PLA-7765, Submittal of Cycle 19 Core Operating Limits Report, Revision 1
| ML19058A247 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/27/2019 |
| From: | Cimorelli K Susquehanna, Talen Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-7765 | |
| Download: ML19058A247 (64) | |
Text
{{#Wiki_filter:Kevin Cimorelli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 TALEN~ FEB 2 7 2019 Tel. 570.542.3795 Fax 570.542.1504 ENERGY Kevin.Cimorelli@TalenEnergy.com U.S. Nuclear Regulatory Commission 10 CFR 50.4 Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION SUBMITTAL OF UNIT 2 CYCLE 19 CORE OPERATING LIMITS REPORT, REVISION 1 PLA-7765 Docket No. 50-388 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 Nuclear Regulatory Commission in accordance with 10 CFR 50.4. In compliance with this requirement, the Unit 2 Cycle 19 COLR, Revision 1 is provided in the attachment. This revision is a result of the Unit 2 Cycle 19 Core being projected to achieve greater core average exposure than what was initially assumed to analyze Unit 2 Cycle 19. The updated licensing analysis results, at a core average exposure which bounds the remaining cycle operations, only affect the power-dependent, equipment out-of-service Linear Heat Generation Rate (LHGR) multipliers. A complete record of revision is included in the attachment. There are no new or revised regulatory commitments contained in this submittal. If you have any questions regarding this report, please contact Mr. Jason Jennings, Manager- Nuclear Regulatory Affairs, at (570) 542-3155. 722--- Kevin Cimorelli
Attachment:
Unit 2 Cycle 19 COLR, Revision 1 Copy: NRC Region I Ms. J. Tobin, NRC Project Manager Ms. L. H. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, PA DEP/BRP
Attachment to PLA-7765 Unit 2 Cycle 19 COLR, Revision 1
Rev. 14 PL-NF-17-001 Rev. 1 Page 1 of 62 Susquehanna SES Unit 2 Cycle 19 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering February 2019 SUSQUEHANNA UNIT 2 3.2-2
Rev. 14 PL-NF-17-001 Rev. 1 Page 2 of 62 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 19 operation. 1 6.0 Figures 6.2-2 through 6.2-4 (editorial) and 6.2-5 (technical) are revised to account for the cycle achieving a greater core average exposure than what was assumed to initially analyze Unit 2 Cycle 19 (U2C19). Updated U2C19 licensing analysis results (Framatome, formerly AREVA, report ANP-3536, Rev. 3) at a bounding core average exposure only affect the power-dependent, equipment out-of-service Linear Heat Generation Rate (LHGR) multipliers. On pages 27, 29, and 32, text supporting these Figures is also updated. ALL Removed page count prefix TRM/ and Effective Date from footer to align formatting with the new process. FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 3.2-3
Rev. 14 PL-NF-17-001 Rev. 1 Page 3 of 62 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 19 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) ............................................................. 27 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS........................................................................................................ 38 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION ......................................... 40 9.0 POWER / FLOW MAP ................................................................................................ 58 10.0 OPRM SETPOINTS .................................................................................................... 60
11.0 REFERENCES
............................................................................................................ 61 SUSQUEHANNA UNIT 2 3.2-4
Rev. 14 PL-NF-17-001 Rev. 1 Page 4 of 62
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 19 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. SUSQUEHANNA UNIT 2 3.2-5
Rev. 14 PL-NF-17-001 Rev. 1 Page 5 of 62 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. SUSQUEHANNA UNIT 2 3.2-6
Rev. 14 PL-NF-17-001 Rev. 1 Page 6 of 62 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference 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. SUSQUEHANNA UNIT 2 3.2-7
Rev. 14 PL-NF-17-001 Rev. 1 Page 7 of 62 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference 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 for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Two Loop operation. The APLHGR limits for Single Loop operation are provided in Section 8.0. SUSQUEHANNA UNIT 2 3.2-8
