PLA-7909, Submittal of Unit 2 Cycle 20 Core Operating Limits Report, Revision 3, PLA-7909
| ML20335A308 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/30/2020 |
| From: | Cimorelli K Susquehanna, Talen Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-7909 | |
| Download: ML20335A308 (74) | |
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 November 30, 2020 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 20 CORE OPERATING LIMITS REPORT, REVISION 3 PLA-7909 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 20 COLR, Revision 3, is provided in the attachment. This revision is a result of updated licensing analysis which is documented in the Susquehanna Nuclear, LLC, Corrective Action Program. All changes are denoted by revision bars in the margin of the report.
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.
Attachment:
SSES Unit 2 Cycle 20 COLR, Revision 3 Copy: NRC Region I Mr. C. Highley, NRC Sr. Resident Inspector Ms. S. Goetz, NRC Project Manager Mr. M. Shields, PA DEP/BRP
Attachment to PLA-7909 SSES Unit 2 Cycle 20 COLR, Revision 3
PL-NF-19-003 Rev. 3 Page 1 of 72 Susquehanna SES Unit 2 Cycle 20 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering December 2020
PL-NF-19-003 Rev. 3 Page 2 of 72 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX REV AFFECTED NO. SECTIONS DESCRIPTION / PURPOSE OF REVISION Issuance of this COLR is in support of Unit 2 Cycle 20 operation.
0 ALL CR-2019-03732 is evaluating a condition that should it result in a revision to the COLR, will be submitted in accordance with Technical Specification 5.6.5.
1 ALL The U2C20 COLR is revised to include licensing analyses results for the revised U2C20 core design (CR-2019-03732).
Changes are made to the following figures: 5.2-1 through 5.2-10, 6.2-5, and 8.2-2 through 8.2-11. Changes to the thermal limits are limited to the following figures: 5.2-1 through 5.2-5, 5.2-7, 5.2-9, 5.2-10, 6.2-5, 8.2-2, 8.2-4, 8.2-6, 8.2-8, and 8.2-10. Only the captions were changed for the remaining figures (5.2-6, 5.2-8, 8.2-3, 8.2-5, 8.2-7, 8.2-9, 8.2-11).
Revision 1 of the Unit 2 Cycle 20 COLR is valid only for operation from BOC to MOC. MOC (Middle Of Cycle) is defined as a cycle exposure of 4,975 MWd/MTU.
2 ALL The U2C20 COLR is revised to include licensing analyses results for the full cycle of U2C20 operation.
Changes are made to the following figures: 5.2-1 to 5.2-10, 6.2-3, 6.2-5, 6.2-7, 6.2-9, and 8.2-2 to 8.2-11. Changes to the thermal limits are limited to the following figures: 5.2-4, 5.2-8, 6.2-3, 6.2-5, 6.2-7, 6.2-9, 8.2-5, and 8.2-9.
Only the captions were changed for the remaining figures (5.2-1 to 5.2-3, 5.2-5 to 5.2-7, 5.2-9, 5.2-10, 8.2-2 to 8.2-4, 8.2-6 to 8.2-8, 8.2-10, and 8.2-11).
Revision 2 of the Unit 2 Cycle 20 COLR is valid for operation from BOC to EOC.
3 ALL The U2C20 COLR is revised to include the updated licensing analyses from Framatome with revised operating limits (CR-2020-15813) and new limits using a new set of Optimal Scram Insertion Times from MOC to EOC (AR-2020-15255).
New figures are added: 5.2-11, 5.2-12, 6.2-10, and 6.2-11.
Changes are made to the following figures: 5.2-4, and 6.2-1.
Table 5.3-1 has been changed for new scram times.
Revision 3 of the Unit 2 Cycle 20 COLR includes fuel thermal operating limits valid from BOC to EOC and adds exposure-dependent limits valid from MOC to EOC, where MOC is a cycle exposure of 16,876.9 MWd/MTU.
