PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078: Difference between revisions
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Edward Casulli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Be1wick, PA 18603 Tel. 570.542.3795 Fax 570.542.1504 Edward. Casulli@talenenergy.com ENERGY July 05, 2023 Attn: Document Control Desk 10 CPR 50.4 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION SUBMITTAL OF UNIT 2 CYCLE 22 CORE OPERATING LIMITS REPORT, REVISION 1 PLA-8078 Docket No. 50-388 | |||
==Reference:== | |||
"Susquehanna Steam Electric Station Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)," dated March 30, 2023 (ADAMS Accession No. ML23089A361). | |||
Susquehanna Steam Electric Station (SSES) Technical Specification Section 5.6.5 requires that the Core Operating Limits Report (COLR), including any mid-cycle supplements or revisions, be provided upon issuance to the NRC in accordance with 10 CPR 50.4. Pursuant to this requirement, the SSES Unit 2 Cycle 22 COLR, Revision 1, is provided in the attachment. | |||
Revision Owas previously provided in the reference. Revision 1 is a result of updated licensing analysis as noted within the COLR Revision Description Index. All changes are denoted by revision bars in the margin of the report. | |||
There are no new or revised commitments contained in this submittal. | |||
Should you have any questions regarding this submittal, please contact Ms. Melisa Krick, Manager- Nuclear Regulatory Affairs, at (570) 542-1818. | |||
E. Casulli | |||
==Attachment:== | |||
SSES Unit 2 Cycle 22 COLR, Revision 1 | |||
Document Control Desk PLA-8078 Copy: NRC Region I Mr. C. Highley, NRC Senior Resident Inspector Ms. A. Klett, NRC Project Manager Mr. M. Shields, PA DEP/BRP | |||
Attachment to PLA-8078 SSES Unit 2 Cycle 22 COLR, Revision 1 | |||
PL-NF-23-002 Rev. 1 Page 1 of 72 Susquehanna SES Unit 2 Cycle 22 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering June 2023 | |||
PL-NF-23-002 Rev. 1 Page 2 of 72 CORE OPERA TING LIMITS REPORT REVISION DESCRIPTION INDEX REV AFFECTED NO. SECTIONS DESCRIPTION / PURPOSE OF REVISION 0 ALL Issuance of this COLR is in support of Unit 2 Cycle 22 operation. | |||
1 ALL Issuance of this COLR revision is to support change in LHGRFACr for base case, EOC-RPT INOP, and Backup Pressure ReQulator INOP conditions. | |||
FORM NFP-QA-008-2, Rev. 2 | |||
PL-NF-23-002 Rev. 1 Page 3 of 72 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 22 CORE OPERATING LIMITS REPORT Table of Contents | |||
==1.0 INTRODUCTION== | |||
........................................................................................................... 4 2.0 DEFINITIONS ............................................................................................................... 5 3.0 SHUTDOWN MARGIN .................................................................................................. 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ....................... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) ............................................................ 10 6.0 LINEAR HEAT GENERATION RATE (LHGR}. ............................................................. 28 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ......................................................................................................... 47 8.0 RECIRCULATION LOOPS-SINGLE LOOP OPERATION .......................................... 49 9.0 POWER/ FLOW MAP .................................................................................................. 68 10.0 OPRM SETPOINTS ...................................................................................................... 70 11.0 , REFERENCES .............................................................................................................. 71 | |||
PL-NF-23-002 Rev. 1 Page 4 of 72 | |||
==1.0 INTRODUCTION== | |||
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 22 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 NRG-approved methods and are established such that all applicable limits of the plant safety analysis are met. | |||
PL-NF-23-002 Rev. 1 Page 5 of 72 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below. | |||
2.1 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height. | |||
2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height. | |||
2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type. | |||
2.4 LHGRFACt is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACt 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. 7 MCPRss.s% is the cycle-specific safety limit MCPR that ensures at least 99.9% of fuel rods are not susceptible to boiling transition. | |||
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 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 MCPRss.s% 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. | |||
2.1 O Sp is the OPRM trip setpoint for the peak to average OPRM signal. | |||
2.11 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated. | |||
PL-NF-23-002 Rev. 1 Page 6 of 72 3.0 SHUTDOWN MARGIN 3.1 References Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than: | |||
a) 0.38% 11k/k with the highest worth rod analytically determined OR b) 0.28% 11k/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 burn up, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SOM) 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-23-002 Rev. 1 Page 7 of 72 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 References Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUM'-10 fuel shall not exceed the limit shown in Figure 4.2-1A. The APLHGRs for ATRIUM' 11 fuel shall not exceed the limit shown in Figure 4.2-1 B. | |||
The APLHGR limits in Figures 4.2-1A and 4.2-1 Bare 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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~-------* ---+---+---~-------------~--~--- | |||
I I I I I I I I I ---+---+---+--- | |||
I I I I--- I ---~---+---~------ | |||
I I I I I ---+---+---~--- | |||
I I I I---------------- | |||
I I I I I ---+---+--- | |||
I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU) -0 | |||
-0 rI Ol AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS co z CD "Tl I | |||
AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION CD ATRIUM' 11 FUEL 0 | |||
:::o"' | |||
CD Cf FIGURE 4.2-1B <O | |||
- .J 0 N ...... )\.) | |||
PL-NF-23-002 Rev. 1 Page 10 of 72 5.0 MINIMUM CRITICAL POWER RA TIO (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 For Unit 2 Cycle 22, the MCPRee.e% Safety Limit is 1.07 for Two Loop operation and 1.09 for Single Loop operation. | |||
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'-10 and ATRIUM' 11) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. | |||
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel b) Main Turbine Bypass Inoperable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-8: Power Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed | |||
PL-NF-23-002 Rev. 1 Page 11 of 72 Figure 5.2-9: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-1 O: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel The MCPR limits in Figures 5.2-1 through 5.2-1 O are valid for Two Loop operation and are applicable to both ATRIUM'-10 and ATRIUM' 11 Fuel. | |||
The MCPR limits for Single Loop operation are provided in Section 8.0. | |||
5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented. | |||
Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures. | |||
PL-NF-23-002 Rev. 1 Page 12 of 72 Main Turbine Bypass / EOC-RPT / | |||
Backup Pressure Regulator Operable | |||
SSES UNIT 2 CYCLE 22 2.6 I LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.4 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 I | |||
2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES | |||
+-' 2.1 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
.E H30.0, 2.06 i I I I I | |||
::i C> 2.0 USED IN DETERMINING MFLCPR C: | |||
...a:s a, 1.9 C. 140.0, 1.86 I 0 | |||
a: 1.8 n.. | |||
0 1.7 1.6 1.5 140.1, 1.411 1.4 - A B | |||
1.3 I | |||
==REFERENCE:== | |||
T.S. 3.2.2 1.2 -1108.0, 1.221 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) -0 -0 tu i;-- | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW cg z MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE _,_ 77 | |||
<.,.) ::0 I\.) | |||
TWO LOOP OPERATION (BOC TO EOC) 0 CD Cf' ATRIUM'-10 AND ATRIUM' 11 FUEL - | |||
--.J" | |||
<o 0 I\.) _,_ I\.) | |||
FIGURE 5.2-1 | |||
SSES UNIT 2 CYCLE 22 4.0 I I I I I I 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME ... | |||
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 i-I- | |||
CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR 3.2 CURVE A: ALL SCRAM INSERTION TIMES I-26, 2.61 ... | |||
23, 2.84 3.0 | |||
.E | |||
- i- | |||
'.:i CURVEB: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE C> 2.8 26, 2.61 " A I-C: | |||
PER SR 3.7.6.1 AND 3.7.6.2 | |||
~ | |||
23, 2.84 \ B I- | |||
...cu I I G) 2.6 C ' I Cl. | |||
0 CURVEC: 126.01, 2.41 USED IN DETERMINING MFLCPR a: 26, 2.59 D.. 2.4 0 | |||
23, 2.84 ... ..... r | |||
~ -... ... _ | |||
2.2 I 1........ ......... 140, 2.071 lso, 2.011 I 26.01, 2.23 I ~ ~ | |||
2.0 -... 1.86: | |||
............. ... ...: 60, | |||
............._ 1.19: | |||
1 1.8 1 40, 1.90 1 ~ | |||
...... _A- H10, I I .___ | |||
,so, 1.89, | |||
--- ........... *-iso, 1.73 ,_: 90, 1.62 ~ | |||
1.6 :so, 1.71: | |||
B | |||
-- --- --. --- .... 1100, 1.56 I | |||
:10, 1.ss: | |||
1.4 -l | |||
==REFERENCE:== | |||
T.S. 3.2.2 I :so, 1.57: 100, 1.421 I I 90, 1.52 I | |||
------- I 1.2 10 20 30 40 50 60 70 80 90 100 Core Power (% RATED) | |||
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-2 | |||
PL-NF-23-002 Rev. 1 Page 15 of 72 Main Turbine Bypass Inoperable | |||
