ML15308A500
| ML15308A500 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna |
| Issue date: | 09/30/2015 |
| From: | Talen Energy |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML15308A498 | List: |
| References | |
| PLA-7396 PL-NF-15-002, Rev. 1 | |
| Download: ML15308A500 (63) | |
Text
{{#Wiki_filter:Attachment 2 to PLA-7396 Revised Unit 2 Cycle 18 COLR
Rev. 12 Susquehanna SES Unit 2 Cycle 18 PL-NF-15-002 Rev. 1 Page 1 of 62 CORE OPERATING LIMITS REPORT SUSQUEHANNA UNIT 2 TRM/3.2-2 Nuclear Fuels Engineering September 2015 EFFECTIVE DATE 11/04/2015
Rev. Affected No. Sections 0 ALL 1 ALL Rev. 12 PL-NF-15-002 Rev. 1 Page 2 of 62 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Description/Purpose of Revision Issuance of this COLR is in support of Unit 2 Cycle 18 operation. New COLR for the inclusion of operating limits regarding a Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closure event. This revision also changes the Turbine Bypass Inoperable MCPRt limits that were updated in the licensing analysis to remove conservatisms from the initial analysis that are not required per the NRC approved methodology. FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 TRM/3.2-3 EFFECTIVE DATE 11/04/2015
Rev. 12 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 18 CORE OPERATING LIMITS REPORT Table of Contents PL-NF-15-002 Rev. 1 Page 3 of 62
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 I FLOW MAP................................................................................................ 58 10.0 OPRM SETPOINTS.................................................................................................... 60
11.0 REFERENCES
............................................................................................................ 61 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 11/04/2015
Rev. 12
1.0 INTRODUCTION
PL-NF-15-002 Rev. 1 Page 4 of 62 This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 18 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 TRM/3.2-5 EFFECTIVE DATE 11/04/2015
Rev. 12 2.0 DEFINITIONS PL-NF-15-002 Rev. 1 Page 5 of 62 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 MAP RAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR 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 I hr, below which the OPRM RPS trip is activated. SUSQUEHANNA UNIT 2 TRM/3.2-6 EFFECTIVE DATE 11/04/2015
Rev. 12 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 b) 0.28% ~klk with the highest worth rod determined by test PL-NF-15-002 Rev. 1 Page 6 of 62 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 TRM/3.2-7 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 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 ATRIUM'-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 TRM/3.2-8 EFFECTIVE DATE 11/04/2015
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Rev. 12 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 Technical Specification Reference PL-NF-15-002 Rev. 1 Page 9 of 62 Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 5.2 Technical Requirements Manual Reference Technical Requirements Manual3.3.7 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 (ATRIUM '-1 0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. a) Main Turbine Bypass I EOC-RPT I 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 TRM/3.2-10 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 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 TRM/3.2-11 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 Rev. 1 Page 11 of 62 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 EFFECTIVE DATE 11/04/2015
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REFERENCE:
T.S. 3.2.2 ~ ~ 1108, 1.211 30 40 ~ 50 60 70 80 90 100 Total Core Flow (MLBIHR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-1 110
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REFERENCE:
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Rev. 12 Main Turbine Bypass Inoperable PL-NF-15-002 Rev. 1 Page 14 of 62 SUSQUEHANNA UNIT 2 TRM/3.2-15 EFFECTIVE DATE 11/04/2015
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REFERENCE:
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REFERENCE:
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SUSQUEHANNA UNIT 2 Rev. 12 EOC-RPT Inoperable TRM/3.2-18 PL-NF-15-002 Rev. 1 Page 17 of 62 EFFECTIVE DATE 11/04/2015
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1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 18 LEGEND I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM f-- INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME f-- I I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES r-- ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR ~ 30, 1.57 ~ -......... ~ A B ~ I
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 I ~ 30 40 50 ~ 1108, 1.211 ~ 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-5
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2.0 1.8 1.6 1.4 1.2 --123, 3.40 \\ \\ 126, 3.161 ,...- c r-1 26.01, 2.00 1 140,1.721 SSES UNIT 2 CYCLE 18 I I I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR I I I I l SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR A -s
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REFERENCE:
T.S. 3.3.4.1 and 3.2.21 180,1.441 -J 1194.46, 1.38 r 1100,1.381 I 20 30 40 50 60 70 80 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-6 90 100 lJ lJ Ill r (Q I <D z 71 CO ;:a-" oro'f -<o en
- o N-"N
Rev. 12 PL-NF-15-002 Rev. 1 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-21 EFFECTIVE DATE 11/04/2015
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(1:1... 1.7 Q) c. 0 0::: c.. (.) 1.6 2 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 18 I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR J 30, 1.571 ~ ............... ~ A B [!