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 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) 3.2-9 Rev. 14 8.0 67000, 6.9 6.0 4.0 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU) PL-NF-17-001 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION Rev. 1 ATRIUMTM-10 FUEL Page 8 of 62 FIGURE 4.2-1
Rev. 14 PL-NF-17-001 Rev. 1 Page 9 of 62 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 Technical Specification Reference Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 5.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 5.3 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 SUSQUEHANNA UNIT 2 3.2-10
Rev. 14 PL-NF-17-001 Rev. 1 Page 10 of 62 The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop operation. The MCPR limits for Single Loop operation are provided in Section 8.0. 5.4 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. SUSQUEHANNA UNIT 2 3.2-11
Rev. 14 PL-NF-17-001 Rev. 1 Page 11 of 62 Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 3.2-12
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 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 3.2-13 1.6 Rev. 14 30, 1.54 1.5 A B 1.4
REFERENCE:
T.S. 3.2.2 1.3 108, 1.21 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 1 TWO LOOP OPERATION (BOC TO EOC) Page 12 of 62 FIGURE 5.2-1
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 3.6 3.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.2 23, 3.09 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 26, 2.95 23, 3.04 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 2.8 26, 2.84 MCPR Operating Limit 2.6 C SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.4 Rev. 14 USED IN DETERMINING MFLCPR 3.2-14 2.2 26.01, 1.99 2.0 1.8 40, 1.70 26.01, 1.89 A 1.6 40, 1.62 80, 1.44 94.46, 1.37 B 1.4
REFERENCE:
T.S. 3.2.2 100, 1.35 80, 1.41 85, 1.39 94.46, 1.34 100, 1.32 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 1 TWO LOOP OPERATION (BOC TO EOC) Page 13 of 62 FIGURE 5.2-2
Rev. 14 PL-NF-17-001 Rev. 1 Page 14 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 3.2-15
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 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 1.8 30, 1.74 1.7 3.2-16 Rev. 14 A 1.6 B 1.5 108, 1.36 1.4
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-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE Rev. 1 TWO LOOP OPERATION (BOC TO EOC) Page 15 of 62 FIGURE 5.2-3
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 3.6 23, 3.43 3.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 INSERTION TIME 23, 3.04 26, 3.15 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 C CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 26, 2.84 2.8 MCPR Operating Limit 2.6 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.4 3.2-17 2.2 USED IN DETERMINING MFLCPR Rev. 14 26.01, 2.03 2.0 1.8 40, 1.74 A B 80, 1.54 1.6 100, 1.54
REFERENCE:
T.S. 3.7.6 and 3.2.2 1.4 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE Rev. 1 TWO LOOP OPERATION (BOC to EOC) Page 16 of 62 FIGURE 5.2-4
Rev. 14 PL-NF-17-001 Rev. 1 Page 17 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 2 3.2-18
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 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 3.2-19 1.6 Rev. 14 30, 1.54 1.5 A B 1.4
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 1.3 108, 1.21 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE Rev. 1 TWO LOOP OPERATION (BOC TO EOC) Page 18 of 62 FIGURE 5.2-5
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 3.6 LEGEND 3.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 INSERTION TIME 23, 3.09 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 23, 3.04 26, 2.95 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 2.8 26, 2.84 C 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 3.2-20 2.2 Rev. 14 26.01, 1.99 2.0 40, 1.70 1.8 A B 1.6 80, 1.44
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 94.46, 1.43 100, 1.43 1.4 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE Rev. 1 TWO LOOP OPERATION (BOC to EOC) Page 19 of 62 FIGURE 5.2-6
Rev. 14 PL-NF-17-001 Rev. 1 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 3.2-21
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 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 3.2-22 1.6 Rev. 14 30, 1.54 1.5 A B 1.4
REFERENCE:
T.S. 3.7.8 and 3.2.2 1.3 108, 1.21 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE Rev. 1 TWO LOOP OPERATION (BOC TO EOC) Page 21 of 62 FIGURE 5.2-7