SSES UNIT 2 CYCLE 22 2.5 LEGEND 2.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME -- | |||
2.3 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I I I 2.2 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE - | |||
INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 2.1 130, 2.061 USED IN DETERMINING MFLCPR | |||
.E I | |||
- 2.0 | |||
:::i C) | |||
C: | |||
:;:; 1.9 l40, 1.86l cu Cl) | |||
C. | |||
0 1.8 " | |||
a: | |||
fl. | |||
0 | |||
:iE 1.7 I I 1.6 ,40.1, 1.561 | |||
- A 1.5 B 1.4 I | |||
==REFERENCE:== | |||
T.S. 3.7.6 and 3.2.2 I -1108, 1.341 1.3 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) "'U "'U ru (C | |||
rI MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD z | |||
_,_ "'Tl I | |||
MAIN TURBINE BYPASS INOPERABLE | |||
: 0) ~ N TWO LOOP OPERATION (BOC TO EOC) 0 CD 'f ATRIUM'-10 AND ATRIUM' 11 FUEL ~<o | |||
-....J" 0 FIGURE 5.2-3 N ->-N | |||
SSES UNIT 2 CYCLE 22 4.3 LEGEND -,... | |||
4.1 CURVE A: CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 26, 3.16 INSERTION TIME 3.9 23, 3.51 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.7 CURVE 8: CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3.5 26, 3.16 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 3.51 \A -,... | |||
3.3 \ B CURVE D: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR - | |||
..... REALISTIC AVERAGE SCRAM INSERTION TIME | |||
.E CURVEC: | |||
::i 3.1 ' | |||
26, 2.59 Cl SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE - | |||
C: 23,2.84 | |||
~ 2.9 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 - | |||
...m Cl) | |||
C. '\ | |||
0 2.7 CURVED: ,-c | |||
~ 26, 2.59 \ USED IN DETERMINING MFLCPR | |||
: a. 23, 2.84 D ~ | |||
0 2.5 I 26.01, 2.44: | |||
~ ~ | |||
2.3 | |||
..... ......... 140, 2.01: | |||
..... i-.... 150, 2.071 2.1 : 26.01, 2.25 I | |||
~------- -- ... _-... ... _ : 60, 1.86 1.9 A_ ~ 70, 1.82 I | |||
............ 180,1.741 I 90, 1.69 ~ | |||
140, 1.901 ............. | |||
1.7 150, 1.90 1 *-------- ----- *------ I100, 1.691 | |||
: 60, 1.71 ~ | |||
B_ H70, 1.66 I 1100, 1.551 1.5 | |||
] | |||
==REFERENCE:== | |||
T.S. 3.7.6 and 3.2.21 I 80, 1.58 I I 90, 1.55 I 1.3 10 20 30 40 50 60 70 80 90 100 Core Power(% RATED) -0 ""'CJ ni r (0 I MCPR OPERATING LIMIT VERSUS CORE POWER CD z | |||
....>. -;n MAIN TURBINE BYPASS INOPERABLE | |||
--..J :::0 N TWO LOOP OPERATION (BOC TO EOC) 0 CD Cf | |||
....., < 0 ATRIUM'-10 AND ATRIUM' 11 FUEL --..J* 0 N....,. N FIGURE 5.2-4 | |||
PL-NF-23-002 Rev. 1 Page 18 of 72 EOC-RPT Inoperable | |||
SSES UNIT 2 CYCLE 22 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 I | |||
2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
.. 2.1 | |||
"§ I 30.0, 2.06 I - | |||
:::i K USED IN DETERMINING MFLCPR Cl 2.0 C: | |||
L 11:S | |||
...a., 1.9 C. 140.0, 1.861 0 | |||
0::: "' | |||
0.. 1.8 | |||
(.) | |||
~ | |||
1.7 1.6 1.5 140.1, 1.411 | |||
~ | |||
1.4 A B | |||
1.3 H | |||
==REFERENCE:== | |||
T.S. 3.3.4.1 and 3.2.2 : | |||
1108.0, 1.221 1.2 30 40 50 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) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-5 | |||
SSES UNIT 2 CYCLE 22 4.3 LEGEND 4.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.9 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.7 CURVE A: | |||
26, 2.61 - | |||
23,2.84 CURVE C: CORE POWER:$; 26% AND CORE FLOW:$; 50 MLBM/HR 3.5 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME - | |||
3.3 f- CURVES: CURVE D: CORE POWER:$; 26% AND CORE FLOW:$; 50 MLBM/HR | |||
.... 26, 2.61 REALISTIC AVERAGE SCRAM INSERTION TIME 23, 2.84 3.1 | |||
*e::i C> | |||
C: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE | |||
:.:; 2.9 .... CURVEC: PER SR 3.7.6.1 AND 3.7.6.2 l'G - | |||
Cl) | |||
.... 26, 2.59 I | |||
C. 23,2.84 0 2.7 0:: | |||
As USED IN DETERMINING MFLCPR ll.. | |||
0 CURVED: _D_ | |||
t 2.5 7 26.01, 2.41 | |||
~ 26, 2.59 23, 2.84 ...... ~ | |||
2.3 | |||
......... 140, 2.12LJ , 2 _12 1 2.1 26.01, 2.231 | |||
... .... -------50 | |||
............. -... .........I 60, 1.99 1A_ 770, 1.901 1.9 ------ | |||
--........ ...... ... _ 180,1.741 190, 1.731- | |||
:40, 1.90: - ...... | |||
................ 1100, 1.731 1.7 150, 1.891 *--------------- | |||
I 60, 1.72 1100, 1.56 1.5 B_ J10, 1.67L I | |||
"-180, 1.60 1 190, 1.571 | |||
==REFERENCE:== | |||
T.S. 3.3.4.1 and 3.2.21 I I 1.3 10 20 30 40 50 60 70 80 90 100 Core Power (% RATED) ""O ""O ru (C | |||
rI MCPR OPERATING LIMIT VERSUS CORE POWER (I) z I\.) 71 EOC-RPT INOPERABLE 0 ;:oN TWO LOOP OPERATION (BOC TO EOC) 0 CD Cf ATRIUM'-10 AND ATRIUM' 11 FUEL - <o | |||
-....i* 0 I\.)->. I\.) | |||
FIGURE 5.2-6 | |||
PL-NF-23-002 Rev. 1 Page 21 of 72 Backup Pressure Regulator Inoperable | |||
SSES UNIT 2 CYCLE 22 2.6 I LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.4 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 I I I I 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.1 -I 30.0, 2.06 : | |||
*e:J.... I I I I USED IN DETERMINING MFLCPR Cl 2.0 ~ | |||
C: | |||
~ | |||
...cu Q) 1.9 I 40.0, 1.86 I C. | |||
0 0:: 1.8 a.. | |||
0 | |||
~ | |||
1.7 1.6 1.5 140.1, 1.411 1.4 A B | |||
1.3 1 | |||
==REFERENCE:== | |||
T.S. 3.7.8 and 3.2.2: | |||
1.2 | |||
- I 108.0, 1.221 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-7 | |||
SSES UNIT 2 CYCLE 22 4.0 I I I I I 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE A: CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 26, 2.61 23, 2.84 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3.2 ALL SCRAM INSERTION TIMES CURVEB: | |||
.... 3.0 | |||
.E 26, 2.61 | |||
::i 23, 2.84 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES C) 2.8 ,. A r::: ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
:;::; CURVEC: \. B ca | |||
... I I --. --. I Cl) 2.6 26, 2.59 --c c.. 23,2.84 USED IN DETERMINING MFLCPR 0 | |||
0:: | |||
' 126.01, 2.411 | |||
: a. 2.4 0 | |||
~ ..._ ... ..... | |||
2.2 140, 2.07 1 | |||
- -...... _ 150, 2.071 26.01, 2.23 I 2.0 | |||
...... l 60, 1.86 lA- H10,1.19: | |||
40, 1.971 ____,,;,,:: | |||
1.8 : 50, 1.93: ~--------- | |||
.......... r-.-. ........ ,....,,. ~80,1.73: | |||
: 90, 1.62t-I 60, 1.83 I ....... ~ . | |||
1.6 B 1100, 1.561 | |||
~---- *------ | |||
I i 70, 1.65: 1180, 1.57 I 1.4 ~ I100, 1.421 | |||
==REFERENCE:== | |||
T.S. 3.7.8 and 3.2.2J I 90, 1.521 1.2 10 20 30 40 50 60 70 80 90 100 Core Power(% RATED) | |||
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-8 | |||
PL-NF-23-002 Rev. 1 Page 24 of 72 One TSV or TCV Closed | |||
SSES UNIT 2 CYCLE 22 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 2.2 H 30.0, 2.16: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.1 I | |||
*e... 2.0 USED IN DETERMINING MFLCPR J I C) | |||
C: | |||
' 140.0, 1.941 | |||
:;:; 1.9 | |||
...cu Cl) a. | |||
0 1.8 0:: | |||
ll.. | |||
0 | |||
:ii: 1.7 140.1, 1.591 1.6 A | |||
B 1.5 1.4 | |||
- I10s.o, 1.31 I 1.3 H | |||
==REFERENCE:== | |||
T.S. 3.2.2 and TRM 3.3.71 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* | |||
TWO LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-9 | |||
*Operation with one TSV or TCV closed is only supported at power levels s; 75% rated power | |||
SSES UNIT 2 CYCLE 22 4.0 I I I I 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME - | |||
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 - CURVE A: | |||
26, 2.61 CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR - | |||
-- 23, 2.84 i-- | |||
3.2 -- ALL SCRAM INSERTION TIMES 3.0 - CURVEB: | |||
.....E 26, 2.61 J 23, 2.84 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE C> 2.8 A s:::: | |||
--- ' PER SR 3.7.6.1 AND 3.7.6.2 - | |||
I'll B- - | |||
a, 2.6 CURVEC: -C C. | |||
- 26, 2.59 - | |||
0 - 23, 2.84 126.01, 2.41 J-i USED IN DETERMINING MFLCPR ct: 2.4 ll. - | |||
0 r | |||
:§: | |||
2.2 2.071 A | |||
... __________ ISO, 2.071 | |||
- ....... -... ... _-... ... ... :4o, 126.01, 2.231 - ............... ......... | |||
2.0 | |||
............... ...... ... ... : 60, 1.86: | |||
... , .......... ___ 70, 1.791 1.8 :40, 1.90 B I so, 1.89 I ---.......... - - - - - 175, 1.761 1.6 :so, 1.71: 175, 1.61 I 70, 1.65: | |||
1.4 7 | |||
==REFERENCE:== | |||
T.S. 3.2.2 and TRM 3.3.7: | |||
1.2 10 20 30 40 50 60 70 80 Core Power (% RATED) | |||
MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-10 | |||
PL-NF-23-002 Rev. 1 Page 27 of 72 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds) | |||
Position 45 0.470 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-23-002 Rev. 1 Page 28 of 72 6.0 LINEAR HEAT GENERATION RA TE (LHGR) 6.1 References Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 6.2 Description The maximum LHGR for ATRIUM'-10 and ATRIUM' 11 fuel shall not exceed the LHGR limits determined from Figure 6.2-1A and Figure 6.2-18, respectively. | |||
The LHGR limits in Figures 6.2-1A and 6.2-1 Bare valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. | |||
To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided in the following figures: | |||
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 6.2-3: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 6.2-5: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel c) EOC-RPT Inoperable Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 6.2-7: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel d) Backup Pressure Regulator Inoperable Figure 6.2-8: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel | |||
PL-NF-23-002 Rev. 1 Page 29 of 72 Figure 6.2-9: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-10: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 6.2-11: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel The LHGR limits in Figures 6.2-1A/6.2-1 Bare valid for both Two Loop and Single Loop operation and are fuel type specific. The LHGR limit multipliers in Figures 6.2.2 through 6.2.11 are valid for both Two Loop and Single Loop operation and are applicable to both ATRIUM'-10 and ATRIUM' 11 Fuel. | |||
