Text

Submittal of Unit 2 Cycle 20 Core Operating Limits Report, Revision 2 (PLA-7802)
	ML19239A111
Person / Time
Site:	Susquehanna
Issue date:	08/27/2019
From:	Cimorelli K; Susquehanna, Talen Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	PLA-7802
	Download: ML19239A111 (67)
	v • d • e

Kevin Cimorelli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 TALEN*~.

ENERGY Tel. 570.542.3795 Fax 570.542.1504 Kevin.Cimorelli@TalenEnergy.com August 27, 2019 Attn: Document Control Desk 10 CFR 50.4 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION SUBMITTAL OF UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT, REVISION 2 PLA-7802 Docket No. 50-388 Susquehanna Stearn Electric Station (SSES) Technical Specification Section 5.6.5 requires that the Core Operating Limits Report (COLR), including any mid-cycle supplements or revisions, be provided upon issuance to the NRC in accordance with 10 CFR 50.4. Pursuant to this requirement, the SSES Unit 2 Cycle 20 COLR, Revision 2, is provided in the attachment. This revision is a result of updated licensing analysis for the revised Cycle 20 core design which is documented in the licensee's Corrective Action Program. All changes are denoted by revision bars in the margin of the report.

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

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

Attachment:

SSES Unit 2 Cycle 20 COLR, Revision 2 Copy: NRC Region I Ms. L. H. Micewski, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. M. Shields, PA DEP/BRP

Attachment to PLA-7802 SSES Unit 2 Cycle 20 COLR, Revision 2

PL-NF-19-003 Rev. 2 Page 1 of 65 Susquehanna SES Unit 2 Cycle 20

-CORE -OPERATING -LIMITS

-REPORT Nuclear Fuels Engineering August 2019

PL-NF-19-003 Rev.2 Page 2 of 65 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX REV AFFECTED NO. SECTIONS DESCRIPTION I PURPOSE OF REVISION Issuance of this COLR is in support of Unit 2 Cycle 20 operation.

0 ALL CR-2019-03732 is evaluating a condition that should it result in a revision to the COLR, will be submitted in accordance with Technical Specification 5.6.5.

1 ALL The U2C20 COLR is revised to include licensing analyses results for the revised U2C20 core design (CR-2019-03732).

Changes are made to the following figures: 5.2-1 through 5.2-10, 6.2-5, and 8.2-2 through 8.2-11. Changes to the thermal limits are limited to the following figures: 5.2-1 through 5.2-5, 5.2-7, 5.2-9, 5.2-10, 6.2-5, 8.2-2, 8.2-4, 8.2-6, 8.2-8, and 8.2-10. Only the captions were changed for the remaining figures (5.2-6, 5.2-8, 8.2-3, 8.2-5, 8.2-7, 8.2-9, 8.2-11).

Revision 1 of the Unit 2 Cycle 20 COLR is valid only for operation from BOC to MOC. MOC (Middle Of Cycle) is defined as a cycle exposure of 4,975 MWd/MTU.

2 ALL The U2C20 COLR is revised to include licensing analyses results for the full cycle of U2C20 operation.

Changes are made to the following figures: 5.2-1 to 5.2-10, 6.2-3, 6.2-5, 6.2-7, 6.2-9, and 8.2-2 to 8.2-11. Changes to the thermal limits are limited to the following figures: 5.2-4, 5.2-8, 6.2-3, 6.2-5, 6.2-7, 6.2-9, 8.2-5, and 8.2-

9. Only the captions were changed for the remaining figures (5.2-1 to 5.2-3, 5.2-5 to 5.2-7, 5.2-9, 5.2-10, 8.2-2 to 8.2-4, 8.2-6 to 8.2-8, 8.2-10, and 8.2-11 ).

Revision 2 of the Unit 2 Cycle 20 COLR is valid for operation from BOC to EOC.