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 3.6 3.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 INSERTION TIME 23, 3.09 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 26, 2.95 23, 3.04 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 2.8 26, 2.84 MCPR Operating Limit C 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, 2.30 USED IN DETERMINING MFLCPR Rev. 14 40, 2.08 3.2-23 2.2 A 2.0 B 1.8 1.6 80, 1.46
REFERENCE:
T.S. 3.7.8 and 3.2.2 94.46, 1.37 1.4 100, 1.35 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE Rev. 1 TWO LOOP OPERATION (BOC to EOC) Page 22 of 62 FIGURE 5.2-8
Rev. 14 PL-NF-17-001 Rev. 1 Page 23 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 2 3.2-24
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 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 30, 1.74 USED IN DETERMINING MFLCPR 1.7 3.2-25 1.6 A Rev. 14 B 1.5 108, 1.37 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-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* Rev. 1 TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-9 Page 24 of 62
*Operation with one TSV or TCV closed is only supported at power levels 75% rated power
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 3.6 3.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.2 23, 3.09 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 26, 2.95 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 23, 3.04 2.8 26, 2.84 C 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 Rev. 14 USED IN DETERMINING MFLCPR 3.2-26 2.2 26.01, 1.99 2.0 1.8 40, 1.70 26.01, 1.89 A 1.6 75, 1.47 40, 1.62 B 1.4
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 75, 1.43 1.2 20 30 40 50 60 70 80 Core Power (% RATED) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED* Rev. 1 TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-10 Page 25 of 62
*Operation with one TSV or TCV closed is only supported at power levels 75% rated power
Rev. 14 PL-NF-17-001 Rev. 1 Page 26 of 62 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 SUSQUEHANNA UNIT 2 3.2-27
Rev. 14 PL-NF-17-001 Rev. 1 Page 27 of 62 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 6.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 6.3 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 or EOC-RPT or Backup Pressure Regulator Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: Power-Dependent LHGR Limit Multiplier The LHGR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation. SUSQUEHANNA UNIT 2 3.2-28
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 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 3.2-29 Rev. 14 8.0 74400, 7.1 6.0 4.0 0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWD/MTU) PL-NF-17-001 LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE Rev. 1 ATRIUMTM-10 FUEL FIGURE 6.2-1 Page 28 of 62
Rev. 14 PL-NF-17-001 Rev. 1 Page 29 of 62 Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 3.2-30
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1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I c I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.60 I I I I I I I I I I I I I I -1
--------~--------~-------~-------~-------~-------~--------~--------~--------~--------~--------~--------~--------~--------+--------*--------
1 I I I I I I I I I I I I I -1
~ I I I I I I I I I I I I I I I 0 I I
I I I I 1 I I I I I I I I I I I I I I I I I I I I I I I ii: I I I I I I I I I I I I I I I
--------r--------r-------~-------~-------~-------1--------1--------1--------~--------~--------7--------7--------7--------t~------~t--------
I :I :I : I : I : I :I : I : I : I : I ~ 1:EFE ~I - . 1: .
* :* ' ~
R RENCE: T~S. 3.2.3 - I I I I I I I I I I I 0.50 --*------l--------..:.-*------+-------+-------+-----:..:...:--------.:--------~--------"'~--------~---------~---
- I :I :I :I :I :I :I :I :I :
I l r I I I I I I I I I I I -- . il~~::::r:::::::JC:::::::r::::::::c:::::~ I I I I I r I I I I f'
- I I I I
--------:--------:-------:-------:-------:-------~-------,_-------:--------;--------;-------- USED IN DETERMINING FDLRX -
I I I I I I I I I I . . o~4o -------~--------~-------~-------~-------~-------~------r-l~________L*_______j~~------l~~----_Jc:::::::J::::::::r:::::::J::::::::r:::::~ I I I I I I I I I I I I I I I I I I I I I I I I SAFETY ANALYSESASSUME THAT FOUR BYPASS VALVES 1- 1- I I I
--------r--------r-------~-------~~-------~-------~-----