SSES UNIT 2 CYCLE 22 16.0 I I | |||
I I | |||
I I I I i--,,--.--r--.1I I I 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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------~-------+-------~--------~-------~---- SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 126, :o.4o I l _____ j _______ l_______ j____ ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
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1 - - - - 1I I I I I I I I I I I I | |||
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::I I I I I I I I I I I I I | |||
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POWER DEPENDENT LHGR LIMIT MULTIPLIER EOC-RPT INOPERABLE ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 6.2-7 | |||
PL-NF-23-002 Rev. 1 Page 41 of 72 Backup Pressure Regulator Inoperable | |||
SSES UNIT 2 CYCLE 22 1.10 I I | |||
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: 0) rI co FLOW DEPENDENT LHGR LIMIT MULTIPLIER (1) z | |||
.j:s. | |||
tl I | |||
BACKUP PRESSURE REGULATOR INOPERABLE N N ATRIUM'-10 AND ATRIUM' 11 FUEL 0 ?;,1(f | |||
<O 0 FIGURE 6.2-8 --..J . | |||
N ->.N | |||
SSES UNIT 2 CYCLE 22 1.10 I I | |||
I I I I LEGEND I I I I I | |||
----,--------r--------r--------T--------r------- | |||
1 I I I I I I I I I I I I I I I I I I I CURVE A: BASE CURVE I I I I I 1.00 1 | |||
----,--------r-------~-------T--------r------ | |||
I I I I I I I I I I I I I I I I CURVE B: CORE POWER :'.5: 26% AND CORE FLOW :'.5: 50 MLBM/HR I I I 1 I I | |||
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==REFERENCE:== | |||
: T.S. 3.2.3 and~ 3.7.8~ | |||
I I I I I I I I I I I I I I I I I I I I I I I I I 0.50 1 I I I I I I I | |||
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-r*------~--------~-------~------ SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I I I I I I I I ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 26, 0.39 I I I I I I I I | |||
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I 0.30 20 30 40 50 60 70 80 90 100 Core Power(% RATED) lJ lJ | |||
: 0) rI co POWER DEPENDENT LHGR LIMIT MULTIPLIER CD z"'Tl | |||
~ I BACKUP PRESSURE REGULATOR INOPERABLE w ::o"' | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL 0 CD 'f | |||
<O FIGURE 6.2-9 ---.J 0 I\.) _,_ I\.) | |||
PL-NF-23-002 Rev. 1 Page 44 of 72 One TSV or TCV Closed | |||
SSES UNIT 2 CYCLE 22 1.10 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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==REFERENCE:== | |||
T.S. 3.2.3 and TRM 3.3.7 lL I I I I I | |||
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I I I I I I I I I I I I I I I I I I I I I I I I | |||
-j30 , o 35j----~-------~--------!--------~-------~--------i-------..:..-------!--------~-------~--------i-------..:..-------!--------~------- | |||
* I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) | |||
-0 -0 ni rI co FLOW DEPENDENT LHGR LIMIT MULTIPLIER CD z | |||
..i:,.. "Tl ONE TSV OR TCV CLOSED* I 01 ::::0 N ATRIUM'-10 AND ATRIUM' 11 FUEL 0 CD Cf FIGURE 6.2-10 <O | |||
'1 . 0 | |||
*Operation with one TSV or TCV closed is only supported at power levels :!. 75% rated power N ...>.N | |||
SSES UNIT 2 CYCLE 22 1.10 I I | |||
I I I I LEGEND I I I I | |||
--r----------~-----------T----------~----------- | |||
1 I I I I I I I I I I I I I I I CURVE A: BASE CURVE I I I I 1.00 --r----------,-----------~-----------,----------- | |||
1 I I I I I I I I I I I CURVE B: CORE POWER ::s;; 26% AND CORE FLOW ::s;; 50 MLBM/HR I I I I I I I I | |||
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;- --------r---------t----------r----------i-----------t1 R~FEREN~E: T.S. 3.2.3 and TRM 3.3.! 1-- | |||
* I I I I I I I I I I 0.50 t --------r----------t---------r----------1-----------r----------1-----------1 USED IN DETERMINING FDLRX 1_-_- | |||
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_____ .,_ --------~----------~-----------~----------~-----------~----------~-----------------,-------,------,----~ | |||
: : : : I I I B l26, o.~o I ______ j_________ j __________ j SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 0.40 | |||
' I : : : ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 0.35 :26,I 0.39 ! ! ! | |||
---------------------------------------------~--------=-=-=-=-=-=,~-----=-=-=-=--=-==-~=----=-=--=-=-=-=---~=--=-=-=-=-=-----,--=-=-=-=---------~-~~=-=-=-------------~==---------_- | |||
I I I I I I I I I I ___, | |||
I 23, 0.35 ~ I ~ : : : : : : : : | |||
. . I I I I I I I I I I I I I I I I I I I I I 0.30 20 30 40 50 60 70 80 Core Power (% RATED) | |||
POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 6.2-11 | |||
PL-NF-23-002 Rev. 1 Page 47 of 72 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 References Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and f) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. | |||
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated. | |||
PL-NF-23-002 Rev. 1 Page 48 of 72 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value( 1> Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 117.4 117.0 High Power Range - Upscale 107.6 107.2 (1 > Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of RATED THERMAL POWER. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level. | |||
Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR (2,3,4) | |||
(% of Rated) | |||
~ 28 and< 90 < 1.78 | |||
~ 90 and< 95 < 1.47 | |||
::: 95 < 1.68 | |||
( 2> Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and one TCV/TSV closed. | |||
( 3> Applicable to both Two Loop and Single Loop Operation. | |||
(4> Applicable to both ATRI U M-10 and ATRIUM 11 Fuel. | |||
PL-NF-23-002 Rev. 1 Page 49 of 72 8.0 RECIRCULATION LOOPS -SINGLE LOOP OPERATION 8.1 References Technical Specification 3.2.1, 3.2.2, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 8.2 Description APLHGR The APLHGR limit for ATRIUM'-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1A. The APLHGR limit for ATRIUM' 11 fuel shall be equal to the APLHGR Limit from Figure 8.2-1 B. | |||
The APLHGR limits in Figures 8.2-1A and 8.2-1 Bare 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 and ATRIUM' 11) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. | |||
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel b) Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel | |||
PL-NF-23-002 Rev. 1 Page 50 of 72 d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-1 O: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-11: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel The MCPR limits in Figures 8.2-2 through 8.2-11 are applicable to both ATRIUM'-10 and ATRIUM' 11 Fuel, are valid only for Single Loop operation, and support power levels up to 67.2% RATED THERMAL POWER and core flows up to 52 Mlbm/hr. These conditions conservatively bound Single Loop Operation in accordance with Technical Specification 3.4.1. | |||
Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0. | |||
RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0. | |||
SSES UNIT 2 CYCLE 22 16.00 I I | |||
I I | |||
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: 0) rI CQ AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS CD z "Tl AVERAGE PLANAR EXPOSURE - SINGLE LOOP OPERATION 01 I | |||
_,._ ;oN ATRIUM'-10 FUEL 0 CD Cf FIGURE 8.2-1A <O | |||
--..J 0 N _,._ N | |||
SSES UNIT 2 CYCLE 22 16.00 I I | |||
I I | |||
I I I I I I I I I I I I I I I 1 | |||
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I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 4.00 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU) | |||
""'O ""'O m | |||
(0 rI AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS CD z AVERAGE PLANAR EXPOSURE -SINGLE LOOP OPERATION (J1 71 N :::0 N ATRIUM' 11 FUEL 0 CD Cf FIGURE 8.2-1 B - | |||
---i* | |||
<o 0 N _._ N | |||
PL-NF-23-002 Rev. 1 Page 53 of 72 Main Turbine Bypass / EOC-RPT / | |||
Backup Pressure Regulator Operable | |||
SSES UNIT 2 CYCLE 22 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 FOUR BYPASS VALVES 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
:::i ------ | |||
Cl C: 130.0, 2.061 - | |||
cu | |||
,_ r---,.....__ I Q) 2.0 USED IN DETERMINING MFLCPR I | |||
: 0. -----. I I 0 140.0, 1.861 0::: ~ | |||
a.. | |||
(.) 1.8 | |||
~ | |||
1.6 | |||
.A B 1.4 ' 152.0, 1.381 140.1, 1.41 I 1.2 | |||
==REFERENCE:== | |||
T.S. 3.4.1 and 3.2.21 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR) | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-2 | |||
SSES UNIT 2 CYCLE 22 4.0 I I I I LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE A: | |||
26, 2.63 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 23, 2.86 ALL SCRAM INSERTION TIMES 3.2 I I I | |||
.... SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES | |||
"§ 3.0 - CURVE B: | |||
:J 26, 2.63 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C) - 23, 2.86 C: \. A | |||
;; 2.8 ,- | |||
ltS Cl) | |||
\. B I USED IN DETERMINING MFLCPR I | |||
C. CURVE C: C I | |||
0 2.6 26, 2.61 a::: 23, 2.86 : 26.01, 2.43 : | |||
a. | |||
(.) | |||
:§i: 2.4 ....... | |||
--... ...... 40, 2.09 2.2 ..........__ ...... ....... A- i5o, 2.09: | |||
126.01, 2.251 | |||
------ -- ,so, 2.00 67.2, 2.00, 2.0 140, 2.001 8- i 50, 2.00: ,so, 2.00 67.2, 2.00 I 1.8 1.6 H | |||
==REFERENCE:== | |||
T.S. 3.4.1 and 3.2.2: | |||
1.4 10 20 30 40 50 60 70 80 Core Power (% RATED) | |||
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-3 | |||
PL-NF-23-002 Rev. 1 Page 56 of 72 Main Turbine Bypass Inoperable | |||
SSES UNIT 2 CYCLE 22 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 I I | |||
~ SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS E VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 | |||
::J 2.2 - | |||
C) | |||
C: 130, 2.061 | |||
!'Cl r----......... USED IN DETERMINING MFLCPR Cl> 2.0 I | |||
: a. ----... | |||
0 | |||