REFERENCE:
T.S. 3.7.8 and 3.2.21 ~ 30 40 50 ~ 1108, 1.211 ~I 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-7 100 110
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I H23, 3.4o LEGEND \\ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM \\ 126, 3.161 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR r-c SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 126.01' 2.331 USED IN DETERMINING MFLCPR r---........ t40, 2.10j A B -.............. -~ I so 1 441
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REFERENCE:
T.S. 3.7.8 and 3.2.21 194.46, 1.37 ~ ~ I 20 30 I 40 50 60 70 80 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-8 90 1100, 1.351 100 ""'0 ""'0 w r (Q I CD z N "Jl N;:u-'" oCD'f -<a (J') 0 N-'"N
Rev. 12 PL-NF-15-002 Rev. 1 Page 23 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM/3.2-24 EFFECTIVE DATE 11/04/2015
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REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 I 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-9
- Operation with one TSV or TCV closed is only supported at power levels ~ 75% rated power.
100 110
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\\. LEGEND \\. 126, 3.161 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR -c I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE - PER SR 3.7.6.1 AND 3.7.6.2 r-I I I USED IN DETERMINING MFLCPR ~ 126.01, 2.oo 1 ............... r----:---- -.._. 140,1.721 l26.o1, 1.91 1 --....::.:::.:: ~ ~.L ---A ---------- 40, 1.69 1 1 75, 1.48 r t 8 n_
REFERENCE:
T.S. 3.2.2 and TRM 3.3.71 20 30 40 50 60 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-10 65, 1.50 175,1.441 70 80
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Rev. 12 Table 5.3-1 PL-NF-15-002 Rev. 1 Page 26 of 62 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 TRM/3.2-27 EFFECTIVE DATE 11/04/2015
Rev. 12 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 Manual3.3.7 6.3 Description PL-NF-15-002 Rev. 1 Page 27 of 62 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, and Backup Pressure Regulator Operable and Inoperable. 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 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) 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 6.2-2 and 6.2-3 are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable. The LGHR 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 TRM/3.2-28 EFFECTIVE DATE 11/04/2015
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REFERENCE:
T.S. 3.2.3 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 I I I I I I ~ I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --!---~--~---~--~---~--.!..--~--.!..--!--- -!---~--~---~--.:---~--.!..--~--.!..--~--~--!---~--~---~--~ USED IN DETERMINING FDLRX -- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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--- ~---*--~--t--~--t---~--i---~--i---~--~---*--~--t--~--t--~--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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---*--~--+--~--~---~--1---~--1---~--1---*--~--+-- --~--~--1---~--1---~--1---*--~--+--~--~--~--1---~--1---~--1---~-- 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---~--i---~--i---t--~--t--~--t---~--t---~--t---~--i---t--~--t--~--t--~--t--- ---~--i---t--~--t--~--t--~--t---~--t---~--i---t-- 1 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --~---~--~---~--~---~--~--y--~--T---~--~---r--~---~--1---~--~--y--~--T--~--~---~--~---r--~---r- --y--~--T--~--~---~--~---r--,---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 I I I I I I I I I I I I I I I I I I I I I 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 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---'----'---'----'---L---'---L---'---"'---'---"'---'----'---L---'---L---'---L---'---"'---'---"'---'----'---L---'---L---'---"'---'---"'-- -"'---M 74400 7 1 0 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I I I I
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Rev. 12 Main Turbine Bypass Operable PL-NF-15-002 Rev. 1 Page 29 of 62 SUSQUEHANNA UNIT 2 TRM/3.2-30 EFFECTIVE DATE 11/04/2015
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Rev. 12 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 PL-NF-15-002 Rev. 1 Page 38 of 62 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 TRM/3.2-39 EFFECTIVE DATE 11/04/2015
Rev. 12 Function Low Power Range Setpoint Table 7.2-1 RBM Setpoints Intermediate Power Range Setpoint High Power Range Setpoint Low Power Range - Upscale Intermediate Power Range-Upscale High Power Range - Upscale Allowable Value<1l 28.0 63.0 83.0 123.4 117.4 107.6 PL-NF-15-002 Rev. 1 Page 39 of 62 Nominal Trip Setpoint 24.9 61.0 81.0 123.0 117.0 107.2 (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 <2.3l (%of Rated) ~ 28 and< 90 < 1.76 ~ 90 and< 95 < 1.47 ~ 95 < 1.68 <2l Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable. <3l Applicable to both Two Loop and Single Loop Operation. SUSQUEHANNA UNIT 2 TRM/3.2-40 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 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 ATRIUM'-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 (ATRIUM'-1 0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. a) Main Turbine Bypass I EOC-RPT I 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 TRM/3.2-41 EFFECTIVE DATE 11/04/2015