1 I I I f I I ARE OPERABLE PER SR 3.7~6~1 AND 3.7 ~6;2 I I I I I I I I I I I I I I I I I I I 0.30 ;.------_.*-------t'------~~-------f------~*------~~r-----~~------r-------~------t-------~------t-------~------;-------~'-------; 1 1
"'"0:::0"'"0
'30 40 50 60 70 80 90 100 110 mcor C0 < I CD
- Z Total Core Flow (MLB/hr) w_,_'Jl 0 _,_
0 ........ FLOW DEPENDENT LHGR LIMIT MULTIPLIER ...... 0 I MAIN TURBINE BYPASS I EOC~RPT/ BACKUP PRESSURE REGULATOR OPERABLE Q) N 0 A TRIUM'-"1 0 FUEL FIGURE 6.2-2
SSES UNIT 2 CYCLE 19 (f) 1.10 c I I
-----r-------:--------r-------n 94.46, 1.oo 1 I I (f)
LEGEND I I I I I I I I I r--------,j 0 c m I I I I . . CURVE A: BASE CURVE I I I I I I I I I I I 1.00 -----:--------:--------:--------:-----~-~::--;:::::L___, )>
--.--J-----{--------{------ : -------t--------f--~--=-=::__::::_r---_,
I I I I z L..c_u_R_V'T"E_B_:_c_o'T__
"RE P_OT"WE__R_*;5;_**T"2_6_%_o_A_N.,.D_c_o_R'T"E_F_L_o_Wrr-;5;-S_o_Mrr-L_B_MI_HT"R__
z )> 'I I
*1 I
I I I I I I c I I I I I I I I 0.90 -------*--------*--------+--------+-------- I I I I I I I I I I I I I I I z I-
--------~--------~-------~-------~-------~-------~--------~--------~--------~--------~-------
1 I I I I I I I I I I I I I I I
- A I
I I I I i I I I I I I I -I .!!! ------:i--------7---------t--------t--------t--------t-------- I
- c. --------~-----;...--~-------+-------+-------+-------~--------~--------~---*----
I l I I I I I I I I I I I I I
- I I I I I I I I I I I I I "S
I I I I I I I I I I I I I
- a: ------...;---}---*------}--------+------;;,.-+-*------+-------i--------
I I I I I I I I I I I I I I 0.80 1 I I I I I I I
------i--------i--------~--------i--------i--------i--------+--------+--------
I I I I I I I I 0::: I I I I I I I I I I I I I I I I I I I I I I I I I I I I I (!) I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I J: --------~--------~-------~-------~------- 1 I I I -----~--------~--------~--------~--------~--------*--------*--------*--------+--------+-------- I I 1- I I I I I I I
...I I I
I I I I I I I I I I I I I I I I I I I I I I I I I cCl): I I I I I I I I I I I I I
--------r--------r-------
I I I I I I I I I I I I I I I "C 0.70
- I
-----~-------~-------~--------1--------i--------i--------i--------~--------~--------~--------+--------+--------
I I I I I I' I I I I I I c: I I I I I I I I 'I I I I I I
--------r -----*r-------r-------r-------l--------,--------,--------;--------1--------1--------1--------t--------t--------
I I I I I I I I I I I I I Cl) I I I I I I I I I I *1 I I I 1 c. 12s~:o1, o.s5~ ,-.
-----+-------+-------+-------+-------+-------+------+------+------+------+---I
REFERENCE:
T.S. I Cl) c l . . . . I I I I I -* 'I I I I I I I- I I I I I I ,. I I Cl)
- 0.60 1 I I I I I I I I I I 3.2.3 ----
0 I I I I I I I I I I I I I I I L--------L: ------- _r_: --------L..: -------.J:--------..J--------.l--------:.J.;. _______ - Q.; I I I I I I I I I I
--------L I I I I I I I I I I FDLRX
;J ___
USED IN DETERMINING 126, ?.so lj______ j ______ j _______ j___
------~ I I I I I I I I I I I I I I I I I I I I 0:.50 I t I I I SAFElY ANALYSES ASSUME THAT FOUR BYPASS VALVES I I I I I I I I I I I I I I I ARE OPERABLE PERSR 3.7.6;1 AND*3.7.6.2 I I I 1 I
------~-------~-------~-------~-------~---
!26. 0.431 1 I I I I 1 ~ ~ ~ ~ I I I I I I I I I OAO --r--------F-------~-------~-------~-------~-------1--------i--------i--------i--------~--------~--------~--------+--------+--------
.I
- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
-I23, o.40----r-------+-------+-------+-------i--------~f*---..:.. . ..:. _,_______..:..l--------1--------1--------1--------*i--------+--------+--------
,----':---, I I I I I I I *t *1 I I I I I I I* I I I I I I' I I I *I I I
, I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.30 20 30 40 50 60 70 80 90 *100 Core Power (% RATED)
POWER DEPENDENT LHGR LIMIT MULTIPLIER 0 -...! I 0 MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE ( j) 0 N A TRIUM'-1 0 FUEL ....>. FIGURE 6.2-3
Rev. 14 PL-NF-17-001 Rev. 1 Page 32 of 62 Main Turbine Bypass or EOC-RPT or Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 3.2-33
SSES UNIT 2 CYCLE 19 C/) 1.10 c I I I C/) I I I I I I I I' I I I I I I I I I I I I I I I 0 --------~--------~-------~-------~-------~--------~--------~--------~--------~--------~--------~--------+--------+--------*--------~--------
*r c
1 I I I I I I I I I 1 I I I ________L________L _______ JL _______JL _______ j ________ j ________ j________ j ________ j ________ j ________ j ________1______100 1 00 I I I I I I I I I I I I I m 1 1 I I I I I f I I I I I I