~ ~ I40, 1.86 I a. | |||
0 1.8 | |||
~ | |||
1.6 A-8 152, 1.521 140.1, 1.561 1.4 I | |||
==REFERENCE:== | |||
T.S. 3.4.1, 3.7.6, and 3.2.2 j 1.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR) ""'CJ ""'CJ ru (0 | |||
rI CD z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CJ1 77 MAIN TURBINE BYPASS INOPERABLE -...J ::0 N SINGLE LOOP OPERATION (BOC TO EOC) 0 CD Cf | |||
- <o | |||
-...J* 0 ATRIUM'-10 AND ATRIUM' 11 FUEL N -"- N FIGURE 8.2-4 | |||
SSES UNIT 2 CYCLE 22 4.4 I I I I LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.0 CURVE A: INSERTION TIME 26, 3.18 3.8 23,3.54 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER:;;; 26% AND CORE FLOW:;;; 50 MLBM/HR 3.6 A CURVEB: \. MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 3.18 _s \ | |||
3.4 23, 3.54 CURVE D: CORE POWER:;;; 26% AND CORE FLOW:;;; 50 MLBM/HR | |||
.... \ | |||
.E REALISTIC AVERAGE SCRAM INSERTION TIME | |||
::J 3.2 I I I Cl CURVEC: | |||
C: 26, 2.61 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS | |||
~ 3.0 23, 2.86 | |||
...cu Cl) | |||
VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 Cl. | |||
-c \. | |||
0 2.8 I 0:: CURVED: | |||
\. USED IN DETERMINING MFLCPR | |||
: a. -o \ | |||
0 2.6 26, 2.61 r | |||
::!?: 23, 2.86 I 2s.01, 2.46 2.4 2.2 -, , ... 140, 2.09 A- H5o, 2.09: | |||
: 26.01, 2.27 : | |||
--......... -- ---- - 1so, 2.00 67.2, 2.ooj 2.0 | |||
:4o, 2.00 8- H5o, 2.00: :so, 2.00 67.2, 2.00! | |||
1.8 1.6 7 | |||
==REFERENCE:== | |||
T.S. 3.4.1, 3.7.6, and 3.2.2 : | |||
1.4 10 20 30 40 50 60 70 80 Core Power(% RATED) | |||
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-5 | |||
PL-NF-23-002 Rev.1 Page 59 of 72 EOC-RPT Inoperable | |||
SSES UNIT 2 CYCLE 22 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 I I I | |||
.... SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES | |||
.E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
:J 2.2 CJ C: 130, 2.061 | |||
...m ...........__ USED IN DETERMINING MFLCPR CD 2.0 I I 0.. ----.. | |||
0 a:: 140, 1.861 a. | |||
~ | |||
0 1.8 | |||
~ | |||
1.6 A B 1.4 I 52, 1.38 I 140.1, 1.41 I 1.2 | |||
==REFERENCE:== | |||
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR) ""'O ""'O Ill rI (Cl CD z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW | |||
: 0) 71 EOC-RPT INOPERABLE O :::0 N SINGLE LOOP OPERATION (BOC TO EOC) 0 CD 'f | |||
-<o ATRIUM'-10 AND ATRIUM' 11 FUEL -...J" 0 N ->. N FIGURE 8.2-6 | |||
SSES UNIT 2 CYCLE 22 4.4 LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.0 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME | |||
===3.8 CURVEA=== | |||
CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR 3.6 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 2.63 23, 2.86 3.4 CURVE D: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR | |||
.E REALISTIC AVERAGE SCRAM INSERTION TIME CURVE 8: | |||
:::i 3.2 26, 2.63 Cl C: 23, 2.86 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES | |||
:;:; 3.0 | |||
...cu ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (I) | |||
C. CURVEC: '- A 0 2.8 0:: 26, 2.61 B | |||
: a. 23, 2.86 -c USED IN DETERMINING MFLCPR 0 2.6 | |||
~ | |||
D 2.43: | |||
_ : 26.01, | |||
===2.4 CURVED=== | |||
26, 2.61 ~ | |||
23, 2.86 - ... ...... 40, 2.141 A_ LJ50, 2.141 2.2 - | |||
r--,...,__ | |||
I 26.01, 2.25 1 : 60, 2.01 | |||
--............. -- - ........... __ 67.2, 2.001 2.0 | |||
:4o, 2.00 8- rl 50, 2.00 I 160, 2.00 67.2, 2.001 1.8 1.6 | |||
==REFERENCE:== | |||
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 1.4 10 20 30 40 50 60 70 80 Core Power(% RATED) | |||
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-7 | |||
PL-NF-23-002 Rev. 1 Page 62 of 72 Backup Pressure Regulator Inoperable | |||
SSES UNIT 2 CYCLE 22 3.0 LEGEND 2.8 - | |||
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME ---- | |||
I I 2.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
*e... | |||
J 2.2 . | |||
Cl USED IN DETERMINING MFLCPR C: 130, 2.061 I'll (I) 2.0 | |||
: a. ---... | |||
0 0::: ~ 140, 1.861 fl. | |||
0 1.8 | |||
~ | |||
1.6 A B 1.4 I 52, 1.38 I 140.1, 1.41 I 1.2 7 | |||
==REFERENCE:== | |||
T.S. 3.4.1, 3.7.8, and 3.2.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR) ""'D ""'D n:, r;- | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW cg z | |||
: 0) -;n BACKUP PRESSURE REGULATOR INOPERABLE W ;;o N SINGLE LOOP OPERATION (BOC TO EOC) 0 CD Cf 0 | |||
0 ATRIUM'-10 AND ATRIUM' 11 FUEL ---.J"< | |||
N ....,._ N FIGURE 8.2-8 | |||
SSES UNIT 2 CYCLE 22 4.0 LEGEND 3.8 ,---- | |||
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 - CURVE A: | |||
CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR | |||
- 26, 2.63 | |||
_ 23,2.86 ALL SCRAM INSERTION TIMES 3.2 3.0 .... CURVEB: | |||
26, 2.63 | |||
..,. 23, 2.86 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES | |||
\. A ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 B I | |||
'""CURVEC: I | |||
.E.. C | |||
::i 2.6 ..,. 26, 2.61 USED IN DETERMINING MFLCPR C> .... 23, 2.86 C | |||
'' I 26.01, 2.43 I I'll | |||
... 2.4 Cl) c.. | |||
0 ........... -... ...... _ | |||
0::: 2.2 -r--,....__ ...... ... _ :40, 2.09 A H5o, 2.09: | |||
: a. I 26.01, 2.25: | |||
0 s1.2, 2.00 I | |||
~ --............. --------- ....................... _ : so, 2.00h 2.0 | |||
:40, 2.00 B H5o, 2.00: :so, 2.00 67.2, 2.001 1.8 | |||
] | |||
==REFERENCE:== | |||
T.S. 3.4.1, 3.7.8, and 3.2.2 I 1.6 1.4 10 20 30 40 50 60 70 80 Core Power(% RATED) | |||
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-9 | |||
PL-NF-23-002 Rev. 1 Page 65 of 72 One TSV or TCV Closed | |||
SSES UNIT 2 CYCLE 22 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM - | |||
INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME - | |||
2.4 | |||
~ SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
::i 2.2 :-(30,2.16 1 - | |||
Cl C: | |||
(1:1 ~ ............ | |||
Q) 2.0 I USED IN DETERMINING MFLCPR I | |||
: a. 140, 1.941 I I 0 | |||
0:: | |||
a. | |||
0 1.8 | |||
:1!: | |||
A B 1.6 I52, 1.551 140.1, 1.591 1.4 1.2 | |||
==REFERENCE:== | |||
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR) | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOG) | |||
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-10 | |||
SSES UNIT 2 CYCLE 22 4.0 I 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 A: | |||
26, 2.63 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 23, 2.86 ALL SCRAM INSERTION TIMES 3.2 I I I 3.0 CURVE 8: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
*-Je 26, 2.63 C) r::: 23, 2.86 \. A 2.8 cu Cl) | |||
USED IN DETERMINING MFLCPR a. | |||
- CURVEC: C~B I I 0 2.6 26, 2.61 0::: 23, 2.86 | |||
: n. 1 26.01, 2.43 1 0 . | |||
:!!: 2.4 ......... | |||
~- -.... ........ | |||
2.2 .... ........... 40, 2.09 A- ~ 50, 2.os: | |||
: 26.01, 2.25 : | |||
r---....... :so, 2.00 67.2, 2.001 2.0 | |||
:4o, 2.00 B- H5o, 2.00: 1 so, 2.00 67.2, 2.00 I 1.8 1.6 H | |||
==REFERENCE:== | |||
T.S. 3.4.1, 3.2.2, and TRM 3.3.7: I I 1.4 10 20 30 40 50 60 70 80 Core Power(% RATED) -0 -0 m | |||
(0 rI (D z MCPR OPERATING LIMIT VERSUS CORE POWER | |||
: 0) -;n ONE TSV OR TCV CLOSED -...J :::0 I\.) | |||
SINGLE LOOP OPERATION (BOC TO EOC) 0 CD Cf | |||
- <o | |||
-...J" 0 ATRIUM'-10 AND ATRIUM' 11 FUEL I\.)....,,_ I\.) | |||
FIGURE 8.2-11 | |||
PL-NF-23-002 Rev. 1 Page 68 of 72 9.0 POWER/ FLOW MAP 9.1 References Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and 11 of the Power/ Flow map, Figure 9.1. | |||
If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power/ Flow map is considered an immediate exit region. | |||
If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power 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-23-002 Rev. 1 Page 69 of 72 f )tf-.,J 120 120 | |||
==Purpose:== | |||
I It,, I,, | |||
I I I UNIT2 | |||
==:r,n,,:TT. | |||
--:-r- | |||
...cJ_--.,_~_-,J!:: | |||
-r-. --r-1-- | |||
110 110 Initial / Date: ' ' | |||
STABILITY REGION I IF OPRM INOPERAaLE IMM5DIATELY SCRAM IAW APPLICABLE PROCEDURE. | |||
100 100 IF OPRM OPERABLE IMMEDIATfLY EXITIAW APPLICABLE PROCEDURE. | |||
STABILITY REGION II IMMEDIATELY EXIT IAW APPLICABLE PROCEDURE. ITiillill 90 RESTRICTED REGION I I I I I \ I 90 IF ABOVE MELLLABOUNDARY, --H--H-- +++ | |||
IMMEDIAlELY EXITIAW APPLICABLE | |||
--f-~--f-4-- -1 lni-* | |||
PROCEDURE. I I I I I 80 .j..!~:=!':=!=:9:;=f=!':=!=:9:==;:=F=!=:91==;:=;::=i=9:==;1=;::=:F-l-+:-+-1 80 | |||
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20 r-;;;::;;:;;:;;'7-i--4--i-+¥--l---+-li-+-l--l-./-i--+-i-i--l-+--i-\-i.-l--l--i-i--i-i--J...+-i-i--+-J.-i-i--i-++.+-i-i--+-J.-i-+-i-liffl-20 | |||
- --r-1-+-1-- -r-1--r- --r-t-t-t- --}--:--+-+- -+-~-+- :m | |||
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-, 30 ~--~-~-- -~--~-~--~- --~-t--~-+- -i-t-i-~-- -~--~-~-- ~ | |||
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10 10 | |||
--~-4--~--l--- -~-+-4--~- --r--}--r--T- -T-"1--T--,-- --,--,---,-- I | |||
,.-t: ::~:i:~:~:: :~::~:r:~: ::~:~::~:~:: :~:l:r:~: ::~:i::~:r :i:i:rl: :r:r:r: | |||
t I I I I l I l I I I l I I 1I I I I 0 | |||
I I I I I I 1 I I I t I I I I I I I I I I I I I I I I 0 | |||
j 0 10 20 30 40 50 60 -70 80 90 100 110 Total core Flow (Mlbm/hr) | |||
Figure 9.1 SSES Unit 2 Cycle 22 Power/ Flow Map | |||
PL-NF-23-002 Rev. 1 Page 70 of 72 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPRss.s3/4 Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below: | |||
= 1.12 | |||
= 16 Fp = 60 Mlbm / hr | |||
PL-NF-23-002 Rev. 1 Page 71 of 72 | |||
==11.0 REFERENCES== | |||
11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: | |||
: 1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984. | |||
: 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-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983. | |||
: 5. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987. | |||
: 6. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986. | |||