FORM NFP-QA-008-2, Rev. 2
PL-NF-19-003 Rev. 3 Page 3 of 72 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 20 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) ............................................................ 9 6.0 LINEAR HEAT GENERATION RATE (LHGR) .............................................................. 30 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ......................................................................................................... 48 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION .......................................... 50 9.0 POWER / FLOW MAP................................................................................................... 68 10.0 OPRM SETPOINTS ...................................................................................................... 70
11.0 REFERENCES
.............................................................................................................. 71
PL-NF-19-003 Rev. 3 Page 4 of 72
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 20 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-19-003 Rev. 3 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.
2.6 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-19-003 Rev. 3 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-19-003 Rev. 3 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 4.2-1.
The APLHGR limits in Figure 4.2-1 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 20 16.0 REFERENCE T.S. 3.2.1 14.0 USED IN DETERMINING MAPRAT 0.0, 12.5 15000, 12.5 Average Planar 12.0 10.0 Linear Heat Generation Rate Limit (kw/ft) 8.0 67000, 6.9 6.0 4.0 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU) PL-NF-19-003 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS Rev. 3 AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION ATRIUMTM-10 FUEL Page 8 of 72 FIGURE 4.2-1
PL-NF-19-003 Rev. 3 Page 9 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 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) 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 Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-8: Power Dependent MCPR value determined from BOC to EOC e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-9: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-10: Power-Dependent MCPR value determined from BOC to EOC f) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable -
Optimal Scram Insertion Time Figure 5.2-11: Flow-Dependent MCPR value determined from MOC to EOC Figure 5.2-12: Power-Dependent MCPR value determined from MOC to EOC
PL-NF-19-003 Rev. 3 Page 10 of 72 The MCPR limits in Figures 5.2-1 through 5.2-12 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 Optimal Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Realistic Average Scram Insertion Time must be implemented. 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-19-003 Rev. 3 Page 11 of 72 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 20 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 MCPR Operating Limit 1.8 USED IN DETERMINING MFLCPR 1.7 30, 1.59 1.6 1.5 A B
1.4
REFERENCE:
T.S. 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-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) Page 12 of 72 FIGURE 5.2-1
SSES UNIT 2 CYCLE 20 3.6 3.4 LEGEND 23, 3.15 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.2 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 C 26, 3.00 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 2.8 MCPR Operating Limit 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.4 USED IN DETERMINING MFLCPR 2.2 26.01, 2.02 2.0 1.8 26.01, 1.91 40, 1.71 A
1.6 80, 1.45 B 100, 1.36 1.4
REFERENCE:
T.S. 3.2.2 80, 1.42 100, 1.32 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) Page 13 of 72 FIGURE 5.2-2
PL-NF-19-003 Rev. 3 Page 14 of 72 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 20 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.0 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1.9 USED IN DETERMINING MFLCPR MCPR Operating Limit 30, 1.78 1.8 1.7 A
B 1.6 90, 1.49 1.5 99, 1.42 1.4 108, 1.39
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-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC) Page 15 of 72 FIGURE 5.2-3
SSES UNIT 2 CYCLE 20 3.8 3.6 LEGEND 23, 3.48 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.4 INSERTION TIME 3.2 26, 3.20 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 23, 3.16 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.0 26, 3.01 C
MCPR Operating Limit 2.8 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE 2.6 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.4 USED IN DETERMINING MFLCPR 2.2 26.01, 2.06 2.0 40, 1.76 1.8 A B
1.6
REFERENCE:
T.S. 3.7.6 and 3.2.2 80, 1.54 100, 1.54 1.4 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC) Page 16 of 72 FIGURE 5.2-4
PL-NF-19-003 Rev. 3 Page 17 of 72 EOC-RPT Inoperable