~_1_::~:__~ ~
I '1.00 I I I I I I I I I I* I I I I
- I
)> i i i i ! i i : i ! ! ! : : 1os,-1 ;oo I I I I I I I I I I I I 1- I z z --------~-------~-------~-------~-------~--------i--------i--------~--------~--------~--------i-------- -----f--------f--------~-------- 1 1 I I I I I I I I I I I I I )> I I I I I I I I I I I I I I I I I I I I I I I I I I I I c I I I I I I I I I I I I I 0.90 I I I I I I I I I I I I I I I z --------~--------~-------~-------~------~--------~--------~--------~--------~--------~--- 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --~--------~--------*--------*--------~-------- I I I I I I I I I I I I I I I I I I I I -I I I I I I I I I I I I I I I N --------~--------~-------~-------~-------~--------~--------~--------~----- l I I I I I I I
~--------1--------1--------1--------+--------t--------t--------
I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.80 --------~-------~-------~-------~-------~--------~------- l I I I I I -------4~-------4--------4--------1--------1--------+--------+--------t-------- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I
--------~--------~-------~-------~-------~-
1 I .1 I ----~--------~--------~--------~--------~~-------~--------~--------*--------*--------~-------- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I I I I I I I I 0.70 -------+--------:---------+-- l I
--+-------~---------:--------~--------~---------t---------t---------t*--------1--------t--------t-:.-------t--------
I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
-------~----
1 -r-------~r-------~-------~--------~--------~--------~--------~--------~--------~--------~--------+--------+--------t-------- I I I I I I 0.60 ______ J~ -------,.~-------+-------+-------J-------~--------~-------1
REFERENCE:
T~s. I I I I I I I I I I 3.2~3, 3.3:.4.1, 3].6 and 3.7.8 1-- 130, 0.60 I .: : : : : : : : : ~ ~
--------:--------+-------+-------+--------1--------~--------~--------~--------~--------i------- USED IN DETERMINING FDLRX --
1 I I I I I I I I I I 1 I I I I I rl'I ________I'L_______ j'I ________l' I _______Jc:::::::J::::::::r:::::::J::::::::r:::~ I I I I I I I 0.50 I -1 I I I
--------r--------r-------~r-------~r-------~--------~-------
1 I I I I I I FOR MAIN TURBINE BYPASS INOPERABLE, SAFETY I I I I I I I I I I I I I I I I I I I I I I I I ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES
--------~--------~-------~-------~-------~-------~-------
1 I I I I I I I I I I I ARE INOPERABLE PERSR3.7.6.1 OR3.7.6.2 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.40 --------~--------~-------~-------~-------~---------:--------~--------~--------~--------7--------7--------t--------t--------t--------t-------- l I I I I I I I I I I I I I I
-1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
-1 -1 I I I I I I I I I I I I I
--------r--------r-------~r-------~r-------~--------,--------,--------,--------,--------~--------~--------T--------T--------T--------r--------
1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.30 I I 1 I I I I I I I I 1 I I I
-o;;u-o 30 40 50 60 70 80 90 100 OlCDI
<C<'
Total Core Flow {MLB/HR) CD" Z w--'-71 w -->.. FLOW DEPENDENT LHGR LIMIT MULTIPLIER 0 --.! I MAIN TURBINE BYPASS:OR EOC-RPTOR BACKUP PRESSURE REGULATOR INOPERABLE 0
- 0) 0 A TRIUM'~1 0 FUEL N FIGURE 6~2-4
SSES UNIT 2 CYCLE 19 (/) 1.10 c I I I (/) LEGEND
-----1--------1--------1--------r--------r-11oo 1.00 I I I I I I I I I I I 0
c _____L______L_____ j 94.46, 1.oo L.~:!----1 I I I I I 1.._._ _,_7, - - - - ' m 1.00 CURVE A: BASE CURVE I I I I I I I I I 7'"1 I )> I I I I I z I I I I I CURVE B: CORE POWER ~26% AND CORE FLOW ~50 MLBMIHR
-----{--------{--------{--------+-
I I I I I z L----,----.----.----.----.----.----,,----,,----~---~~ : : : :
---~-+-~-*-----
)> I I I I c I I I I I I I I I z o~go --------r--------r-------~-------~-------~-------~--------1--------~--------~--------~--------1--------1--------1----- -+--------+--------
- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
-i I I I I I I I I I I I I I I I
. . ._____.,.~. ------t------*-*--t--------
I I I I I I I I I I I I I I 1
--------r--------r-------+-------+-------+-------"1---------1--------1-----------~---*-----1---*------t-*--------t----
, I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.8.0 I I I I I I I I I
____;..;,,;i-----, I I I I* __ _;. ___ +-------- I
-------_;;~--------~-------+-------+-------+-------~--------i--------i-------;,.,;i-*_;.