: 7. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc., | |||
September 1986. | |||
: 8. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995. | |||
: 9. EMF-2209(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009. | |||
: 10. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A), | |||
"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," | |||
Siemens Power Corporation, February 1998. | |||
: 11. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999. | |||
: 12. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis - | |||
Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000. | |||
PL-NF-23-002 Rev. 1 Page 72 of 72 | |||
: 13. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996. | |||
: 14. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005. | |||
: 15. BAW-10247PA, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors," AREVA, Inc., April 2008. | |||
: 16. ANP-10340P-A, Revision 0, "Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods," Framatome Inc., May 2018. | |||
: 17. ANP-10335P-A, Revision 0, "ACE/ATRIUM-11 Critical Power Correlation," | |||
Framatome Inc., May 2018. | |||
: 18. ANP-10300P-A, Revision 1, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios," | |||
Framatome Inc., January 2018. | |||
: 19. ANP-10332P-A, Revision 0, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios," | |||
Framatome Inc., March 2019. | |||
: 20. ANP-10333P-A, Revision 0, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA)," | |||
Framatome Inc., March 2018. | |||
: 21. ANP-10307PA, Revision 0, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors," AREVA, Inc., June 2011. | |||
: 22. BAW-10247P-A Supplement 1P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 1: | |||
Qualification of RODEX4 for Recrystallized Zircaloy-2 Cladding," AREVA Inc., | |||
April 2017. | |||
: 23. BAW-10247P-A Supplement 2P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 2: | |||
Mechanical Methods," Framatome Inc., August 2018.}} | |||
Latest revision as of 10:38, 17 July 2023
| ML23186A032 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/05/2023 |
| From: | Casulli E Susquehanna |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| PLA-8078 | |
| Download: ML23186A032 (1) | |
Text
TALEN~
Edward Casulli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Be1wick, PA 18603 Tel. 570.542.3795 Fax 570.542.1504 Edward. Casulli@talenenergy.com ENERGY July 05, 2023 Attn: Document Control Desk 10 CPR 50.4 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION SUBMITTAL OF UNIT 2 CYCLE 22 CORE OPERATING LIMITS REPORT, REVISION 1 PLA-8078 Docket No. 50-388
Reference:
"Susquehanna Steam Electric Station Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)," dated March 30, 2023 (ADAMS Accession No. ML23089A361).
Susquehanna Steam Electric Station (SSES) Technical Specification Section 5.6.5 requires that the Core Operating Limits Report (COLR), including any mid-cycle supplements or revisions, be provided upon issuance to the NRC in accordance with 10 CPR 50.4. Pursuant to this requirement, the SSES Unit 2 Cycle 22 COLR, Revision 1, is provided in the attachment.
Revision Owas previously provided in the reference. Revision 1 is a result of updated licensing analysis as noted within the COLR Revision Description Index. All changes are denoted by revision bars in the margin of the report.
There are no new or revised commitments contained in this submittal.
Should you have any questions regarding this submittal, please contact Ms. Melisa Krick, Manager- Nuclear Regulatory Affairs, at (570) 542-1818.
E. Casulli
Attachment:
SSES Unit 2 Cycle 22 COLR, Revision 1
Document Control Desk PLA-8078 Copy: NRC Region I Mr. C. Highley, NRC Senior Resident Inspector Ms. A. Klett, NRC Project Manager Mr. M. Shields, PA DEP/BRP
Attachment to PLA-8078 SSES Unit 2 Cycle 22 COLR, Revision 1
PL-NF-23-002 Rev. 1 Page 1 of 72 Susquehanna SES Unit 2 Cycle 22 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering June 2023
PL-NF-23-002 Rev. 1 Page 2 of 72 CORE OPERA TING LIMITS REPORT REVISION DESCRIPTION INDEX REV AFFECTED NO. SECTIONS DESCRIPTION / PURPOSE OF REVISION 0 ALL Issuance of this COLR is in support of Unit 2 Cycle 22 operation.
1 ALL Issuance of this COLR revision is to support change in LHGRFACr for base case, EOC-RPT INOP, and Backup Pressure ReQulator INOP conditions.
FORM NFP-QA-008-2, Rev. 2
PL-NF-23-002 Rev. 1 Page 3 of 72 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 22 CORE OPERATING LIMITS REPORT Table of Contents
1.0 INTRODUCTION
........................................................................................................... 4 2.0 DEFINITIONS ............................................................................................................... 5 3.0 SHUTDOWN MARGIN .................................................................................................. 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ....................... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) ............................................................ 10 6.0 LINEAR HEAT GENERATION RATE (LHGR}. ............................................................. 28 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ......................................................................................................... 47 8.0 RECIRCULATION LOOPS-SINGLE LOOP OPERATION .......................................... 49 9.0 POWER/ FLOW MAP .................................................................................................. 68 10.0 OPRM SETPOINTS ...................................................................................................... 70 11.0 , REFERENCES .............................................................................................................. 71
PL-NF-23-002 Rev. 1 Page 4 of 72
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 22 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 NRG-approved methods and are established such that all applicable limits of the plant safety analysis are met.
PL-NF-23-002 Rev. 1 Page 5 of 72 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.
2.1 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.
2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height.
2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
2.4 LHGRFACt is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACt 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. 7 MCPRss.s% is the cycle-specific safety limit MCPR that ensures at least 99.9% of fuel rods are not susceptible to boiling transition.
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 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 MCPRss.s% 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.
2.1 O Sp is the OPRM trip setpoint for the peak to average OPRM signal.
2.11 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.
PL-NF-23-002 Rev. 1 Page 6 of 72 3.0 SHUTDOWN MARGIN 3.1 References Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:
a) 0.38% 11k/k with the highest worth rod analytically determined OR b) 0.28% 11k/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 burn up, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SOM) 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-23-002 Rev. 1 Page 7 of 72 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 References Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUM'-10 fuel shall not exceed the limit shown in Figure 4.2-1A. The APLHGRs for ATRIUM' 11 fuel shall not exceed the limit shown in Figure 4.2-1 B.
The APLHGR limits in Figures 4.2-1A and 4.2-1 Bare valid in Two Loop operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. The APLHGR limits for Single Loop operation are provided in Section 8.0.
SSES UNIT 2 CYCLE 22 16.0 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
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PL-NF-23-002 Rev. 1 Page 10 of 72 5.0 MINIMUM CRITICAL POWER RA TIO (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 For Unit 2 Cycle 22, the MCPRee.e% Safety Limit is 1.07 for Two Loop operation and 1.09 for Single Loop operation.
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'-10 and ATRIUM' 11) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel b) Main Turbine Bypass Inoperable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-8: Power Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed
PL-NF-23-002 Rev. 1 Page 11 of 72 Figure 5.2-9: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-1 O: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel The MCPR limits in Figures 5.2-1 through 5.2-1 O are valid for Two Loop operation and are applicable to both ATRIUM'-10 and ATRIUM' 11 Fuel.
The MCPR limits for Single Loop operation are provided in Section 8.0.
5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.
Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
PL-NF-23-002 Rev. 1 Page 12 of 72 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 22 2.6 I LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.4 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 I
2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
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CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 i-I-
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I 1.2 10 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-2
PL-NF-23-002 Rev. 1 Page 15 of 72 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 22 2.5 LEGEND 2.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME --
2.3 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I I I I 2.2 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE -
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SSES UNIT 2 CYCLE 22 4.3 LEGEND -,...