SSES UNIT 2 CYCLE 20 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 MCPR Operating Limit 1.8 USED IN DETERMINING MFLCPR 1.7 30, 1.59 1.6 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-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC) Page 18 of 72 FIGURE 5.2-5
SSES UNIT 2 CYCLE 20 3.6 LEGEND 3.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 23, 3.17 INSERTION TIME 3.2 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 26, 3.02 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR C
2.8 MCPR Operating Limit 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.4 USED IN DETERMINING MFLCPR 2.2 26.01, 2.04 2.0 40, 1.73 1.8 A B 1.6 80, 1.47
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 100, 1.43 1.4 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC) Page 19 of 72 FIGURE 5.2-6
PL-NF-19-003 Rev. 3 Page 20 of 72 Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 20 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 MCPR Operating Limit 1.8 USED IN DETERMINING MFLCPR 1.7 30, 1.59 1.6 1.5 A B
1.4
REFERENCE:
T.S. 3.7.8 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-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) Page 21 of 72 FIGURE 5.2-7
SSES UNIT 2 CYCLE 20 3.6 3.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 23, 3.15 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 26, 3.00 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR C
2.8 MCPR Operating Limit 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.4 26.01, 2.27 USED IN DETERMINING MFLCPR 2.2 40, 2.08 2.0 A B
1.8 80, 1.47 1.6
REFERENCE:
T.S. 3.7.8 and 3.2.2 100, 1.36 1.4 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) Page 22 of 72 FIGURE 5.2-8
PL-NF-19-003 Rev. 3 Page 23 of 72 One TSV or TCV Closed
SSES UNIT 2 CYCLE 20 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 MCPR Operating Limit 30, 1.78 1.8 USED IN DETERMINING MFLCPR 1.7 A
B 1.6 1.5 108, 1.41 1.4
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 1.3 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 ONE TSV OR TCV CLOSED*
TWO LOOP OPERATION (BOC TO EOC) Page 24 of 72 FIGURE 5.2-9
SSES UNIT 2 CYCLE 20 3.4 23, 3.15 3.2 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.0 26, 3.00 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C
2.8 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 2.6 MCPR Operating Limit SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.4 2.2 USED IN DETERMINING MFLCPR 26.01, 2.02 2.0 1.8 26.01, 1.91 40, 1.71 A
1.6 75, 1.48 B
1.4
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 75, 1.45 1.2 20 30 40 50 60 70 80 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC) Page 25 of 72 FIGURE 5.2-10
PL-NF-19-003 Rev. 3 Page 26 of 72 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable - Optimal Scram Insertion Time
SSES UNIT 2 CYCLE 20 2.2 2.1 LEGEND CURVE A: OPTIMAL SCRAM INSERTION TIME 2.0 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 MCPR Operating Limit 1.8 USED IN DETERMINING MFLCPR 1.7 30, 1.59 1.6 1.5 A 1.4
REFERENCE:
T.S. 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-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 Page 27 of 72 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (MOC TO EOC)
OPTIMAL SCRAM INSERTION TIME FIGURE 5.2-11
SSES UNIT 2 CYCLE 20 3.6 3.4 LEGEND 3.2 23, 3.15 CURVE A: OPTIMAL SCRAM INSERTION TIME 3.0 B 26, 3.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 2.8 MCPR Operating Limit 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.4 USED IN DETERMINING MFLCPR 2.2 2.0 26.01, 1.80 1.8 1.6 40, 1.63 A
1.4
REFERENCE:
T.S. 3.2.2 80, 1.37 100, 1.32 90, 1.33 94.46, 1.32 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 Page 28 of 72 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (MOC TO EOC)
OPTIMAL SCRAM INSERTION TIME FIGURE 5.2-12
PL-NF-19-003 Rev. 3 Page 29 of 72 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 0.310 0.470 0.520 39 0.620 0.630 0.860 25 1.380 1.500 1.910 5 2.550 2.700 3.440 Average Scram Maximum Optimal Realistic Insertion Time Allowable
PL-NF-19-003 Rev. 3 Page 30 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 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is 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 Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) EOC-RPT or Backup Pressure Regulator Inoperable Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: Power-Dependent LHGR Limit Multiplier d) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-8: Flow-Dependent LHGR Limit Multiplier Figure 6.2-9: Power-Dependent LHGR Limit Multiplier e) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable -
Optimal Scram Insertion Time Figure 6.2-10: Flow-Dependent LHGR Limit Multiplier Figure 6.2-11: Power-Dependent LHGR Limit Multiplier
PL-NF-19-003 Rev. 3 Page 31 of 72 The LHGR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-11 are valid for both Two Loop and Single Loop operation.