1 1 1 lao I 0
- 75
~-*..;. __ ,
11
~-..;.--;..;..;..*_-_;._+_;_,
i i ! i ! I I I I I I I I I I
~ ~ ~ ~ ~ ~ I' *. ~ ~ ~
--------r--------r-------~-------~-------~-------1--------1--------1---- ~**1--------1--------~-----
1 I I I I I I I I I I -------1--------+--------t-------- I I I I I I I I I I I I I I I
-1 I I I I I I I I I I I I 0.70 --------~--------~-------+-------+-------+-------J__
1 I I I
- --------~--------~--------~--------i--------t--------t--------t*--------t--------
I I I J I I I I I
*1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I w --------~ 12s~o:j~-o~6!>::--------r--------r-------~--------~--------l--------l--------l--------1--------1--------1--------~--------~--------
NI ~ ~ o.so
* . I I I I I I I I I I I I w --------r -----~r-------~-------1r-------1r-------1--------1--------1--------1--------1--------1--------1--------1--------+--------t--------
l I I I I I I I I I I I I I I 01 I I I I I I I I I I I I I I I I I I 1 I t I I I I I I I I I o.5o 2 --------'" l2s, ~.so L.J-_______.J-_______.J-____ ~ 1 ;~-~~~~i -----+------t-------t-------t-------1--------!--------~~
REFERENCE:
T~S. 3.2.31 3~3.4.1,. 3.7.6, and 3.7.8
~
_c __ ________ ________ ... ~_ _-_-_-_-_-_-_;~--------_-_-_-_;~r-_-_-__-_-;:=:~c::::===c::::===c:===c:===c:==. _/. I I I I I I I I I 8 r*i i i USED. IN DETERMINING FDLRX I I I I I I I I I I
--------~ j2s~-?~43j--r-------r-------r-----;:-:-:t~-:~:-~:-:~:--:~t~~:--:l~:--:~:-1~-:~:~:-;:~:~:-"':t~~:-yp:--:-:~:~::l~t~:~:~:-O=:PIE=RA==B=L:::J.c:E=,=S=A=.=FIE=TY==A=NA::c:=L=Y=S=EIS=~
-+--------:--------+-------+-------+----
J______J_______ J_______,--------,--------,-- ------~:~-~-~,~~~~~=~~~~::~:~~~----~--------T--------T-------- 0.40 ASSUME THATlWO OR MORE BYPASS VALVES ARE INOPERABLE
-' 23,. d.40 j__
1 I I I I I l______ I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.30 I I I I I I I I I I I I I I I 20 30 40 50 60 70 80 90 100 Core Power (% RATED) POWER DEPENDENT LHGRLIMIT MULTIPLIER MAIN TURBINE BYPASS OR EOC-RPT.OR BACKUP PRESSURE REGULATOR INOPERABLE A TRIUMTM*1 0 FUEL FIGURE 62*5
Rev. 14 PL-NF-17-001 Rev. 1 Page 35 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 2 3.2-36
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 1.10 1.00 108, 0.94 0.90 Flow Dependent LHGR Multiplier 0.80 0.70 3.2-37 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES Rev. 14 0.60 ARE OPERABLE PER SR 3.7.6.1 OR 3.7.6.2 30, 0.55
REFERENCE:
REFERENCE:
T.S. T.S. 3.2.3 3.2.3 andand TRM3.7.6 3.3.7 0.50 USED IN DETERMINING FDLRX 0.40 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-17-001 FLOW DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED* Rev. 1 ATRIUMTM-10 FUEL FIGURE 6.2-6 Page 36 of 62
*Operation with one TSV or TCV closed is only supported at power levels 75% rated power
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 1.10 LEGEND CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 75.00, 0.90 0.90 Power Dependent LHGR Multiplier A 0.80 0.70 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES Rev. 14 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2-38 26.01, 0.65 0.60
REFERENCE:
T.S. 3.2.3 and TRM 3.3.7 USED IN DETERMINING FDLRX B 26, 0.50 0.50 23, 0.47 26, 0.43 0.40 23, 0.40 0.30 20 30 40 50 60 70 80 Core Power (% RATED) PL-NF-17-001 POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED* Rev. 1 ATRIUMTM-10 FUEL FIGURE 6.2-7 Page 37 of 62
*Operation with one TSV or TCV closed is only supported at power levels 75% rated power
Rev. 14 PL-NF-17-001 Rev. 1 Page 38 of 62 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 Technical Specification Reference 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, and Backup Pressure Regulator Operable and Inoperable. 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. SUSQUEHANNA UNIT 2 3.2-39
Rev. 14 PL-NF-17-001 Rev. 1 Page 39 of 62 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, and Backup Pressure Regulator Operable and Inoperable. (3) Applicable to both Two Loop and Single Loop Operation. SUSQUEHANNA UNIT 2 3.2-40
Rev. 14 PL-NF-17-001 Rev. 1 Page 40 of 62 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 8.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 8.3 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 for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Single Loop operation. 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 SUSQUEHANNA UNIT 2 3.2-41