4.1 CURVE A: CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 26, 3.16 INSERTION TIME 3.9 23, 3.51 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.7 CURVE 8: CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3.5 26, 3.16 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 3.51 \A -,...
3.3 \ B CURVE D: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR -
..... REALISTIC AVERAGE SCRAM INSERTION TIME
.E CURVEC:
- i 3.1 '
26, 2.59 Cl SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE -
C: 23,2.84
~ 2.9 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 -
...m Cl)
C. '\
0 2.7 CURVED: ,-c
~ 26, 2.59 \ USED IN DETERMINING MFLCPR
- a. 23, 2.84 D ~
0 2.5 I 26.01, 2.44:
~ ~
2.3
..... ......... 140, 2.01:
..... i-.... 150, 2.071 2.1 : 26.01, 2.25 I
~------- -- ... _-... ... _ : 60, 1.86 1.9 A_ ~ 70, 1.82 I
............ 180,1.741 I 90, 1.69 ~
140, 1.901 .............
1.7 150, 1.90 1 *-------- ----- *------ I100, 1.691
- 60, 1.71 ~
B_ H70, 1.66 I 1100, 1.551 1.5
]
REFERENCE:
T.S. 3.7.6 and 3.2.21 I 80, 1.58 I I 90, 1.55 I 1.3 10 20 30 40 50 60 70 80 90 100 Core Power(% RATED) -0 ""'CJ ni r (0 I MCPR OPERATING LIMIT VERSUS CORE POWER CD z
....>. -;n MAIN TURBINE BYPASS INOPERABLE
--..J :::0 N TWO LOOP OPERATION (BOC TO EOC) 0 CD Cf
....., < 0 ATRIUM'-10 AND ATRIUM' 11 FUEL --..J* 0 N....,. N FIGURE 5.2-4
PL-NF-23-002 Rev. 1 Page 18 of 72 EOC-RPT Inoperable
SSES UNIT 2 CYCLE 22 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 I
2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
.. 2.1
"§ I 30.0, 2.06 I -
- i K USED IN DETERMINING MFLCPR Cl 2.0 C:
L 11:S
...a., 1.9 C. 140.0, 1.861 0
0::: "'
0.. 1.8
(.)
~
1.7 1.6 1.5 140.1, 1.411
~
1.4 A B
1.3 H
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 :
1108.0, 1.221 1.2 30 40 50 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)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-5
SSES UNIT 2 CYCLE 22 4.3 LEGEND 4.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.9 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.7 CURVE A:
26, 2.61 -
23,2.84 CURVE C: CORE POWER:$; 26% AND CORE FLOW:$; 50 MLBM/HR 3.5 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME -
3.3 f- CURVES: CURVE D: CORE POWER:$; 26% AND CORE FLOW:$; 50 MLBM/HR
.... 26, 2.61 REALISTIC AVERAGE SCRAM INSERTION TIME 23, 2.84 3.1
- e::i C>
C: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE
- .:; 2.9 .... CURVEC: PER SR 3.7.6.1 AND 3.7.6.2 l'G -
Cl)
.... 26, 2.59 I
C. 23,2.84 0 2.7 0::
As USED IN DETERMINING MFLCPR ll..
0 CURVED: _D_
t 2.5 7 26.01, 2.41
~ 26, 2.59 23, 2.84 ...... ~
2.3
......... 140, 2.12LJ , 2 _12 1 2.1 26.01, 2.231
... .... -------50
............. -... .........I 60, 1.99 1A_ 770, 1.901 1.9 ------
--........ ...... ... _ 180,1.741 190, 1.731-
- 40, 1.90: - ......
................ 1100, 1.731 1.7 150, 1.891 *---------------
I 60, 1.72 1100, 1.56 1.5 B_ J10, 1.67L I
"-180, 1.60 1 190, 1.571
REFERENCE:
T.S. 3.3.4.1 and 3.2.21 I I 1.3 10 20 30 40 50 60 70 80 90 100 Core Power (% RATED) ""O ""O ru (C
rI MCPR OPERATING LIMIT VERSUS CORE POWER (I) z I\.) 71 EOC-RPT INOPERABLE 0 ;:oN TWO LOOP OPERATION (BOC TO EOC) 0 CD Cf ATRIUM'-10 AND ATRIUM' 11 FUEL - <o
-....i* 0 I\.)->. I\.)
FIGURE 5.2-6
PL-NF-23-002 Rev. 1 Page 21 of 72 Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 22 2.6 I LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.4 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 I I I I 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.1 -I 30.0, 2.06 :
- e:J.... I I I I USED IN DETERMINING MFLCPR Cl 2.0 ~
C:
~
...cu Q) 1.9 I 40.0, 1.86 I C.
0 0:: 1.8 a..
0
~
1.7 1.6 1.5 140.1, 1.411 1.4 A B
1.3 1
REFERENCE:
T.S. 3.7.8 and 3.2.2:
1.2
- I 108.0, 1.221 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-7
SSES UNIT 2 CYCLE 22 4.0 I I I I I 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.4 CURVE A: CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 26, 2.61 23, 2.84 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 3.2 ALL SCRAM INSERTION TIMES CURVEB:
.... 3.0
.E 26, 2.61
- i 23, 2.84 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES C) 2.8 ,. A r::: ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- CURVEC
- \. B ca
... I I --. --. I Cl) 2.6 26, 2.59 --c c.. 23,2.84 USED IN DETERMINING MFLCPR 0
0::
' 126.01, 2.411
- a. 2.4 0
~ ..._ ... .....
2.2 140, 2.07 1
- -...... _ 150, 2.071 26.01, 2.23 I 2.0
...... l 60, 1.86 lA- H10,1.19:
40, 1.971 ____,,;,,::
1.8 : 50, 1.93: ~---------
.......... r-.-. ........ ,....,,. ~80,1.73:
- 90, 1.62t-I 60, 1.83 I ....... ~ .
1.6 B 1100, 1.561
~---- *------
I i 70, 1.65: 1180, 1.57 I 1.4 ~ I100, 1.421
REFERENCE:
T.S. 3.7.8 and 3.2.2J I 90, 1.521 1.2 10 20 30 40 50 60 70 80 90 100 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-8
PL-NF-23-002 Rev. 1 Page 24 of 72 One TSV or TCV Closed
SSES UNIT 2 CYCLE 22 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.3 2.2 H 30.0, 2.16: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.1 I
- e... 2.0 USED IN DETERMINING MFLCPR J I C)
C:
' 140.0, 1.941
- 1.9
...cu Cl) a.
0 1.8 0::
ll..
0
- ii: 1.7 140.1, 1.591 1.6 A
B 1.5 1.4
- I10s.o, 1.31 I 1.3 H
REFERENCE:
T.S. 3.2.2 and TRM 3.3.71 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*
TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-9
SSES UNIT 2 CYCLE 22 4.0 I I I I 3.8 LEGEND 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME -
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 - CURVE A:
26, 2.61 CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR -
-- 23, 2.84 i--
3.2 -- ALL SCRAM INSERTION TIMES 3.0 - CURVEB:
.....E 26, 2.61 J 23, 2.84 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE C> 2.8 A s::::
--- ' PER SR 3.7.6.1 AND 3.7.6.2 -
I'll B- -
a, 2.6 CURVEC: -C C.
- 26, 2.59 -
0 - 23, 2.84 126.01, 2.41 J-i USED IN DETERMINING MFLCPR ct: 2.4 ll. -
0 r
- §:
2.2 2.071 A
... __________ ISO, 2.071
- ....... -... ... _-... ... ... :4o, 126.01, 2.231 - ............... .........
2.0
............... ...... ... ... : 60, 1.86:
... , .......... ___ 70, 1.791 1.8 :40, 1.90 B I so, 1.89 I ---.......... - - - - - 175, 1.761 1.6 :so, 1.71: 175, 1.61 I 70, 1.65:
1.4 7
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7:
1.2 10 20 30 40 50 60 70 80 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-10
PL-NF-23-002 Rev. 1 Page 27 of 72 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 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-23-002 Rev. 1 Page 28 of 72 6.0 LINEAR HEAT GENERATION RA TE (LHGR) 6.1 References Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 6.2 Description The maximum LHGR for ATRIUM'-10 and ATRIUM' 11 fuel shall not exceed the LHGR limits determined from Figure 6.2-1A and Figure 6.2-18, respectively.
The LHGR limits in Figures 6.2-1A and 6.2-1 Bare valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.
To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided in the following figures:
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 6.2-3: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 6.2-5: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel c) EOC-RPT Inoperable Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 6.2-7: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel d) Backup Pressure Regulator Inoperable Figure 6.2-8: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel
PL-NF-23-002 Rev. 1 Page 29 of 72 Figure 6.2-9: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-10: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 6.2-11: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel The LHGR limits in Figures 6.2-1A/6.2-1 Bare valid for both Two Loop and Single Loop operation and are fuel type specific. The LHGR limit multipliers in Figures 6.2.2 through 6.2.11 are valid for both Two Loop and Single Loop operation and are applicable to both ATRIUM'-10 and ATRIUM' 11 Fuel.