FORM NFP-QA-008-2, Rev. 2

PL-NF-19-003 Rev. 2 Page 3 of 65 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 20 CORE OPERATING LIMITS REPORT Table of Contents

1.0 INTRODUCTION

......................................................................................................... 4 2.0 DEFINITIONS ............................................................................................................. 5 3.0 SHUTDOWN MARGIN ................................................................................................ 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ....................... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) ........................................................... 9 6.0 LINEAR HEAT GENERATION RATE (LHGR) ............................................................. 27 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ........................................................................................................ 41 8.0 RECIRCULATION LOOPS- SINGLE LOOP OPERATION ......................................... 43 9.0 POWER I FLOW MAP ................................................................................................ 61 10.0 OPRM SETPOINTS .................................... ,............................................................... 63

11.0 REFERENCES

............................................................................................................ 64

PL-NF-19-003 Rev. 2 Page 4 of 65

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 20 is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.

PL-NF-19-003 Rev. 2 Page 5 of 65 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 LHGRFACr is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACr 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 I hr, below which the OPRM RPS trip is activated.

PL-NF-19-003 Rev. 2 Page 6 of 65 3.0 SHUTDOWN MARGIN 3.1 References Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:

a) 0.38% 6.klk with the highest worth rod analytically determined b) 0.28% 6.k/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.

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

PL-NF-19-003 Rev. 2 Page 7 of 65 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 References 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 in Two Loop operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. The APLHGR limits for Single Loop operation are provided in Section 8.0.