Rev. 12 d) Backup Pressure Regulator Inoperable PL-NF-15-002 Rev. 1 Page 41 of 62 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:Fiow-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 TRM/3.2-42 EFFECTIVE DATE 11/04/2015
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Rev. 12 PL-NF-15-002 Rev. 1 Page 43 of 62 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM/3.2-44 EFFECTIVE DATE 11/04/2015
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Q) c.. 0 2.4 0::: a.. () ~ 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 I LEGEND 1-- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1-- t-- I I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 1-- ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I USED IN DETERMINING MFLCPR I l3o, 1.901 A 8
REFERENCE:
T.S. 3.4.1 and 3.2.21 1108, 1.48 30 40 50 60 70 80 90 100 Total Core Flow (MLBIHR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-2 110
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2.6 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 I I I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 123,4.081 INSERTION TIME \\ \\. CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME ' 26,3.80 CURVE C: CORE POWER::;; 26% AND CORE FLOW::;; 50 MLBM/HR r-C SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I I I USED IN DETERMINING MFLCPR 126.01' 2.421 140,2.081 A 8 60, 1.921 =l_
REFERENCE:
T.S. 3.4.1 and 3.2.21 I 20 30 I 40 50 60 70 Core Power(% RATED) 80 90 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-3 1100, 1.921 100
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Rev. 12 Main Turbine Bypass Inoperable PL-NF-15-002 Rev. 1 Page 46 of 62 SUSQUEHANNA UNIT 2 TRM/3.2-47 EFFECTIVE DATE 11/04/2015
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2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 LEGEND I-- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME I-- CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS I-- VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I USED IN DETERMINING MFLCPR 130, 2.171 A B i
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2j 108, 1.65 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-4 100 110
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SSES UNIT 2 CYCLE 18 LEGEND 4.2 4.4 r2\\4.30 1 ~~~~~,-~----~-~CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3.6 3.4 1-----11---t-----+-----H SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 3.2 3.0 USED IN DETERMINING MFLCPR. 2.8 }= D 2.6 1 1 126.o1, 2.481 I I I I I I I I I I I I I I 2.4 1 -k:: 140, 2.141 ""'1-- 2.2 1.8 20 30 40 160, 1.971 A-s 50 60 70 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-5 100, 1.971 80 90 100
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SUSQUEHANNA UNIT 2 Rev. 12 EOC-RPT Inoperable TRM/3.2-50 PL-NF-15-002 Rev. 1 Page 49 of 62 EFFECTIVE DATE 11/04/2015
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Q) c.. 0 2.6 0:::: a.. (.) 2 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME f-- SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I USED IN DETERMINING MFLCPR I H 3o, 1.9o A B
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 108, 1.48 t 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-6 100 110
- 0 CD <
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- -123,4.081 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
\\ INSERTION TIME \\. CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 26,3.80 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR r-c SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES r-ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR I 26.01, 2.42 I ........................ 140, 2.081 160, 1.921 A -J
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.21 20 30 40 50 60 70 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-7 8 80 90 1-- 1-- 1-- l= 1100, 1.921 100
- 0
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REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-8 100 1108,1.481 110
- u CD <
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4.6 4.4 4.2 4.0 3.8 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 LEGEND W23, 4.o81 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME \\ \\. CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME ' 126,3.801 CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR -_c SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 126.01, 2.81 I USED IN DETERMINING MFLCPR 140,2.531 A B -160,2.141 ~ ~
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.21 __ J. 20 30 __J___ 40 50 60 70 80 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-9 90 1--- 1--- 1--- f-t= 1100,2.141 100
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Rev. 12 PL-NF-15-002 Rev. 1 Page 55 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM/3.2-56 EFFECTIVE DATE 11/04/2015
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REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-10
- Operation with one TSV or TCV closed is only supported at power levels::; 75% rated power.