SSES UNIT 2 CYCLE 20 16.0 14.0 0.0, 13.4 18900, 13.4
REFERENCE:
T.S. 3.2.3 USED IN DETERMINING FDLRX Linear Heat Generation Rate Limit (kw/ft) 12.0 10.0 8.0 74400, 7.1 76000, 6.9 6.0 4.0 0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWD/MTU) PL-NF-19-003 LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE Rev. 3 ATRIUMTM-10 FUEL FIGURE 6.2-1 Page 32 of 72
PL-NF-19-003 Rev. 3 Page 33 of 72 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 20 1.10 80, 1.00 1.00 108, 1.00 0.90 Flow Dependent LHGR Multiplier 0.80 30, 0.75 0.70 0.60
REFERENCE:
T.S. 3.2.3 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 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 Page 34 of 72 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ATRIUMTM-10 FUEL FIGURE 6.2-2
SSES UNIT 2 CYCLE 20 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 Power Dependent LHGR Multiplier 80, 0.91 A
0.80 0.70 26.01, 0.71 0.60
REFERENCE:
T.S. 3.2.3 USED IN DETERMINING FDLRX B 26, 0.50 0.50 23, 0.48 26, 0.48 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 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-19-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ATRIUMTM-10 FUEL Page 35 of 72 FIGURE 6.2-3
PL-NF-19-003 Rev. 3 Page 36 of 72 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 20 1.10 108, 0.99 1.00 0.90 Flow Dependent LHGR Multiplier 0.80 0.70 0.60
REFERENCE:
T.S. 3.2.3 and 3.7.6 30, 0.58 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 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 MAIN TURBINE BYPASS INOPERABLE ATRIUMTM-10 FUEL Page 37 of 72 FIGURE 6.2-4
SSES UNIT 2 CYCLE 20 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 Power Dependent LHGR Multiplier 100, 0.83 0.80 80, 0.83 95, 0.83 A
0.70 60, 0.71 0.60 26.01, 0.59
REFERENCE:
T.S. 3.2.3, and 3.7.6 0.50 B 26, 0.50 USED IN DETERMINING FDLRX 23, 0.46 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-19-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 Page 38 of 72 MAIN TURBINE BYPASS INOPERABLE ATRIUMTM-10 FUEL FIGURE 6.2-5
PL-NF-19-003 Rev. 3 Page 39 of 72 EOC-RPT or Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 20 1.10 80, 1.00 1.00 108, 1.00 0.90 Flow Dependent LHGR Multiplier 0.80 30, 0.75 0.70 0.60
REFERENCE:
T.S. 3.2.3, 3.3.4.1, and 3.7.8 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 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 Page 40 of 72 EOC-RPT OR BACKUP PRESSURE REGULATOR INOPERABLE ATRIUMTM-10 FUEL FIGURE 6.2-6
SSES UNIT 2 CYCLE 20 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 Power Dependent LHGR Multiplier 0.80 A 80, 0.83 0.70 60, 0.71 0.60 26.01, 0.59
REFERENCE:
T.S. 3.2.3, 3.3.4.1, and 3.7.8 0.50 B 26, 0.50 USED IN DETERMINING FDLRX 23, 0.46 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-19-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 Page 41 of 72 EOC-RPT OR BACKUP PRESSURE REGULATOR INOPERABLE ATRIUMTM-10 FUEL FIGURE 6.2-7
PL-NF-19-003 Rev. 3 Page 42 of 72 One TSV or TCV Closed
SSES UNIT 2 CYCLE 20 1.10 1.00 108, 0.94 0.90 Flow Dependent LHGR Multiplier 0.80 0.70 0.60
REFERENCE:
T.S. 3.2.3 and TRM 3.3.7 30, 0.55 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 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 ONE TSV OR TCV CLOSED*
ATRIUMTM-10 FUEL Page 43 of 72 FIGURE 6.2-8
SSES UNIT 2 CYCLE 20 1.10 LEGEND CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 0.90 Power Dependent LHGR Multiplier 75, 0.89 0.80 A
0.70 26.01, 0.71 0.60 B
REFERENCE:
T.S. 3.2.3 and TRM 3.3.7 26, 0.50 0.50 USED IN DETERMINING FDLRX 23, 0.48 26, 0.48 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 Core Power (% RATED) PL-NF-19-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 ONE TSV OR TCV CLOSED ATRIUMTM-10 FUEL Page 44 of 72 FIGURE 6.2-9
PL-NF-19-003 Rev. 3 Page 45 of 72 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable - Optimal Scram Insertion Time
SSES UNIT 2 CYCLE 20 1.10 80, 1.00 1.00 108, 1.00 0.90 Flow Dependent LHGR Multiplier 0.80 30, 0.75 0.70 0.60
REFERENCE:
T.S. 3.2.3 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 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 FLOW DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ATRIUMTM-10 FUEL Page 46 of 72 OPTIMAL SCRAM INSERTION TIME (MOC TO EOC)
FIGURE 6.2-10
SSES UNIT 2 CYCLE 20 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 80, 0.93 Power Dependent LHGR Multiplier A
0.80 26.01, 0.78 0.70 0.60
REFERENCE:
T.S. 3.2.3 USED IN DETERMINING FDLRX B 26, 0.50 0.50 23, 0.48 26, 0.48 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 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-19-003 POWER DEPENDENT LHGR LIMIT MULTIPLIER Rev. 3 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ATRIUMTM-10 FUEL Page 47 of 72 OPTIMAL SCRAM INSERTION TIME (MOC TO EOC)
FIGURE 6.2-11
PL-NF-19-003 Rev. 3 Page 48 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-19-003 Rev. 3 Page 49 of 72 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)
(% 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.