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ATRIUM'-1 0 FUEL oro'P FIGURE 4.2-1 ..... < 0 (j). 0 O'INC..V
PL-NF-19-003 Rev. 2 Page 9 of 65 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 References Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 5.2 Description The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRI UM'-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 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.
PL-NF-19-003 Rev. 2 Page 10 of 65 5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.
Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
PL-NF-19-003 Rev. 2 Page 11 of 65 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 20 2.2 I I I LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I I 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
.....E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
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PL-NF-19-003 Rev. 2 Page 14 of 65 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 20 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME -
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.0 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1.9 r-USED IN DETERMINING MFLCPR E 130, 1.781 I
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TWO LOOP OPERATION (BOC TO EOC) om'P FIGURE 5.2-3 -
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PL-NF-19-003 Rev. 2 Page 17 of 65 EOC-RPT Inoperable
SSES UNIT 2 CYCLE 20 2.2 ------
LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM -
INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I I 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES -
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
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REFERENCE:
T.S. 3.3.4.1 and 3.2.2 I 1.3 I"--- 1108, 1.25J
~
1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) '""0 '""0 ru rI z
(Q MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD EOC-RPT INOPERABLE ....>. 71 co;:o->-
TWO LOOP OPERATION (BOC TO EOC) oro'P
-+.<O FIGURE 5.2-5 0). 0 CJ1NW
SSES UNIT 2 CYCLE 20 3.6 I I I I LEGEND 3.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 123, 3.171 INSERTION TIME 3.2 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 '\ 126, 3.021 CURVE C: CORE POWER::::; 26% AND CORE FLOW::::; 50 MLBM/HR
"--C 2.8
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J 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE Cl 1:
PER SR 3.7.6.1 AND 3.7.6.2 ctS Q) 2.4 c.. USED IN DETERMINING MFLCPR 0
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............... 140,1.731 1.8 ,...........
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T.S. 3.3.4.1 and 3.2.21 I 1100, 1.431 I
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(Q I MCPR OPERATING LIMIT VERSUS CORE POWER CD EOC-RPT INOPERABLE ....>. 71
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TWO LOOP OPERATION (BOC TO EOC) oco'P FIGURE 5.2-6 -
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CJ1 N W
PL-NF-19-003 Rev.2 Page 20 of 65 Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 20 2.2 I I I I 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 E
1.8
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1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) -o -o O> r z
(Q I MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD BACKUP PRESSURE REGULATOR INOPERABLE tv 71 TWO LOOP OPERATION (BOC TO EOC)
-";o-"
ocoCf' FIGURE 5.2-7 -<o m* o CJ1 tv w
SSES UNIT 2 CYCLE 20 3.6 3.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 --j23, 3.151 INSERTION TIME 3.0 ' "\ 126, 3.oo I CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER::;; 26% AND CORE FLOW::;; 50 MLBM/HR r-c 2.8
.E
i 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES Cl c: ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
...11:1 CJ) 2.4 0.. 126.01' 2.271 USED IN DETERMINING MFLCPR 0
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REFERENCE:
T.S. 3.7.8 and 3.2.21 ~ ........ 1100,1.361 I
1.4 I I 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) \J \J ru rI z
(Q MCPR OPERATING LIMIT VERSUS CORE POWER CD BACKUP PRESSURE REGULATOR INOPERABLE 1\.) 71 I'V;:o-"-
TWO LOOP OPERATION (BOC TO EOC) oco'P FIGURE 5.2-8 _..,<o 0'>. 0
(.)11\.)W
PL-NF-19-003 Rev.2 Page 23 of 65 One TSV or TCV Closed
SSES UNIT 2 CYCLE 20 2.2 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
.E 130,1.781
J 1.8 USED IN DETERMINING MFLCPR
~