SSES UNIT 2 CYCLE 22 16.0 I I
I I
I I I I i--,,--.--r--.1I I I 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--+--~--~---~--4--+--~--~---~--~---~--~--+--~--~---~--~--+--~--~---~--~--+-- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 14.0
- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I lo~o,'.13.~rJ---f--j--f--f-d8Joo! 1~.4t-+-++-f-++-+-!--~ : : : :R~F~R~N~~:
I I I I I I II II II II II II II II II II II II II II II II T:. s>-~-3: : : : ~--
~
I I I I I I I I I I I I I I I I I I I I I I
:,---r--r--r--r--,---r--: ..... --r--,---r--1--r--r--,---r--1--r--r--1---:--1--
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 12.0 --.....~--~.,---r--1---:---t--1---r--t---:---t--i---r --7--t--i---r--t--7--1--i---t--~---i--t--~---r--~---r--t---:---t--~---r--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
.E
- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 - ~ -.....-~--!,*---~--t--T--t--1---~--t--T--t--i---~--1--7--t--i-- --:---t--~---~--1---:---t---:---~--1---~--t--T--t--1---~--t---t--
- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I a:: I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I C: I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 10.0 ....._..__._....____,1 ___ ~--+---:---t--i---~--1---:---t-- ---~--1---:---t--i---~--1--+--f-- L-- ---~--t---:---~--1--+--t---:---t-- ---~--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 Cl) I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I C: I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I Cl) I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
(!) + +- i---r--t--+--t--i---r--t--+--t-- ---r--t--+--t-----t--t--+--t-- ---t--t---r--t- --t--i---r--t--+--t-- ---r--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 J I I I 1ii I I I I I I 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 Cl) I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
- c I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
...cu 8.0 +---;,---;--r--l---~--3/4--+--~--~---~--4--+--i--~---~--~--+--1/4--~---~--~--+--3/4--~---~--~---~--3/4--+--~--~---~-- +--~--~---~--4--+--
I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I Cl)
C: : ! ! ! i i : ; : : : ! : i ! : i ! : : ! i i : ! i ! i : : I : : 74400, 7.1 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 t
- J I I I I I I I I I I 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
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
--r--i---~--~---:---~--~---~--4---:---~--~---~--4--+--f--~---~--4--+--~--~---~--~---~--~--+--~--~--4---~---:---~--~---r--4---:--- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 6.0 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
-+-----...--~,---~--T---,...--r--1---~--~---,...--r--~---~--~---,...--T--~---r--1--""T"'--T--~---r--1---~--T--""'l---r--1---~--T---t---r--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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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--o---t--t--- 1 I --+---1---~--
I I I ---
I I --+---1---~--
I I I -----
I I I ---1---+-----
I I I I-- -------
I I --
I ---
I --
I -----+--
I I I ---
I I-----
I I --+---1---
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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWD/MTU) ""CJ
""CJ
- 0) rI co z LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE CD "Tl ATRIUM'-10 FUEL w I 0 ::0 N FIGURE 6.2-1A 0 CD Cf
- < 0
---J 0 N _._ N
SSES UNIT 2 CYCLE 22 16.0 I I
I I
I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1--.-T-+--;'---~--+--+--r--1---~--+--+--r--1---~--f--+--+--1---r--f--+--+--1---r--f---~--+--+--~--f---~--+--+--~--1---~--+--+--
- I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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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- : : : I I I B l26, o.~o I ______ j_________ j __________ j SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 0.40
' I : : : ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 0.35 :26,I 0.39 ! ! !
~--------=-=-=-=-=-=,~-----=-=-=-=--=-==-~=----=-=--=-=-=-=---~=--=-=-=-=-=-----,--=-=-=-=---------~-~~=-=-=-------------~==---------_-
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. . I I I I I I I I I I I I I I I I I I I I I 0.30 20 30 40 50 60 70 80 Core Power (% RATED)
POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 6.2-11
PL-NF-23-002 Rev. 1 Page 47 of 72 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 References Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and f) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.
PL-NF-23-002 Rev. 1 Page 48 of 72 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value( 1> Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 117.4 117.0 High Power Range - Upscale 107.6 107.2 (1 > Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of RATED THERMAL POWER. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.
Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR (2,3,4)
(% of Rated)
~ 28 and< 90 < 1.78
~ 90 and< 95 < 1.47
- 95 < 1.68
( 2> Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and one TCV/TSV closed.
( 3> Applicable to both Two Loop and Single Loop Operation.
(4> Applicable to both ATRI U M-10 and ATRIUM 11 Fuel.
PL-NF-23-002 Rev. 1 Page 49 of 72 8.0 RECIRCULATION LOOPS -SINGLE LOOP OPERATION 8.1 References Technical Specification 3.2.1, 3.2.2, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 8.2 Description APLHGR The APLHGR limit for ATRIUM'-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1A. The APLHGR limit for ATRIUM' 11 fuel shall be equal to the APLHGR Limit from Figure 8.2-1 B.
The APLHGR limits in Figures 8.2-1A and 8.2-1 Bare 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 and ATRIUM' 11) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel b) Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel
PL-NF-23-002 Rev. 1 Page 50 of 72 d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-1 O: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-11: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel The MCPR limits in Figures 8.2-2 through 8.2-11 are applicable to both ATRIUM'-10 and ATRIUM' 11 Fuel, are valid only for Single Loop operation, and support power levels up to 67.2% RATED THERMAL POWER and core flows up to 52 Mlbm/hr. These conditions conservatively bound Single Loop Operation in accordance with Technical Specification 3.4.1.
Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.
RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.
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PL-NF-23-002 Rev. 1 Page 53 of 72 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable
SSES UNIT 2 CYCLE 22 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 FOUR BYPASS VALVES 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- i ------
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- 0. -----. I I 0 140.0, 1.861 0::: ~
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REFERENCE:
T.S. 3.4.1 and 3.2.21 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-2
SSES UNIT 2 CYCLE 22 4.0 I I I I LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE A:
26, 2.63 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 23, 2.86 ALL SCRAM INSERTION TIMES 3.2 I I I
.... SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
"§ 3.0 - CURVE B:
- J 26, 2.63 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C) - 23, 2.86 C: \. A
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126.01, 2.251
-- ,so, 2.00 67.2, 2.00, 2.0 140, 2.001 8- i 50, 2.00: ,so, 2.00 67.2, 2.00 I 1.8 1.6 H
REFERENCE:
T.S. 3.4.1 and 3.2.2:
1.4 10 20 30 40 50 60 70 80 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-3
PL-NF-23-002 Rev. 1 Page 56 of 72 Main Turbine Bypass Inoperable
SSES UNIT 2 CYCLE 22 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 I I
~ SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS E VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
- J 2.2 -
C)
C: 130, 2.061
!'Cl r----......... USED IN DETERMINING MFLCPR Cl> 2.0 I
- a. ----...
0
~ ~ I40, 1.86 I a.
0 1.8
~
1.6 A-8 152, 1.521 140.1, 1.561 1.4 I
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 j 1.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR) ""'CJ ""'CJ ru (0
rI CD z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CJ1 77 MAIN TURBINE BYPASS INOPERABLE -...J ::0 N SINGLE LOOP OPERATION (BOC TO EOC) 0 CD Cf
- <o
-...J* 0 ATRIUM'-10 AND ATRIUM' 11 FUEL N -"- N FIGURE 8.2-4
SSES UNIT 2 CYCLE 22 4.4 I I I I LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.0 CURVE A: INSERTION TIME 26, 3.18 3.8 23,3.54 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER:;;; 26% AND CORE FLOW:;;; 50 MLBM/HR 3.6 A CURVEB: \. MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 3.18 _s \
3.4 23, 3.54 CURVE D: CORE POWER:;;; 26% AND CORE FLOW:;;; 50 MLBM/HR
.... \
.E REALISTIC AVERAGE SCRAM INSERTION TIME
- J 3.2 I I I Cl CURVEC:
C: 26, 2.61 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS
~ 3.0 23, 2.86
...cu Cl)
VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 Cl.
-c \.
0 2.8 I 0:: CURVED:
\. USED IN DETERMINING MFLCPR
- a. -o \
0 2.6 26, 2.61 r
- !?: 23, 2.86 I 2s.01, 2.46 2.4 2.2 -, , ... 140, 2.09 A- H5o, 2.09:
- 26.01, 2.27 :
--......... -- ---- - 1so, 2.00 67.2, 2.ooj 2.0
- 4o, 2.00 8- H5o, 2.00: :so, 2.00 67.2, 2.00!
1.8 1.6 7
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 :
1.4 10 20 30 40 50 60 70 80 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-5
PL-NF-23-002 Rev.1 Page 59 of 72 EOC-RPT Inoperable
SSES UNIT 2 CYCLE 22 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 I I I
.... SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
.E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- J 2.2 CJ C: 130, 2.061
...m ...........__ USED IN DETERMINING MFLCPR CD 2.0 I I 0.. ----..
0 a:: 140, 1.861 a.
~
0 1.8
~
1.6 A B 1.4 I 52, 1.38 I 140.1, 1.41 I 1.2
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR) ""'O ""'O Ill rI (Cl CD z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW
- 0) 71 EOC-RPT INOPERABLE O :::0 N SINGLE LOOP OPERATION (BOC TO EOC) 0 CD 'f
-<o ATRIUM'-10 AND ATRIUM' 11 FUEL -...J" 0 N ->. N FIGURE 8.2-6
SSES UNIT 2 CYCLE 22 4.4 LEGEND 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.0 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
3.8 CURVEA
CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR 3.6 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 2.63 23, 2.86 3.4 CURVE D: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR
.E REALISTIC AVERAGE SCRAM INSERTION TIME CURVE 8:
- i 3.2 26, 2.63 Cl C: 23, 2.86 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
- 3.0
...cu ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (I)
C. CURVEC: '- A 0 2.8 0:: 26, 2.61 B
- a. 23, 2.86 -c USED IN DETERMINING MFLCPR 0 2.6
~
D 2.43:
_ : 26.01,
2.4 CURVED
26, 2.61 ~
23, 2.86 - ... ...... 40, 2.141 A_ LJ50, 2.141 2.2 -
r--,...,__
I 26.01, 2.25 1 : 60, 2.01
--............. -- - ........... __ 67.2, 2.001 2.0
- 4o, 2.00 8- rl 50, 2.00 I 160, 2.00 67.2, 2.001 1.8 1.6
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 1.4 10 20 30 40 50 60 70 80 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-7
PL-NF-23-002 Rev. 1 Page 62 of 72 Backup Pressure Regulator Inoperable
SSES UNIT 2 CYCLE 22 3.0 LEGEND 2.8 -
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME ----
I I 2.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- e...
J 2.2 .
Cl USED IN DETERMINING MFLCPR C: 130, 2.061 I'll (I) 2.0
- a. ---...
0 0::: ~ 140, 1.861 fl.