PL-NF-19-003 Rev. 3 Page 50 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 8.2-1.
The APLHGR limits in Figure 8.2-1 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) 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 Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOC
PL-NF-19-003 Rev. 3 Page 51 of 72 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 Figure 8.2-11:Power-Dependent MCPR value determined from BOC to EOC The MCPR limits in Figures 8.2-2 through 8.2-11 are valid only for Single Loop operation.
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 20 16.0 REFERENCE T.S. 3.4.1 and 3.2.1 14.0 USED IN DETERMINING MAPRAT Average Planar 12.0 0.0, 10.0 15000, 10.0 10.0 Linear Heat Generation Rate Limit (kw/ft) 8.0 6.0 67000, 5.6 4.0 0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 Average Planar Exposure (MWD/MTU) PL-NF-19-003 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS Rev. 3 AVERAGE PLANAR EXPOSURE - SINGLE LOOP OPERATION ATRIUMTM-10 FUEL Page 52 of 72 FIGURE 8.2-1
PL-NF-19-003 Rev. 3 Page 53 of 72 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 20 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 MCPR Operating Limit 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 USED IN DETERMINING MFLCPR 1.8 30, 1.62 1.6 A
B 1.4 108, 1.28 1.2
REFERENCE:
T.S. 3.4.1 and 3.2.2 1.0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Page 54 of 72 FIGURE 8.2-2
SSES UNIT 2 CYCLE 20 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 23, 3.18 3.2 C
MCPR Operating Limit 3.0 26, 3.03 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 USED IN DETERMINING MFLCPR 2.6 2.4 2.2 26.01, 2.05 2.0 40, 1.74 1.8 A B
60, 1.61 1.6
REFERENCE:
T.S. 3.4.1 and 3.2.2 100, 1.61 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Page 55 of 72 FIGURE 8.2-3
PL-NF-19-003 Rev. 3 Page 56 of 72 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 20 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 TWO OR MORE BYPASS MCPR Operating Limit VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.2 USED IN DETERMINING MFLCPR 2.0 30, 1.81 1.8 90, 1.52 1.6 A 99, 1.45 B
1.4 108, 1.42
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1.2 1.0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Page 57 of 72 FIGURE 8.2-4
SSES UNIT 2 CYCLE 20 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 23, 3.51 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 23, 3.19 26, 3.23 3.2 C
MCPR Operating Limit 3.0 26, 3.04 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.8 USED IN DETERMINING MFLCPR 2.6 2.4 2.2 26.01, 2.09 2.0 40, 1.79 A B 1.8 60, 1.66
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 100, 1.66 1.6 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Page 58 of 72 FIGURE 8.2-5
PL-NF-19-003 Rev. 3 Page 59 of 72 EOC-RPT Inoperable
SSES UNIT 2 CYCLE 20 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 MCPR Operating Limit ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.2 USED IN DETERMINING MFLCPR 2.0 1.8 30, 1.62 1.6 1.4 108, 1.28 A
B 1.2
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Page 60 of 72 FIGURE 8.2-6
SSES UNIT 2 CYCLE 20 4.0 3.8 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 23, 3.20 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.2 C 26, 3.05 3.0 MCPR Operating Limit 2.8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.6 USED IN DETERMINING MFLCPR 2.4 2.2 26.01, 2.07 2.0 40, 1.76 1.8 60, 1.63 A B 1.6 100, 1.63
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.4 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Page 61 of 72 FIGURE 8.2-7
PL-NF-19-003 Rev. 3 Page 62 of 72 Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 20 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 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 MCPR Operating Limit 2.2 USED IN DETERMINING MFLCPR 2.0 1.8 30, 1.62 1.6 1.4 108, 1.28 A