Rev. 14 PL-NF-17-001 Rev. 1 Page 41 of 62 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 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. SUSQUEHANNA UNIT 2 3.2-42
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 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) 3.2-43 Rev. 14 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-17-001 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - SINGLE LOOP OPERATION Rev. 1 ATRIUMTM-10 FUEL Page 42 of 62 FIGURE 8.2-1
Rev. 14 PL-NF-17-001 Rev. 1 Page 43 of 62 Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 3.2-44
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 3.6 LEGEND 3.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.2 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 2.8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES MCPR Operating Limit ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.6 USED IN DETERMINING MFLCPR Rev. 14 2.4 3.2-45 2.2 2.0 30, 1.87 1.8 A B 1.6 108, 1.48
REFERENCE:
T.S. 3.4.1 and 3.2.2 1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Rev. 1 SINGLE LOOP OPERATION (BOC to EOC) Page 44 of 62 FIGURE 8.2-2
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 4.6 4.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 23, 3.71 3.8 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.6 26, 3.55 23, 3.65 MCPR Operating Limit 3.4 26, 3.42 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES C ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 3.0 USED IN DETERMINING MFLCPR 3.2-46 Rev. 14 2.8 2.6 26.01, 2.40 2.4 2.2 40, 2.06 A B 60, 1.90 2.0 100, 1.90 1.8
REFERENCE:
T.S. 3.4.1 and 3.2.2 1.6 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER PL-NF-17-001 Rev. 1 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) Page 45 of 62 FIGURE 8.2-3
Rev. 14 PL-NF-17-001 Rev. 1 Page 46 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 3.2-47
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 4.2 LEGEND 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.8 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.6 3.4 3.2 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 3.0 USED IN DETERMINING MFLCPR 2.8 3.2-48 Rev. 14 2.6 2.4 30, 2.11 2.2 2.0 A B 1.8 108, 1.65
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1.6 1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Rev. 1 MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) Page 47 of 62 FIGURE 8.2-4
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 4.4 LEGEND 4.2 23, 4.12 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 C 26, 3.78 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 23, 3.65 3.6 MCPR Operating Limit 3.4 26, 3.42 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 3.2 USED IN DETERMINING MFLCPR Rev. 14 3.0 3.2-49 2.8 2.6 26.01, 2.45 2.4 40, 2.11 2.2 60, 1.96 A B 100, 1.96 2.0
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1.8 20 30 40 50 60 70 80 90 100 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER PL-NF-17-001 Rev. 1 MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) Page 48 of 62 FIGURE 8.2-5
Rev. 14 PL-NF-17-001 Rev. 1 Page 49 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 2 3.2-50
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 3.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES MCPR Operating Limit 3.0 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 USED IN DETERMINING MFLCPR Rev. 14 2.6 3.2-51 2.4 2.2 2.0 30, 1.87 1.8 A B 1.6
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 108, 1.48 1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE Rev. 1 SINGLE LOOP OPERATION (BOC to EOC) Page 50 of 62 FIGURE 8.2-6
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 4.6 4.4 LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 23, 3.71 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.6 26, 3.55 23, 3.65 MCPR Operating Limit 3.4 26, 3.42 C SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.0 Rev. 14 USED IN DETERMINING MFLCPR 3.2-52 2.8 2.6 26.01, 2.40 2.4 2.2 40, 2.06 A B 100, 1.90 2.0 60, 1.90 1.8
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.6 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER PL-NF-17-001 Rev. 1 EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) Page 51 of 62 FIGURE 8.2-7