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T.S. 3.2.2 and TRM 3.3.71 1.3 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) ""0 ""0 w rI z
(Q MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD ONE TSV OR TCV CLOSED* 1\.) 71
..r:..;:o->-
TWO LOOP OPERATION (BOC TO EOC) OCDcp FIGURE 5.2-9 -
0).
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Operation with one TSV or TCV closed is only supported at power levels ::; 75% rated power. CJ'II\.)(.U
SSES UNIT 2 CYCLE 20 3.4 1-3.2 J23, 3.151 LEGEND 1-1-
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.0 1-126,3.001 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
-C 1-2.8 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 1-f-
.... 2.6
"§
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2.4 1-ctl Q)
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~
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2.0 1.8 ~ 26.01, 1.91l---- ........................ 140,1.711
~ A 1.6 -::.... 175,1.481 B
1.4
IREFERENCE:
T.S. 3.2.2 and TRM 3.3.71 ---
175,1.451 1.2 20 30 40 50 60 70 80 Core Power (% RATED) ""'0 ""'0 ru rI z
(C MCPR OPERATING LIMIT VERSUS CORE POWER CD ONE TSV OR TCV CLOSED 1\.) 71
(]1:::0->.
TWO LOOP OPERATION (BOC TO EOC) oco'P FIGURE 5.2-10 -
0').
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(]1 1\.) w
PL-NF-19-003 Rev. 2 Page 26 of 65 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable
PL-NF-19-003 Rev. 2 Page 27 of 65 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 References Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual3.3.7 6.2 Description The maximum LHGR for ATRIUM'-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.
To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided in the following figures:
a) Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) EOC-RPT or Backup Pressure Regulator Inoperable Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: Power-Dependent LHGR Limit Multiplier d) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-8: Flow-Dependent LHGR Limit Multiplier Figure 6.2-9: Power-Dependent LHGR Limit Multiplier The LHGR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-9 are valid for both Two Loop and Single Loop operation.
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PL-NF-19-003 Rev. 2 Page 29 of 65 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 20 1.10 I I
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PL-NF-19-003 Rev. 2 Page 41 of 65 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 References Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, d) Low Power Range - Upscale, e) Intermediate Power Range- Upscale, and f) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.
PL-NF-19-003 Rev. 2 Page 42 of 65 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 23 MCPR <* >
(%of Rated)
~ 28 and< 90 < 1.76
~ 90 and< 95 < 1.47
> 95 < 1.68 2
<> Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and one TCV/TSV closed.
3
<> Applicable to both Two Loop and Single Loop Operation.
PL-NF-19-003 Rev. 2 Page 43 of 65 8.0 RECIRCULATION LOOPS- SINGLE LOOP OPERATION 8.1 References Technical Specification 3.2.1, 3.2.2, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 8.2 Description APLHGR The APLHGR limit for 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 in Single Loop operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.
Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM'-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 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 d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOC
PL-NF-19-003 Rev. 2 Page 44 of 65 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.
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--..:..--..:---~---~---:.---~---~--..:..--..:---~---~---~---~---:..--...:...--..:---~---~---~---~---:..--...:...--..:---~---.;---~---~---:..---:...--..:---..: 67000, 5.6 t-
: : : : : : : : : : : : : : : : : : : : : : : : : : : : : :-~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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 4.0 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 0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 Average Planar Exposure (MWD/MTU) \J \J ru rI z
(Q AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS CD AVERAGE PLANAR EXPOSURE- SINGLE LOOP OPERATION ~ 71 CJ1:;o-'-
ATRIUM'-1 0 FUEL ocoCf FIGURE 8.2-1 - <o (j). 0 CJ1 N W
PL-NF-19-003 Rev. 2 Page 46 of 65 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 20 3.0 I I I I LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 1--
INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1---
2.4
!: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
i 2.2 1---
C) c: I I I CIS Q) 2.0 I USED IN DETERMINING MFLCPR I
a. I I 0
0:::
a..
(..) 1.8 2:
1.6 - 130,1.621 A
8 1.4 1108, 1.28 ~
1.2
REFERENCE:
T.S. 3.4.1 and 3.2.21 1.0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) ""0 ""0 n> rI z
(Q MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE ~ -;n
-....J;:o->.
SINGLE LOOP OPERATION (BOC TO EOC) oco'P FIGURE 8.2-2 -
(j).
<o 0 01 N W
SSES UNIT 2 CYCLE 20 4.0 I I I LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBMIHR 123,3.18
-'c "'
3.2 E 3.0 126, 3.031 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
J ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 Cl c:: I I I 2.8
...cu Q)
USED IN DETERMINING MFLCPR c..
0 2.6 0:::
ll.
(.)
2: 2.4 2.2 I 26.01, 2.051 2.0
~
" " " 140,1.74 A 1.8 r--s
~ 16o, 1.611 1.6 --1
REFERENCE:
T.S. 3.4.1 and 3.2.2 ~ 1100, 1.611 I
1.4 20 30 40 50 60 70 80 90 100 Core Power(% RATED)
-u -u oo rI z
(C MCPR OPERATING LIMIT VERSUS CORE POWER CD MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE ~ -;n SINGLE LOOP OPERATION (BOC TO EOC) CXl;::o-'-
oroCf>
_,<a FIGURE 8.2-3 0). 0 CJ'lNW
PL-NF-19-003 Rev. 2 Page 49 of 65 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 20 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM -
INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -
2.4
......E SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
i 2.2 f---
Cl c:
ttl (I) 2.0 I USED IN DETERMINING MFLCPR c..
0 130, 1.811 0::
a.
(.) 1.8 2
J90, 1.52
-r----__
1.6 A f99, 1.451 B
1.4 -1108,1.42 I
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.21 1.2 1.0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
\J ""'0 ru r MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW (])
(0 zI MAIN TURBINE BYPASS INOPERABLE CJ1 -;n o;::o->.
SINGLE LOOP OPERATION (BOC TO EOC) oro'P FIGURE 8.2-4 -.<0 (j). 0 CJ1 " ' c.v
SSES UNIT 2 CYCLE 20 4.0
~----4-----+-~LEGEND 3.8 R23*
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 1-------t------t-----1 INSERTION TIME 3.6 3.511 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3
j:3; 3.191\ ! I I CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBMIHR f---
I ' H 3.2 '\ )!26, 3.23! 1----
~ 3.0 ~ c ::$26, ~-041 II I I I I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 t=
I I I I II I USED IN D7TERMINING ~FLCPR I c
~ REFEREN~E: 3.0. .6, 3).21 8
I I I 6 66 16 T.S. 7 and l o, ( l A - l11oo, 1.661 1.4 20 30 40 50 60 70 80 90 100 Core Power(% RATED)
""0 ""0 ru rI z
(C MCPR OPERATING LIMIT VERSUS CORE POWER CD MAIN TURBINE BYPASS INOPERABLE (]1 -;n SINGLE LOOP OPERATION (BOC TO EOC) ->-;::o->-
oco'P FIGURE 8.2-5 -<o m* o C11NW
PL-NF-19-003 Rev. 2 Page 52 of 65 EOC-RPT Inoperable
SSES UNIT 2 CYCLE 20 3.0 I I I I LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 1--
INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1--
2.4
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
J 2.2 -
Cl c
USED IN DETERMINING MFLCPR ca Q) 2.0 I I c.
0 a:::
!l.
() 1.8 2:
130, 1.621 1.6 1.4 r
11o8, 1.28 A
B 1.2
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.21 1.0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) ""0 ""0 ru r z
(Q I MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD EOC-RPT INOPERABLE CJ'1 71 W;u-'-
SINGLE LOOP OPERATION (BOC TO EOC) OCDcp FIGURE 8.2-6 -
0').
<o 0 CJ'1 I'V w
SSES UNIT 2 CYCLE 20 4.0 3.8 LEGEND r--
f----
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME r-f----
3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME f----
i23, 3.201 CURVE C: CORE POWER :::; 26% AND CORE FLOW :::; 50 MLBM/HR 3.2 -
...... 3.0 _c 126,3.051
"§ I I I
J -
C) 2.8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 r:::
r-
~
(!) 2.6 0..
0 USED IN DETERMINING MFLCPR
~
D.. 2.4
()
a:
2.2 126.01' 2.071 2.0
............. 140,1.761 1.8 ......
16o, 1.631 A 8 1.6 1100, 1.631
]
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.21 1.4 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
-u m
-u r
MCPR OPERATING LIMIT VERSUS CORE POWER ca CD z' EOC-RPT INOPERABLE 01 71 SINGLE LOOP OPERATION (BOC TO EOC) .j::..;:o-'"
oco'P FIGURE 8.2-7 - <0 (j). 0 01 N W
PL-NF-19-003 Rev. 2 Page 55 of 65 Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 20 3.0 LEGEND 2.8 -
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I I 2.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
.E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