100 1108, 1.681 110
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I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 123,4.081 INSERTION TIME ' '\\. CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME '\\ 26, 3.80 CURVE C: CORE POWER:::; 26% AND CORE FLOW:::; 50 MLBM/HR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I USED IN DETERMINING MFLCPR 126.01' 2.421 140,2.081 A 8 160, 1.921 175,1.9:
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I I 30 40 50 60 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-11 70 80
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Rev. 12 9.0 POWER I FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description PL-NF-15-002. Rev. 1 Page 58 of 62 Monitor reactor conditions to maintain THERMAL POWER I core flow outside of Stability Regions I and II of the Power I Flow map, Figure 9.1. If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power I 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 I Flow map is considered an immediate scram region. Region II of the Power I Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation. SUSQUEHANNA UNIT 2 TRM/3.2-59 EFFECTIVE DATE 11/04/2015
0 w ~ ~ 0 -... Q) ~ a.. iii E... Q) .t: 1-Rev. 12 PL-NF-15-002 Rev. 1 Page 59 of 62 120Lfo~~Ieoaii~~IICD~ICDJJII[OJ~===-;rrT;====~
Purpose:
UNIT 2 120 110 Initial/ Date: 110 100 100 rn 90 90 80 80 70 70 60 60 50 50 40 40 30 10 o~~~++~~~~q_~++~~~+4~~~~~~++~~~+44-~++~~~~ o 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mibm/hr) (for SLO <75% Pump Speed Use Form G0-200-009-2) Figure 9.1 SSES Unit 2 Cycle 18 Power I Flow Map SUSQUEHANNA UNIT 2 TRM/3.2-60 EFFECTIVE DATE 11/04/2015
Rev. 12 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description PL-NF-15-002 Rev. 1 Page 60 of 62 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: = 1.12 = 16 = 60 Mlbm I hr SUSQUEHANNA UNIT 2 TRM/3.2-61 EFFECTIVE DATE 11/04/2015
Rev. 12
11.0 REFERENCES
PL-NF-15-002 Rev. 1 Page 61 of 62 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, "X COBRA-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 TRM/3.2-62 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 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-85-7 4(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 CASM0-4/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. NED0-32465-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 TRM/3.2-63 EFFECTIVE DATE 11/04/2015 to PLA-7396 Revised Unit 2 Cycle 18 COLR
Rev. 12 Susquehanna SES Unit 2 Cycle 18 PL-NF-15-002 Rev. 1 Page 1 of 62 CORE OPERATING LIMITS REPORT SUSQUEHANNA UNIT 2 TRM/3.2-2 Nuclear Fuels Engineering September 2015 EFFECTIVE DATE 11/04/2015
Rev. Affected No. Sections 0 ALL 1 ALL Rev. 12 PL-NF-15-002 Rev. 1 Page 2 of 62 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Description/Purpose of Revision Issuance of this COLR is in support of Unit 2 Cycle 18 operation. New COLR for the inclusion of operating limits regarding a Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closure event. This revision also changes the Turbine Bypass Inoperable MCPRt limits that were updated in the licensing analysis to remove conservatisms from the initial analysis that are not required per the NRC approved methodology. FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 TRM/3.2-3 EFFECTIVE DATE 11/04/2015
Rev. 12 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 18 CORE OPERATING LIMITS REPORT Table of Contents PL-NF-15-002 Rev. 1 Page 3 of 62
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 I FLOW MAP................................................................................................ 58 10.0 OPRM SETPOINTS.................................................................................................... 60
11.0 REFERENCES
............................................................................................................ 61 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 11/04/2015
Rev. 12
1.0 INTRODUCTION
PL-NF-15-002 Rev. 1 Page 4 of 62 This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 18 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 TRM/3.2-5 EFFECTIVE DATE 11/04/2015
Rev. 12 2.0 DEFINITIONS PL-NF-15-002 Rev. 1 Page 5 of 62 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 MAP RAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR 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 I hr, below which the OPRM RPS trip is activated. SUSQUEHANNA UNIT 2 TRM/3.2-6 EFFECTIVE DATE 11/04/2015
Rev. 12 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 b) 0.28% ~klk with the highest worth rod determined by test PL-NF-15-002 Rev. 1 Page 6 of 62 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 TRM/3.2-7 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 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 ATRIUM'-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 TRM/3.2-8 EFFECTIVE DATE 11/04/2015
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Rev. 12 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 Technical Specification Reference PL-NF-15-002 Rev. 1 Page 9 of 62 Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 5.2 Technical Requirements Manual Reference Technical Requirements Manual3.3.7 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 (ATRIUM '-1 0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. a) Main Turbine Bypass I EOC-RPT I 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 TRM/3.2-10 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 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 TRM/3.2-11 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 Rev. 1 Page 11 of 62 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 EFFECTIVE DATE 11/04/2015