B 1.2
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 1.0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 Page 63 of 72 BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
FIGURE 8.2-8
SSES UNIT 2 CYCLE 20 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 23, 3.18 3.2 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.0 C 26, 3.03 2.8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.6 MCPR Operating Limit USED IN DETERMINING MFLCPR 2.4 26.01, 2.30 2.2 40, 2.11 A
2.0 B
60, 1.81 1.8 100, 1.81
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 1.6 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) Page 64 of 72 FIGURE 8.2-9
PL-NF-19-003 Rev. 3 Page 65 of 72 One TSV or TCV Closed
SSES UNIT 2 CYCLE 20 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 MCPR Operating Limit 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 USED IN DETERMINING MFLCPR 30, 1.81 1.8 1.6 108, 1.44 A B 1.4 1.2
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 1.0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 3 ONE TSV OR TCV CLOSED*
SINGLE LOOP OPERATION (BOC TO EOC) Page 66 of 72 FIGURE 8.2-10
SSES UNIT 2 CYCLE 20 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 23, 3.18 3.2 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR C 26, 3.03 3.0 MCPR Operating Limit SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 2.6 USED IN DETERMINING MFLCPR 2.4 2.2 26.01, 2.05 2.0 40, 1.74 1.8 A B
60, 1.61 1.6
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 75, 1.61 1.4 20 30 40 50 60 70 80 Core Power (% RATED) PL-NF-19-003 MCPR OPERATING LIMIT VERSUS CORE POWER Rev. 3 ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC) Page 67 of 72 FIGURE 8.2-11
PL-NF-19-003 Rev. 3 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.
PL-NF-19-003 Rev. 3 Page 69 of 72 120 110 110 Initial/ Date:
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- .I--L-.l.
30 30 I I > I
- * * * * > * , < I I ! I I ! I t t t l
-r i I ! : : : :
- - --:-:--:--:- -;--:-;--i---
--:-r--i--t- -:----;-~-- -:--t--i--
20 ' .~-A_w_ro_x~~*++~r~HHH+&++rrH~+++rrHHH++~,H.H,+,+~,-,+,+,H,-+-, 20
-r-1--r-1-- -r-1--r- --r-r-t-r- -r----t-1-- -r-t
~~lf:~r:~~f~~
-i-~ Two Pump -i-10
-\t( :ttf~: tl:=~=t= =t::::t:( :(t:t: ,
IHHI 10 t:t~t~t- :t-l~1~-~~ ~1J:l:t I I l l t 1 I f I t I l i I
- + :t:(t:( :~=r~t tl)l :(~t:~ =:ri:t:i:
-,--r - -,--~-,--~- __
0 0 0 10 20 30 -40 60 IO 70 80 80 100 110 Total Gore Flow (Mlbm/hr)
Figure 9.1 SSES Unit 2 Cycle 20 Power I Flow Map
PL-NF-19-003 Rev. 3 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 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-19-003 Rev. 3 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.
- 3. EMF-2292(P)(A), Revision 0, ATRIUM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.
- 5. 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.
- 6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982.
- 7. 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.
- 8. 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.
- 9. 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.
- 10. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"
November 1990.
- 11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
- 12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.
PL-NF-19-003 Rev. 3 Page 72 of 72
- 13. EMF-2209(P)(A), Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
- 14. 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.
- 15. 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.
- 16. 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.
- 17. NEDO-32465-A, BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, August 1996.
- 18. ANF-913(P)(A), Volume 1 Revision 1 and Volume 1 Supplements 2, 3, and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.