i 2.2 C) c: USED IN DETERMINING MFLCPR Ill Q) 2.0 0..
0 0:::
a..
{) 1.8
~
130,1.621 1.6 ......
1.4 1108, 1.28 A
8 1.2 --l
REFERENCE:
T.S. 3.4.1, 3. 7 .8, and 3.2.21 1.0 I I I 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) \J \J tu (C
rI CD z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CJ1 71 BACKUP PRESSURE REGULATOR INOPERABLE (j):::o->-
SINGLE LOOP OPERATION (BOC TO EOC) oro'P (j).
<0 0 FIGURE 8.2-8 CJ1 N W
SSES UNIT 2 CYCLE 20 3.8 f----
LEGEND 3.6 r----
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM -
INSERTION TIME 3.4 -
123,3.18 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -
3.2 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3.0 _ c ~H26, 3.o31 -
2.8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES r---
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 r---
!: 2.6 E
J g> 2.4 USED IN DETERMINING MFLCPR
~
.;:::; 126.01, 2.301 ra (I) ............... .........
0 0..
2.2 140, 2.111 0:::
a..
-......::::::: ~A
(.)
2.0 B
lE ..........
'- ~60,1.81J 11oo,1.m I
1.8
~
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.21 1.6 I I I 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
"'U "'U ru rI z
(Q MCPR OPERATING LIMIT VERSUS CORE POWER CD BACKUP PRESSURE REGULATOR INOPERABLE (]1 71
--J;;o->.
SINGLE LOOP OPERATION (BOC TO EOC) oro'P FIGURE 8.2-9 _,.,<0 0). 0
(]11\.)(J.)
PL-NF-19-003 Rev.2 Page 58 of 65 One TSV or TCV Closed
SSES UNIT 2 CYCLE 20 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM -
INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -
2.4 I
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I
.§ 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -
...1 C) s:::::
Ill Q) 2.0 I USED IN DETERMINING MFLCPR I c.. I I 0
0::: l3o, 1.811 D..
(.) 1.8 I
2:
1.6 1108, 1.441 1.4 A B -
1.2
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3. 7 I 1.0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
""'0 ""'0 ro r z
(Cl I MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD ONE TSV OR TCV CLOSED* CJ'l 71 CD:;:o-'-
SINGLE LOOP OPERATION (BOC TO EOC) OCD<f' FIGURE 8.2-10 - <a0
"'w (j) 0
Operation with one TSV or TCV closed is only supported at power levels ::0 75% rated power. CJ'l
SSES UNIT 2 CYCLE 20 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 123,3.181 3.2 CURVE C: CORE POWER::;; 26% AND CORE FLOW::;; 50 MLBM/HR 3.0 f--
c """ 126, 3.031
.... SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
"§
i ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 Cl t: I I
...ell (I) 2.6 USED IN DETERMINING MFLCPR c..
0 0::
a.. 2.4
(.)
2:
2.2 26.01, 2.05 I 2.0 ........
~
140,1.741 1.8 A 1--8
............... ISO, 1.611 1.6 H
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7J I
'75, 1.6~
1.4 20 30 40 50 60 70 80 Core Power (% RATED) lJ lJ
!l.l (C
rI MCPR OPERATING LIMIT VERSUS CORE POWER CD z ONE TSV OR TCV CLOSED Q) 71 o;:o_,_
SINGLE LOOP OPERATION (BOC TO EOC) oco'P FIGURE 8.2-11 -.<0 Q). 0 01"-'W
PL-NF-19-003 Rev. 2 Page 61 of 65 9.0 POWER I FLOW MAP 9.1 References Technical Specification 3.3.1.1 9.2 Description 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.
PL-NF-19-003 Rev. 2 Page 62 of 65 110 100 90 50 40 '
40 30 Hr~~~;;,~~~rt-.,r+,,_~-r~-+,_r+-r~-r~-+,_r+-r~-+,,_-+~r+;~~ 30
-*-;-+-;--"-+-+-1--f--+--"-f-+-+'- '
I j 1 1
+-~--c-~--~*-l--c*o--c-i-+~--c-c~-+-l-c;-**-T-~-+-~-T-~-~--I-c!-*-~--*-+--"-~--;--i-+-'-+-i-*+-l-+*-+--"-+-+-+ - c,**-i-c-- : ,
1 2ott~~~~~tW~~+t+tth~1+1tttttww~t1ttttUW~*!*ll2o
+-i,*+-i---~~-'--;-~~-*-+-*-+~~--i-J--f--~--f-J-->-i--l-i-+-'1 --~*-l--"-'--",-+:*-~-'.--~~-f--+-1--f*-+-+-ii-+-+--!--f-+-1-~--f-+-11~
0 0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mibm/hr)
Figure 9.1 SSES Unit 2 Cycle 20 Power I Flow Map
PL-NF-19-003 Rev. 2 Page 63 of 65 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:
= 1.12
= 16
= 60 Mlbm I hr
PL-NF-19-003 Rev. 2 Page 64 of 65
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).
12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
PL-NF-19-003 Rev. 2 Page 65 of 65
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 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.

PLA-7802, Submittal of Unit 2 Cycle 20 Core Operating Limits Report, Revision 2 (PLA-7802)

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PLA-7802, Submittal of Unit 2 Cycle 20 Core Operating Limits Report, Revision 2 (PLA-7802)

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1.0 INTRODUCTION

11.0 REFERENCES

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