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ra... 1.7 QJ c. 0 0::: a.. (.) 1.6 ~ 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 18 I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR J 30, 1.571 ~ ............... r---: __ 8 ............ ~ I
REFERENCE:
T.S. 3.2.2 ~ ~ 1108, 1.211 30 40 ~ 50 60 70 80 90 100 Total Core Flow (MLBIHR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-1 110
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2.0 1.8 1.6 1.4 1.2 SSES UNIT 2 CYCLE 18 H23, 3.4o \\ LEGEND \\ 126,3.161 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBMIHR -c _l I I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I I I USED IN DETERMINING MFLCPR ~ 126.01, 2.00 1 140,1.721 l26.o1, 1.91 1 ~~-- A 40, 1.69 ~ ISO, 1.441 r---...: --......... 194.46, 1.37 J .L
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REFERENCE:
T.S. 3.2.2 I I so, 1.431 --....~------11oo, 1.351 65, 1.50 185,1.41 II 1100,1.321 20 30 40 50 60 70 80 90 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-2 94.46, 1.32 ~ 100 "'0 "'0 OJ r (Q I CD z 71 VJ:;:o--" OCD'fl -n<o (j) 0 N--"N
Rev. 12 Main Turbine Bypass Inoperable PL-NF-15-002 Rev. 1 Page 14 of 62 SUSQUEHANNA UNIT 2 TRM/3.2-15 EFFECTIVE DATE 11/04/2015
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1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 18 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1-130,1.791 I USED IN DETERMINING MFLCPR ~ ~ ............... ~ r---...... A 8 ~ ~ ~ ~ 1108, 1.361 ~ I
REFERENCE:
T.S. 3.7.6 and 3.2.2 I 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-3 100 110
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Ill (!) a. 0 0:: a.. (.) ~ 123,3.581 SSES UNIT 2 CYCLE 18 3.6 1\\ 123,3.401 \\ LEGEND 3.4 \\\\ \\ 126,3.291 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 126,3.161 INSERTION TIME r-C CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME ~ 3.0 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR r-2.8 r-I I I I 2.6 r-SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE 2.4 2.2 2.0 1.8 1.6 1.4 1.2 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I I I I I 26.01, 2.05 I USED IN DETERMINING MFLCPR 140,1.771 ~ -A-lBO, 1.531 -B-
REFERENCE:
T.S. 3.7.6 and 3.2.21 20 30 40 50 60 70 80 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-4 r-I ~ 100, 1.531 90 100
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SUSQUEHANNA UNIT 2 Rev. 12 EOC-RPT Inoperable TRM/3.2-18 PL-NF-15-002 Rev. 1 Page 17 of 62 EFFECTIVE DATE 11/04/2015
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1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 18 LEGEND I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM f-- INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME f-- I I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES r-- ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR ~ 30, 1.57 ~ -......... ~ A B ~ I
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 I ~ 30 40 50 ~ 1108, 1.211 ~ 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-5
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2.0 1.8 1.6 1.4 1.2 --123, 3.40 \\ \\ 126, 3.161 ,...- c r-1 26.01, 2.00 1 140,1.721 SSES UNIT 2 CYCLE 18 I I I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR I I I I l SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR A -s
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REFERENCE:
T.S. 3.3.4.1 and 3.2.21 180,1.441 -J 1194.46, 1.38 r 1100,1.381 I 20 30 40 50 60 70 80 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-6 90 100 lJ lJ Ill r (Q I <D z 71 CO ;:a-" oro'f -<o en
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Rev. 12 PL-NF-15-002 Rev. 1 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-21 EFFECTIVE DATE 11/04/2015
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REFERENCE:
T.S. 3.7.8 and 3.2.21 ~ 30 40 50 ~ 1108, 1.211 ~I 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-7 100 110
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I H23, 3.4o LEGEND \\ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM \\ 126, 3.161 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR r-c SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 126.01' 2.331 USED IN DETERMINING MFLCPR r---........ t40, 2.10j A B -.............. -~ I so 1 441
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REFERENCE:
T.S. 3.7.8 and 3.2.21 194.46, 1.37 ~ ~ I 20 30 I 40 50 60 70 80 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-8 90 1100, 1.351 100 ""'0 ""'0 w r (Q I CD z N "Jl N;:u-'" oCD'f -<a (J') 0 N-'"N
Rev. 12 PL-NF-15-002 Rev. 1 Page 23 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM/3.2-24 EFFECTIVE DATE 11/04/2015
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m 11 11 m 0 --; m 0 ~ m 0 .t>. -- N 0 01 2.2 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 18 I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME l3o, 1.821 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR ~ ~ ~ 8 ~ ............. ~ 1108, 1.38 ~ II
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7 I 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-9
- Operation with one TSV or TCV closed is only supported at power levels ~ 75% rated power.
