES UNIT 2 CYCLE 21 4.4 LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.0 CURVE A: INSERTION TIME 26, 3.35 3.8 23, 3.50 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.6 CURVE B: A MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 3.26 3.4 23, 3.41 B CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME 3.2 C CURVE C: D 26, 3.04 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS 3.0 23, 3.21 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.8 CURVE D: 26.01, 2.61 USED IN DETERMINING MFLCPR 2.6 26, 2.95 MCPR Operating Limit 23, 3.12 2.4 40, 2.30 50, 2.25 2.2 26.01, 2.33 A
60, 2.03 2.0 67.2, 1.94 40, 1.96 1.8 50, 1.88 B 67.2, 1.72 60, 1.80 1.6
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1.4 10 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 8.2-5A Page 82 of 103
SSES UNIT 2 CYCLE 21 4.4 LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.0 INSERTION TIME CURVE A:
26, 3.20 3.8 23, 3.44 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.6 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR A MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B:
3.4 26, 3.10 23, 3.34 B CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME 3.2 3.0 CURVE C:
26, 2.59 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS 23, 2.80 C VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.8 D
2.6 USED IN DETERMINING MFLCPR MCPR Operating Limit CURVE D:
26, 2.49 2.4 23, 2.70 26.01, 2.29 2.2 A
67.2, 2.06 2.0 26.01, 2.11 B 40, 2.06 1.8 1.6
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1.4 10 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 8.2-5B Page 83 of 103
PL-NF-21-003 Rev. 0 Page 84 of 103 EOC-RPT Inoperable
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 30, 2.39 2.4 35, 2.24 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.2 USED IN DETERMINING MFLCPR 2.0 1.8 MCPR Operating Limit 1.6 A B 40, 1.51 52, 1.46 1.4 1.2
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 8.2-6A Page 85 of 103
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 30, 2.23 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.2 35, 2.08 USED IN DETERMINING MFLCPR 2.0 1.8 MCPR Operating Limit 1.6 A B 40, 1.51 52, 1.46 1.4 1.2
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 8.2-6B Page 86 of 103
SSES UNIT 2 CYCLE 21 4.4 LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.0 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.6 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE C:
CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 26, 3.07 23, 3.18 REALISTIC AVERAGE SCRAM INSERTION TIME 3.2 C D SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.0 CURVE D: ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 26, 2.95 2.8 23, 3.06 26.01, 2.64 USED IN DETERMINING MFLCPR 2.6 MCPR Operating Limit 40, 2.32 2.4 50, 2.25 A
2.2 26.01, 2.30 60, 2.08 2.0 67.2, 2.00 40, 1.93 1.8 50, 1.87 B 67.2, 1.72 60, 1.80 1.6
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.4 10 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 8.2-7A Page 87 of 103
SSES UNIT 2 CYCLE 21 4.4 LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.0 INSERTION TIME CURVE A:
3.8 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 26, 2.80 23, 2.88 3.6 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE C:
26, 2.69 CURVE D: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 23, 2.80 REALISTIC AVERAGE SCRAM INSERTION TIME 3.2 3.0 CURVE B:
26, 2.60 A SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 23, 2.68 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 C B
2.6 CURVE D: USED IN DETERMINING MFLCPR D
MCPR Operating Limit 26, 2.49 23, 2.60 26.01, 2.38 2.4 40, 2.15 50, 2.15 A 2.2 60, 2.14 67.2, 2.14 2.0 26.01, 2.07 40, 2.06 67.2, 2.06 50, 2.06 B 60, 2.06 1.8 1.6
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.4 10 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 8.2-7B Page 88 of 103
PL-NF-21-003 Rev. 0 Page 89 of 103 Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 30, 2.39 2.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 35, 2.24 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.2 USED IN DETERMINING MFLCPR 2.0 1.8 MCPR Operating Limit 1.6 A B 40, 1.51 52, 1.46 1.4 1.2
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL Page 90 of 103 FIGURE 8.2-8A
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 30, 2.23 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.2 35, 2.08 USED IN DETERMINING MFLCPR 2.0 1.8 MCPR Operating Limit 1.6 A B 40, 1.51 52, 1.46 1.4 1.2