Rev. 14 PL-NF-17-001 Rev. 1 Page 52 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 3.2-53
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 4.0 3.8 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 3.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 MCPR Operating Limit 3.0 USED IN DETERMINING MFLCPR 2.8 Rev. 14 2.6 3.2-54 2.4 2.2 2.0 30, 1.87 1.8 A B
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 108, 1.48 1.6 1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE Rev. 1 SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-8 Page 53 of 62
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 4.6 4.4 LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 23, 3.71 3.8 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.6 26, 3.55 23, 3.65 3.4 26, 3.42 C SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.0 MCPR Operating Limit Rev. 14 26.01, 2.77 USED IN DETERMINING MFLCPR 3.2-55 2.8 40, 2.51 A 2.6 B 2.4 60, 2.14 100, 2.14 2.2 2.0 1.8
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) MCPR OPERATING LIMIT VERSUS CORE POWER PL-NF-17-001 Rev. 1 BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) Page 54 of 62 FIGURE 8.2-9
Rev. 14 PL-NF-17-001 Rev. 1 Page 55 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 2 3.2-56
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 4.0 3.8 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 3.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 MCPR Operating Limit 3.0 USED IN DETERMINING MFLCPR 2.8 Rev. 14 2.6 3.2-57 2.4 2.2 30, 2.11 2.0 A B 1.8 108, 1.67
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 1.6 1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* Rev. 1 SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-10 Page 56 of 62
*Operation with one TSV or TCV closed is only supported at power levels 75% rated power
SSES UNIT 2 CYCLE 19 SUSQUEHANNA UNIT 2 4.6 4.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 23, 3.71 CURVE C: CORE POWER 26% AND CORE FLOW 50 MLBM/HR 3.6 26, 3.55 23, 3.65 MCPR Operating Limit 3.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 26, 3.42 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C 3.2 3.0 USED IN DETERMINING MFLCPR 3.2-58 Rev. 14 2.8 2.6 26.01, 2.40 2.4 2.2 40, 2.06 A B 2.0 60, 1.90 75, 1.90 1.8
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 1.6 1.4 20 30 40 50 60 70 80 Core Power (% RATED) PL-NF-17-001 MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED* Rev. 1 SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-11 Page 57 of 62
*Operation with one TSV or TCV closed is only supported at power levels 75% rated power
Rev. 14 PL-NF-17-001 Rev. 1 Page 58 of 62 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference 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. SUSQUEHANNA UNIT 2 3.2-59
Rev. 14 PL-NF-17-001 Rev. 1 Page 59 of 62 120 :r~~~~~~=cCCLI~~~~~~=r-r-rT-T-~l=~r=====jj~~;=====l+120 purpos(:l: UNIT 2 110 Initial/ Date: 110 100 100 90
~ ~
a. iU
....E Q) .s:
1-40 30 Approx One Pump 10 -H-f--H-+-+-++-H--'k-1~-hf-1-+-+-11-l-+-H 80% Speed. H-H-+-l-f--H-l-+-+-1-H--Hf-++-1-l-+-+-+-+-+- 10 0 ~-F-H-1-~-l-H-+-l~+-+-+-+-++-l-++-'++'+-!-+-+-+-+-+-++-H--H-f--H-l-+-+-l-l-+~-f--H-l-+ 0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core l=low (Mibm/hr) (for SLO <75% Pump Speed Us~ Form G0-200-009-2) Figure 9.1 SSES Unit 2 Cycle 19 Power I Flow Map SUSQUEHANNA UNIT 2 3.2-60
Rev. 14 PL-NF-17-001 Rev. 1 Page 60 of 62 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference 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 SUSQUEHANNA UNIT 2 3.2-61
Rev. 14 PL-NF-17-001 Rev. 1 Page 61 of 62
11.0 REFERENCES
11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.
- 2. EMF-2361(P)(A), Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP, May 2001.
- 3. EMF-2292(P)(A), Revision 0, ATRIUM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.
- 4. XN-NF-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).
SUSQUEHANNA UNIT 2 3.2-62
Rev. 14 PL-NF-17-001 Rev. 1 Page 62 of 62
- 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.
- 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.
- 19. ANF-1358(P)(A), Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Framatome ANP, September 2005.
SUSQUEHANNA UNIT 2 3.2-63}}