100 110
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\\. LEGEND \\. 126, 3.161 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR -c I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE - PER SR 3.7.6.1 AND 3.7.6.2 r-I I I USED IN DETERMINING MFLCPR ~ 126.01, 2.oo 1 ............... r----:---- -.._. 140,1.721 l26.o1, 1.91 1 --....::.:::.:: ~ ~.L ---A ---------- 40, 1.69 1 1 75, 1.48 r t 8 n_
REFERENCE:
T.S. 3.2.2 and TRM 3.3.71 20 30 40 50 60 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-10 65, 1.50 175,1.441 70 80
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Rev. 12 Table 5.3-1 PL-NF-15-002 Rev. 1 Page 26 of 62 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 TRM/3.2-27 EFFECTIVE DATE 11/04/2015
Rev. 12 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 Manual3.3.7 6.3 Description PL-NF-15-002 Rev. 1 Page 27 of 62 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, and Backup Pressure Regulator Operable and Inoperable. 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 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) 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 6.2-2 and 6.2-3 are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable. The LGHR 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 TRM/3.2-28 EFFECTIVE DATE 11/04/2015
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Rev. 12 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 PL-NF-15-002 Rev. 1 Page 38 of 62 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 TRM/3.2-39 EFFECTIVE DATE 11/04/2015
Rev. 12 Function Low Power Range Setpoint Table 7.2-1 RBM Setpoints Intermediate Power Range Setpoint High Power Range Setpoint Low Power Range - Upscale Intermediate Power Range-Upscale High Power Range - Upscale Allowable Value<1l 28.0 63.0 83.0 123.4 117.4 107.6 PL-NF-15-002 Rev. 1 Page 39 of 62 Nominal Trip Setpoint 24.9 61.0 81.0 123.0 117.0 107.2 (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 <2.3l (%of Rated) ~ 28 and< 90 < 1.76 ~ 90 and< 95 < 1.47 ~ 95 < 1.68 <2l Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable. <3l Applicable to both Two Loop and Single Loop Operation. SUSQUEHANNA UNIT 2 TRM/3.2-40 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 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 ATRIUM'-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 (ATRIUM'-1 0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. a) Main Turbine Bypass I EOC-RPT I 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 TRM/3.2-41 EFFECTIVE DATE 11/04/2015
Rev. 12 d) Backup Pressure Regulator Inoperable PL-NF-15-002 Rev. 1 Page 41 of 62 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:Fiow-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 TRM/3.2-42 EFFECTIVE DATE 11/04/2015
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- 0 CD <
N ""0 r I z, I -" CJ1 I 0 0 N
Rev. 12 PL-NF-15-002 Rev. 1 Page 43 of 62 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM/3.2-44 EFFECTIVE DATE 11/04/2015
(f) c (f) 0 c m I )> z z )> c z -I N -I
- 0 s:: --w N
I .j:>. c.n m "'Tl "'Tl m 0 -I m 0 )> -I m 0 .j:>. i\\3 0 c.n 3.6 3.4 3.2 3.0 2.8 .E
- .::i C'l = 2.6 til...
Q) c.. 0 2.4 0::: a.. () ~ 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 I LEGEND 1-- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1-- t-- I I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 1-- ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I USED IN DETERMINING MFLCPR I l3o, 1.901 A 8
REFERENCE:
T.S. 3.4.1 and 3.2.21 1108, 1.48 30 40 50 60 70 80 90 100 Total Core Flow (MLBIHR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-2 110
- a CD
- <
N \\J \\J ru r (Q I CD z ~ 71 ~;:a-" oCD'f ...... <0 0') 0 N-"N
(f) c (f) 0 c m I )> z z )> c z -1 N -1
- 0 s: --
VJ i-v I -l:>. (j) m "'Tl "'Tl m 0 -1 m 0 ~ m 0 -l:>. i\\:3 0 U1 4.6 4.4 4.2 4.0 3.8 3.6 .E 3.4
- .::i Cl s::
3.2 ~ Q) 3.0 c.. 0 0::: 2.8 ll. (..)
- 2:
2.6 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 I I I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 123,4.081 INSERTION TIME \\ \\. CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME ' 26,3.80 CURVE C: CORE POWER::;; 26% AND CORE FLOW::;; 50 MLBM/HR r-C SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I I I USED IN DETERMINING MFLCPR 126.01' 2.421 140,2.081 A 8 60, 1.921 =l_
REFERENCE:
T.S. 3.4.1 and 3.2.21 I 20 30 I 40 50 60 70 Core Power(% RATED) 80 90 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-3 1100, 1.921 100
- 0 CD <
N "'U "'U OJ r (Q I CD z ~ 71 CJ1:;:o-'- OCD'f -<a (j) 0 N-'-N
Rev. 12 Main Turbine Bypass Inoperable PL-NF-15-002 Rev. 1 Page 46 of 62 SUSQUEHANNA UNIT 2 TRM/3.2-47 EFFECTIVE DATE 11/04/2015
(/) c (/) 0 c m I > z z > c z -I N -I
- 0 s::
~ N I ~ OJ m "'Tl "'Tl m () -I m 0 > -I m 0 ~ N 0 01 4.2 4.0 3.8 3.6 3.4 ~ 3.2 E
- .:i g> 3.0 ttl...