0 1.8
~
1.6 A B 1.4 I 52, 1.38 I 140.1, 1.41 I 1.2 7
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR) ""'D ""'D n:, r;-
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW cg z
- 0) -;n BACKUP PRESSURE REGULATOR INOPERABLE W ;;o N SINGLE LOOP OPERATION (BOC TO EOC) 0 CD Cf 0
0 ATRIUM'-10 AND ATRIUM' 11 FUEL ---.J"<
N ....,._ N FIGURE 8.2-8
SSES UNIT 2 CYCLE 22 4.0 LEGEND 3.8 ,----
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 - CURVE A:
CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR
- 26, 2.63
_ 23,2.86 ALL SCRAM INSERTION TIMES 3.2 3.0 .... CURVEB:
26, 2.63
..,. 23, 2.86 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
\. A ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.8 B I
'""CURVEC: I
.E.. C
- i 2.6 ..,. 26, 2.61 USED IN DETERMINING MFLCPR C> .... 23, 2.86 C
I 26.01, 2.43 I I'll
... 2.4 Cl) c..
0 ........... -... ...... _
0::: 2.2 -r--,....__ ...... ... _ :40, 2.09 A H5o, 2.09:
- a. I 26.01, 2.25:
0 s1.2, 2.00 I
~ --............. --------- ....................... _ : so, 2.00h 2.0
- 40, 2.00 B H5o, 2.00: :so, 2.00 67.2, 2.001 1.8
]
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 I 1.6 1.4 10 20 30 40 50 60 70 80 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-9
PL-NF-23-002 Rev. 1 Page 65 of 72 One TSV or TCV Closed
SSES UNIT 2 CYCLE 22 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM -
INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -
2.4
~ SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES E ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- i 2.2 :-(30,2.16 1 -
Cl C:
(1:1 ~ ............
Q) 2.0 I USED IN DETERMINING MFLCPR I
- a. 140, 1.941 I I 0
0::
a.
0 1.8
- 1!:
A B 1.6 I52, 1.551 140.1, 1.591 1.4 1.2
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 1.0 30 35 40 45 50 55 60 65 70 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOG)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-10
SSES UNIT 2 CYCLE 22 4.0 I 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 A:
26, 2.63 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR 23, 2.86 ALL SCRAM INSERTION TIMES 3.2 I I I 3.0 CURVE 8: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- -Je 26, 2.63 C) r::: 23, 2.86 \. A 2.8 cu Cl)
USED IN DETERMINING MFLCPR a.
- CURVEC: C~B I I 0 2.6 26, 2.61 0::: 23, 2.86
- n. 1 26.01, 2.43 1 0 .
- !!: 2.4 .........
~- -.... ........
2.2 .... ........... 40, 2.09 A- ~ 50, 2.os:
- 26.01, 2.25 :
r---....... :so, 2.00 67.2, 2.001 2.0
- 4o, 2.00 B- H5o, 2.00: 1 so, 2.00 67.2, 2.00 I 1.8 1.6 H
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7: I I 1.4 10 20 30 40 50 60 70 80 Core Power(% RATED) -0 -0 m
(0 rI (D z MCPR OPERATING LIMIT VERSUS CORE POWER
SINGLE LOOP OPERATION (BOC TO EOC) 0 CD Cf
- <o
-...J" 0 ATRIUM'-10 AND ATRIUM' 11 FUEL I\.)....,,_ I\.)
FIGURE 8.2-11
PL-NF-23-002 Rev. 1 Page 68 of 72 9.0 POWER/ FLOW MAP 9.1 References Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and 11 of the Power/ Flow map, Figure 9.1.
If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power/ Flow map is considered an immediate exit region.
If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power 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-23-002 Rev. 1 Page 69 of 72 f )tf-.,J 120 120
Purpose:
I It,, I,,
I I I UNIT2
==:r,n,,:TT.
--:-r-
...cJ_--.,_~_-,J!::
-r-. --r-1--
110 110 Initial / Date: ' '
STABILITY REGION I IF OPRM INOPERAaLE IMM5DIATELY SCRAM IAW APPLICABLE PROCEDURE.
100 100 IF OPRM OPERABLE IMMEDIATfLY EXITIAW APPLICABLE PROCEDURE.
STABILITY REGION II IMMEDIATELY EXIT IAW APPLICABLE PROCEDURE. ITiillill 90 RESTRICTED REGION I I I I I \ I 90 IF ABOVE MELLLABOUNDARY, --H--H-- +++
IMMEDIAlELY EXITIAW APPLICABLE
--f-~--f-4-- -1 lni-*
PROCEDURE. I I I I I 80 .j..!~:=!':=!=:9:;=f=!':=!=:9:==;:=F=!=:91==;:=;::=i=9:==;1=;::=:F-l-+:-+-1 80
-r-1-+- --:---t--:---t- -+--:---+--:-- --:--+--:--t-- --r-
-i--~-t--~- --:--i--!--i- -t--~-t-~-- -~--+-~--~- -.
c -r-1--r- --r-1--r -t--r-;- ;-- -;- ;--~
I l I I I I I I I I I I I I I I w 70
-:-r-r- --t:--r -r-r-rr- -r*r ,1-~l-l-l~l-+-l-l~l-l-+--~~HH- 70
~ -1-1- --:-:--: -r-1--r- --:--1--r ......
- I l I I I I I
~ -r-r-r*r-
' t I I
--r*r--r*r-I l I I L.
60 TT1T-rrrr G) -l-,.l-'-.C.....-1--'-"--'-'-...j,...'--'-.....,._
_J_J_J_J __ J_J __L_J_ 60
~
-:--:-:--:- --:-:-~:-:-
I I I I I I I I a.
I I I I l I 1 I cu -r-1--r- --i--t--r-t-E 50
-:--:-r-:- --r-r-rr 1 I I 1 I I I I
-+--<'--'-~-+-.;......;.-.-....i-,~,~ * ..- 50
-t-i--t-1--
-f-r ~
G)
.c: -i __L-L I-
-t-+-i --
.1-J____L_L_L_L I
_J. __ L_J._
I l I -t-.J,--f-~-- -.J,--7-~--
-t-i--+-+- -~--~-i-- :
, l : : : : l
-: -t- : . - : -t- : ,t-1 I l 1 1 I/
-t--l--t--1--
- I / /
--!--f--!--
I/ I 40 i /
40
-++- -+-1-+-1-- +-1-+- -+-r-+-t- --t-+-t-+- -+-r-+-
1 I l I I I I 1 l I l I I I I l
, I I l I I I I I I I I 1 I I I I I l I I I I
~f--~-
--1--+--1--.i.- --1--1---1--
_J__L_J._L ___ L_L_LL __ L_L_l._L __ _l_l __LL _l_J__l_J_ __ J_LJ_ ~
---l--- --1-- --1---4--1--- --4-4---4---l-- -+-- --+--1--
- _ 1 -~-.!--
--+-~-~-- -~--~-~--~- --~-~--~-~--I -~--i--i--l-- --!--i--~-l- -t-~--+-~-- -~--~-~--
I
_L_L_L ~
l l I * : I l /: I: I I 30 11 30
+- --~-1-+-1-- +-i-+- -+-~--l--t- --t-i--t-+- -+-r-+-
t l : l : : : j ,*
- I
- 1 -r: ::cr1:r: :r1:r1: :1:c:cr :tI]:I: :11:1:
l I I I I I I I I I I t l I I l ! I I I I ~
~:1 _, _
-; +-l -;-+-t- -:-1--t-1-- -t-:-;-- 1/4 I I : l : : :
1 1 1 I I I I I I I I I I I I I
-~--'- ; - --; -;--; - ;--
20 r-;;;::;;:;;:;;'7-i--4--i-+¥--l---+-li-+-l--l-./-i--+-i-i--l-+--i-\-i.-l--l--i-i--i-i--J...+-i-i--+-J.-i-i--i-++.+-i-i--+-J.-i-+-i-liffl-20
- --r-1-+-1-- -r-1--r- --r-t-t-t- --}--:--+-+- -+-~-+- :m
-r I I I I I I l I I I I I I I I I I I I
-, 30 ~--~-~-- -~--~-~--~- --~-t--~-+- -i-t-i-~-- -~--~-~-- ~
-~,--t-, ~-,-,-~~--* -~.--~, -~,-- -~.--~, -~.--~, - --~. -~. --~, -t,- J_J_J_J_
- : : l
__ J__t_J__
- I: ~
i--i-1-- -r-i-- ~
10 10
--~-4--~--l--- -~-+-4--~- --r--}--r--T- -T-"1--T--,-- --,--,---,-- I
,.-t: ::~:i:~:~:: :~::~:r:~: ::~:~::~:~:: :~:l:r:~: ::~:i::~:r :i:i:rl: :r:r:r:
t I I I I l I l I I I l I I 1I I I I 0
I I I I I I 1 I I I t I I I I I I I I I I I I I I I I 0
j 0 10 20 30 40 50 60 -70 80 90 100 110 Total core Flow (Mlbm/hr)
Figure 9.1 SSES Unit 2 Cycle 22 Power/ Flow Map
PL-NF-23-002 Rev. 1 Page 70 of 72 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPRss.s3/4 Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:
= 1.12
= 16 Fp = 60 Mlbm / hr
PL-NF-23-002 Rev. 1 Page 71 of 72
11.0 REFERENCES
11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
- 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-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.
- 5. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.
- 6. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.
- 7. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,
September 1986.
- 8. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
- 9. EMF-2209(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.
- 10. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),
"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"
Siemens Power Corporation, February 1998.
- 11. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.
- 12. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -
Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.
PL-NF-23-002 Rev. 1 Page 72 of 72
- 13. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
- 14. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
- 15. BAW-10247PA, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors," AREVA, Inc., April 2008.
- 16. ANP-10340P-A, Revision 0, "Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods," Framatome Inc., May 2018.
- 17. ANP-10335P-A, Revision 0, "ACE/ATRIUM-11 Critical Power Correlation,"
Framatome Inc., May 2018.
- 18. ANP-10300P-A, Revision 1, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios,"
Framatome Inc., January 2018.
- 19. ANP-10332P-A, Revision 0, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios,"
Framatome Inc., March 2019.
- 20. ANP-10333P-A, Revision 0, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA),"
Framatome Inc., March 2018.
- 21. ANP-10307PA, Revision 0, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors," AREVA, Inc., June 2011.
- 22. BAW-10247P-A Supplement 1P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 1:
Qualification of RODEX4 for Recrystallized Zircaloy-2 Cladding," AREVA Inc.,
April 2017.
- 23. BAW-10247P-A Supplement 2P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 2:
Mechanical Methods," Framatome Inc., August 2018.