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL Page 91 of 103 FIGURE 8.2-8B
SSES UNIT 2 CYCLE 21 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES 3.2 23, 3.06 3.0 C 26, 2.95 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 2.6 26.01, 2.52 USED IN DETERMINING MFLCPR 2.4 26.01, 2.50 40, 2.23 2.2 50, 2.13 40, 2.21 A MCPR Operating Limit 2.0 60, 1.93 50, 2.02 B 67.2, 1.86 1.8 60, 1.93
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 67.2, 1.80 1.6 1.4 20 30 40 50 60 70 80 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER PL-NF-21-003 BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Rev. 0 ATRIUMTM-10 FUEL FIGURE 8.2-9A Page 92 of 103
SSES UNIT 2 CYCLE 21 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES 3.2 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 23, 2.68 2.6 26, 2.60 USED IN DETERMINING MFLCPR 23, 2.60 C 26, 2.49 2.4 2.2 26.01, 2.28 40, 2.06 67.2, 2.06 MCPR Operating Limit 2.0 A B 1.8 1.6
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 1.4 20 30 40 50 60 70 80 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER PL-NF-21-003 BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Rev. 0 ATRIUMTM 11 FUEL FIGURE 8.2-9B Page 93 of 103
PL-NF-21-003 Rev. 0 Page 94 of 103 One TSV or TCV Closed
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 30, 2.39 2.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 40, 2.09 2.0 USED IN DETERMINING MFLCPR 1.8 MCPR Operating Limit A B 52, 1.67 45, 1.70 1.6 1.4 1.2
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL Page 95 of 103 FIGURE 8.2-10A
SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 30, 2.23 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 40, 1.93 USED IN DETERMINING MFLCPR 1.8 MCPR Operating Limit A B 52, 1.67 45, 1.70 1.6 1.4 1.2
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL Page 96 of 103 FIGURE 8.2-10B
SSES UNIT 2 CYCLE 21 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES 3.2 23, 3.06 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.0 26, 2.95 C ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 USED IN DETERMINING MFLCPR 2.6 26.01, 2.52 MCPR Operating Limit 2.4 40, 2.17 2.2 26.01, 2.30 50, 2.13 A
2.0 60, 1.90 1.8 40, 1.93 67.2, 1.81 50, 1.87 B 60, 1.80 67.2, 1.72 1.6
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 1.4 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10 FUEL FIGURE 8.2-11A Page 97 of 103
SSES UNIT 2 CYCLE 21 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR ALL SCRAM INSERTION TIMES 3.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.0 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 23, 2.68 USED IN DETERMINING MFLCPR 26, 2.60 2.6 23, 2.60 26, 2.49 C
MCPR Operating Limit 2.4 2.2 26.01, 2.15 A
67.2, 2.06 2.0 26.01, 2.06 B 40, 2.06 1.8 1.6
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 1.4 20 30 40 50 60 70 80 Core Power (% RATED)
PL-NF-21-003 MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED Rev. 0 SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM 11 FUEL FIGURE 8.2-11B Page 98 of 103
PL-NF-21-003 Rev. 0 Page 99 of 103 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.
PL-NF-21-003 Rev. 0 Page 100 of 103 120 120
-,-- -~- UNIT2 t !
Purpose:
I I I I I
' I I I I > I I I -
_ _ I.,. _ .,I _ _ I,__ ..J _ _ - ~- -o---
I I I 1 * ; '
_.._ _ _ _ ... _.1 __ ...
-!---l-1--1 I I C I 110 110 Initial/ Date: - ,.. - --,.--"I--
1-1-:-:~:-i:-:+:-~~i-: -l:~:-lj-f::~~:::'.:~:°::!:~A:',. P-:_R~~;~_f:_f_"'f~~~
STABILITY REGION I IF OPRM INOPERABLE IMMEDIATELY SCRAM IAW APPLICABLE PROCEDURE.
100 IF OPRM OPERABLE IMMEDIAlELY 100 EXITIAW APPLICABLE PROCEDURE.
--r--.--r-.,--
I l I I STABILITY REGION JI
--.t--.. -
' I I I I I l I I I I I I IMMEDIATELY EXITIAWAPPLICABLE - - t - - - i- -t---.t--
' I I I I I I I PROCEDURE. ------1--&.--1-- --1--&.-
I I , t I I I inr}l' I l I I I I 90 90 I I I I I I RESTRICTED REGION I I
I I
I I
I I
1 I
l 1
I I
l I
IF ABOVE MELLLA BOUNDARY, I I I l I I I IMMEDIATELY EXIT IAW APPLICABLE PROCEDURE.
80 _µ,;::=i=:~:=i=:=F=,!='!,=i=,=i=,=t==!,=i=,=i=,~.=i==i=,=i=,:::;:,=i=,4...:,!-!,-
~:q: :rrr: :p:p:: :rr:r--
80
-r-1--r- --:--i--r -t--:--t-7-- -~--1--:--:- --t-0 f-:--:-:--:- --: -:--: -:-- -:- : -:- : - -+-t-w 70 l
!<<0::: 70 I I I I I I I I l I I I I 1 I
,_ _,1_
' t '
I I I I I I I I
-;... T~l+T1+f
_.,1 __ L_..1 __ 1,._ - - L - ..l __
I I l t ! 1 1 I I I I I I I I I
~
60 _..,! __ ._ I _ _.I __ I._ _ _ _ 1-_
I t
..I __ ,.._.,_
60 0
a..