2.8 Q) c. 0 0::: a.. 2.6 (.)
- 2:
2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 LEGEND I-- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME I-- CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS I-- VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I USED IN DETERMINING MFLCPR 130, 2.171 A B i
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2j 108, 1.65 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-4 100 110
- 0 CD N
'""() '""() s:u r (Q I CD z .j:>. 71 -....J:;:o--" oCD'f -<0 (j)" 0 N--"N
(/) c (/) 0 c m I )> z z )> c z --i N --i
- a s
- --
(;.) N I ~ <0 m 'Tl 'Tl m 0 --i m 0 ::; m 0 ~ i\\3 0 01 .... E
- J Cl t:
~ Q) c. 0 0::: D. ()
- 2:
SSES UNIT 2 CYCLE 18 LEGEND 4.2 4.4 r2\\4.30 1 ~~~~~,-~----~-~CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3.6 3.4 1-----11---t-----+-----H SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 3.2 3.0 USED IN DETERMINING MFLCPR. 2.8 }= D 2.6 1 1 126.o1, 2.481 I I I I I I I I I I I I I I 2.4 1 -k:: 140, 2.141 ""'1-- 2.2 1.8 20 30 40 160, 1.971 A-s 50 60 70 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-5 100, 1.971 80 90 100
- 0 CD N
"lJ "lJ s:u r (Cl I CD z .f:>,. 71 CXJ;::o""" oCD<f -<a (J). 0 N--"N
SUSQUEHANNA UNIT 2 Rev. 12 EOC-RPT Inoperable TRM/3.2-50 PL-NF-15-002 Rev. 1 Page 49 of 62 EFFECTIVE DATE 11/04/2015
(/) c (/) 0 c m I )> z z )> c z -I N -I
- 0 s:: --
c..v N I CJ1 m,.,,., m 0 -I m 0 )> -I m 0 ~ N 0 CJ1 4.0 3.8 3.6 3.4 3.2 E 3.0
- J Cl 1:
- 0:0 2.8 ro...
Q) c.. 0 2.6 0:::: a.. (.) 2 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME f-- SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I USED IN DETERMINING MFLCPR I H 3o, 1.9o A B
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 108, 1.48 t 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-6 100 110
- 0 CD <
N ""'0 ""'0 ru r (Q I CD z <J1 71 O:;:o--"' OCDCf -<0 (j)
- 0 N--"'N
(/) c (/) 0 c m I )> z z )> c z -I N -I
- 1J s
- --
0.) tv I 01 N m -n -n m 0 -I m 0 )> -I m 0 ~ N 0 01 4.6 4.4 4.2 4.0 3.8 3.6 .E 3.4
- .:i Cl s::
3.2 Ia... (l) 3.0 c.. 0 0::: 2.8
- a.
(..)
- 2:
2.6 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 LEGEND
- -123,4.081 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
\\ INSERTION TIME \\. CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 26,3.80 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR r-c SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES r-ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR I 26.01, 2.42 I ........................ 140, 2.081 160, 1.921 A -J
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.21 20 30 40 50 60 70 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-7 8 80 90 1-- 1-- 1-- l= 1100, 1.921 100
- 0
<D < N "U "U ru r (Q I <D z (]1 71 -->.:::0-->. om<f -<o Q). 0 N-->.N
Rev. 12 PL-NF-15-002 Rev. 1 Page 52 of62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-53 EFFECTIVE DATE 11/04/2015
(/) c (/) 0 c m I )> z z )> c z _, N ..... E
- i Cl c:
- 0
- i Cl c:
~
- 5::
Q) c. 0 c..v 0::: t;-J c.. (]1 () ,l::>.
- !iE m
"Tl "Tl m 0 _, m 0 ~ m 0 ,l::>. -- N 0 (]1 4.0 3.8 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 LEGEND f--- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR W 30, 1.90 L A B j
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-8 100 1108,1.481 110
- u CD <
N "0 "0 w r (Q I CD z (]1 71 C.V:;u--" oCD'f -<o (J). 0 N --" N
(/) c (/) 0 c m I )> z z )> c z -1 N -1
- 0 s: --w tv I
(]1 (]1 m "Tl "Tl m 0 -1 m 0 ~ m 0 ,l::>. -- N 0 (]1 '§
- .:i C) c
- .;::J nl Q) c..
0 a:: a.. (.)
- 2:
4.6 4.4 4.2 4.0 3.8 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 LEGEND W23, 4.o81 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME \\ \\. CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME ' 126,3.801 CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR -_c SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 126.01, 2.81 I USED IN DETERMINING MFLCPR 140,2.531 A B -160,2.141 ~ ~
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.21 __ J. 20 30 __J___ 40 50 60 70 80 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-9 90 1--- 1--- 1--- f-t= 1100,2.141 100
- 0 CD <
1\\.) '1J '1J w r (.Cl I CD z CJ1 71 ~::::0...>. oCD'f -<o m
- o 1\\.)...>.1\\.)
Rev. 12 PL-NF-15-002 Rev. 1 Page 55 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM/3.2-56 EFFECTIVE DATE 11/04/2015
(/) c (/) 0 c m I )> z z )> c z -I N -I
- 0 s:
w N I (Jl -..J m 11 11 m 0 -I m 0 ::; m 0 +:>. i\\3 0 (Jl 4.0 3.8 3.6 3.4 3.2 .E 3.0
- J C'l s:::
2.8 C'CI Q) c. 0 2.6 0::: a.. (.) ~ 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 18 LEGEND r--- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 13o, 2.201 A 8 j
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 30 40 50 60 70 80 90 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-10
- Operation with one TSV or TCV closed is only supported at power levels::; 75% rated power.
100 1108, 1.681 110
- 0 CP N
"U "U ru r (0 I CP z ()1 71 m;u-" ocoCf ...... <0 0) 0 N-"N
(/) c (/) 0 c m I > z z > c z -I N -I
- u s::
c..v N I CJ'l ():) m Tl Tl m 0 -I m 0 ~ m 0 ~ 0 CJ'l .E
- i Cl t:
C'Cl Q) c.. 0 0::: a.. ()
- 2 4.6 4.4 4.2 4.0 3.8 3.6 3.4 _c 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.8 1.6 D 1.4 20 SSES UNIT 2 CYCLE 18 I
I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 123,4.081 INSERTION TIME ' '\\. CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME '\\ 26, 3.80 CURVE C: CORE POWER:::; 26% AND CORE FLOW:::; 50 MLBM/HR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I USED IN DETERMINING MFLCPR 126.01' 2.421 140,2.081 A 8 160, 1.921 175,1.9:
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I I 30 40 50 60 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-11 70 80
- 0 CD <
N ""0 ""0 Ill r (Q I CD z CJ1 71 -..J;:o-'- OCD'f _,<0 (j). 0 !\\..)....>.!\\..)
Rev. 12 9.0 POWER I FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description PL-NF-15-002. Rev. 1 Page 58 of 62 Monitor reactor conditions to maintain THERMAL POWER I core flow outside of Stability Regions I and II of the Power I Flow map, Figure 9.1. If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power I 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 I Flow map is considered an immediate scram region. Region II of the Power I Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation. SUSQUEHANNA UNIT 2 TRM/3.2-59 EFFECTIVE DATE 11/04/2015
0 w ~ ~ 0 -... Q) ~ a.. iii E... Q) .t: 1-Rev. 12 PL-NF-15-002 Rev. 1 Page 59 of 62 120Lfo~~Ieoaii~~IICD~ICDJJII[OJ~===-;rrT;====~
Purpose:
UNIT 2 120 110 Initial/ Date: 110 100 100 rn 90 90 80 80 70 70 60 60 50 50 40 40 30 10 o~~~++~~~~q_~++~~~+4~~~~~~++~~~+44-~++~~~~ o 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mibm/hr) (for SLO <75% Pump Speed Use Form G0-200-009-2) Figure 9.1 SSES Unit 2 Cycle 18 Power I Flow Map SUSQUEHANNA UNIT 2 TRM/3.2-60 EFFECTIVE DATE 11/04/2015
Rev. 12 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description PL-NF-15-002 Rev. 1 Page 60 of 62 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: = 1.12 = 16 = 60 Mlbm I hr SUSQUEHANNA UNIT 2 TRM/3.2-61 EFFECTIVE DATE 11/04/2015
Rev. 12
11.0 REFERENCES
PL-NF-15-002 Rev. 1 Page 61 of 62 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, "X COBRA-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 TRM/3.2-62 EFFECTIVE DATE 11/04/2015
Rev. 12 PL-NF-15-002 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-85-7 4(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 CASM0-4/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. NED0-32465-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 TRM/3.2-63 EFFECTIVE DATE 11/04/2015}}