I ! I I 1 I
-:--:-:--:- --:-1-t-:-
t I I I i I l I t I e
co
... :t:Ltt: :t:tt:t I I I I : : : :
50 Q) 50 +:~;:-:~f_-_j~,:~:~-:+:-:~~-~;-~:~+-:~j:+...;_..;._~~ . .
_,..'I __.' __... _...,' __ __, __. _...., __
- rr*-*-__._ ,_ ._,_
.c:
I- .
_,_ J' __ .'. '
I I I I !
I I
_..,J _ _ _ J __ .,_ _ _, _ _
--1-;--t--;-- - -!--t-t -
I I I I I I I
, I I I I I I 40
--:-T-r: --r-r- r- 40
' ' I
....I __ ,_
I ! _ ..* _ _ ,___
_ _ _ .. I i
- I I
..I --...
I l
.t _ _,_
I I
I
_ -- *I - ....I I
I l O i I t
+'"--,-1-..,.....,..__.,.:-_,---T-,.J
~ - - -
t ! j I I I I I I I I t I < t I t l t ( t j I I ! I I I l I I ! I I I I I I I I I I ! t >
- -' - - h - -'- - h - - -L*.l- _ ... _ _. -- *-' - *l- * " ' * * ' -
- _ _ ,_ _ ,. __ ,._ _ ... * * . . ... _ ..., __ ,. _..., _ _ _ ..., __ .. _ _,_.
- *I -:~:** *:**:*:**:~ **;-:~*:*:~* *:**-r*:-~:- **t*t**:**:~ *:~:**:*:~* -:--r-:--
I I I I I I I ! I I I I 1 I I t I I I > t I I
. . 1.. * ..1 ' ' r ' t r !
-r-1-* -~-1--r- --l*t*t*t**tt*r-i-- --r;--~-t--t~*1-*t**i-- -;-y-
- .1 *
- L . I I ' ' ' ' I ' ' ' I ' ' I '
- I l ! l I
--'--.l- -
30 30
> I I I
-- ... -~- -,--. -- - -.t --.-I - -.<- -,--
I I l l i I I
--,-I - I I I I l
l 1
I I
I I
- - -- J,.- -- ,- -
I t
I I
- - o. - +- - o. - -
I 1
t I
1 I
I I
(
t I
I t
~ . ........ - __. __ .. _., __ _.,_ _.., __ ._ __ _._ _., __. . _. . _ _,. __,._ __., __,._ __--i--* ---- - - _. . __, __ i_..., ___ ..., __.. _.., __
i I I I I O I I I I I I I I
t I
I t
I I
I I
I I
I I
I I
I I
I t
I I
1 t
I l
i*t-1--:--1--:-1-- -7*-*:-1--:- --:-;--:-:---1--i-*t*;- --:--:--i- -- **1--:- -;-t* --!*-:--:--
I l l I I 1 I I l I I I I I I j i
- I I < I I I I f I I I I I I I I I < I + I ! I > I
- I I I I I ! I ' 0 I 20
_J:;: -,-,-*,**-*-~*::**r Jf[I :iTU::fj} _InTTIT
' : Approx H,-+-++*HH-ll-:-+:-,:H-f-1--+++-f-H-++-++-+:-+:-+:-,:H-+:+! -;:-+:-+-.!-:-!:-+:-++-+,-+,-+,-;,--+-+:- :H:-liM- 20
~-l.* :_--_J,L_-~:~-~W-~'L:_ ~-~'Le_ m-~.~--*~.L_:1,:_ -H-:- . . -*
-:~-:-;~~:- --:-:~-;- ----:~;--;~:-- -y-:-:--
- _ . * , , , , , , , , Approx , , , , , , , , , , , , , , , , , , ,
- ; ; : : ; : : *t t *t :-- : -;~;--; --;-;- One Pump : - --:-;--;-;~-
):: ::t :::r::r *rrr - *_*:.._-.:-.*: :. : :;*.:- *.:.* : -:.,: _ -_*
10 . ' : : 80% Speed. : ' ' ' ' ' , : , '
- 10
-- *- -:- ,-:--:- *r:--:*:-- *:--:-:**:*---:-:--:-:-- -:--:-:-<- --:-:-+-- - -
1
-: .~: .-:-:.* -_1.--i-O+~!!==H-+~"'l==+-+-H--+~+++;-_-~;-~;1-**;_--l-*~\-~:~-+;_-~;-1--~*~;---+;_-~;--;-:1-*+**+:--~;-~-;1-*-1;-_--l--~;-~-;_-;-_-~;~-~--;_-+;-_-~~~-.--!--+-+-:~:--+:-+-:f-i:-+:~~ 0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbm/hr)
Figure 9.1 SSES Unit 2 Cycle 21 Power I Flow Map
PL-NF-21-003 Rev. 0 Page 101 of 103 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 MCPR Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:
SP = 1.12 NP = 16 FP = 60 Mlbm / hr
PL-NF-21-003 Rev. 0 Page 102 of 103
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.
- 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-21-003 Rev. 0 Page 103 of 103
- 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.