NL-19-1384, Cycle 30 Core Operating Limits Report
| ML19323D818 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/19/2019 |
| From: | Gayheart C Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-19-1384 | |
| Download: ML19323D818 (17) | |
Text
~ Southern Nuclear Regu latory Affairs 3535 Colonnade Parkway Birmingllam, AL 35243 205 992 5000 tel 205 992 7795 fax NOV 1 9 2019
(
Docket No.: 50-348 NL-19-1384 U. S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Unit 1 Cycle 30 Core Operating Limits Report Ladies and Gentlemen:
In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company (SNC) submits the enclosed Core Operating Limits Report (COLA) for the Joseph M.
Farley Nuclear Plant (FNP) - Unit 1 Cycle 30 Version 1.
This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.
Respectfully submitted, C eryl . yheart Regulatory Affairs Director CAG/was/scm
Enclosure:
Core Operating Limits Report for FNP Unit 1 Cycle 30 Version 1 cc: Regional Administrator, Region II NRR Project Manager- Farley Nuclear Plant Senior Resident Inspector - Farley Nuclear Plant RTYPE: CFA04.054
Joseph M. Farley Nuclear Plant - Unit 1 Cycle 30 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 1 Cycle 30 Version 1
SOUTHERN<<\
COMPANY Energy to Serve Your World*
Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 - Cycle 30 Version 1 June 2019
CORE OPERATING LIMITS REPORT. FNP UNlT I CYCLE 30 June 2019 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT I CYCLE 30 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The Technical Requirement affected by this report is listed below:
13.1.1 SHUTDOWN MARGIN- MODES I and 2 (with ke1T ::::: I)
The Technical Specifications affected by this repmi are listed below:
2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN- MODES 2 (with kerr< I) 3, 4 and 5
- 3. 1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2 .1 Heat Flux Hot Channel Factor- FQ(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor- F,{,1 3.2.3 Axial Flux Difference 3.3 . 1 Reactor Trip System Instrumentation Overtemperature ~T (OT~T) and Overpower ~T (OP~T) Setpoint Parameter Values for Table 3.3 .1-1 3.4. 1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration Page I of 15
CORE OPERATING LIMITS REPORT, FNP UNIT J CYCLE 30 June 2019 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section I .0 are presented in the follow ing subsections. These limits have been developed using NRC-approved methodologies, including those specified in Technical Specification 5.6.5.
2.1 SHUTDOWN MARGIN- MODES I and 2 (with ken*:2: 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGrN shall be greater than or equal to 1.77 percent L'.k/k.
2.2 SHUTDOWN MARGIN - MODES 2 (with ketT < 1.0), 3. 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (kerr < 1.0), 3 and 4- The SHUTDOWN MARGrN shall be greater than or equal to 1.77 percent L'.k/k.
2.2.2 Mode 5- The SHUTDOWN MARGfN shall be greater than or equal to 1.0 percent L'.k/k.
Page 2 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 June 20 19 2.3 Moderator Temperature Coefficient (Specification 3. 1.3) 2.3. 1 The Moderator Temperature Coefficient (MTC) limits are:
The BOLlARO-MTC shall be less than or equal to +0.7 x I 0-4 ~k/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 ~klk/°F at 100 percent RTP.
The EOLIARO/ RTP-MTC shall be less negative than -4.3 x 10-4 ~k/k/°F.
2.3 .2 The MTC Survei ll ance limits are:
The 300 ppm/ ARO/RTP-MTC should be less negative than or equal to 4
-3.65 X ] 0- ~k/k/°F.
The revised predicted near-EOL 300 ppm MTC sha ll be calcu lated using Figure 5 and the following algorithm :
Revised Predicted MTC Predicted MTC* + AFD Correction** + Predictive Correction***
where,
- Predicted MTC is calculated from Figure 5 at the burnup corresponding to the measurement of 300 ppm at RTP conditions,
- AFD Correction is the more negative value of:
{0 pcmr F or (~AFD
- AFD Sensitivity)}
where: ~AFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the burnup corresponding to 300 ppm, AFD Sensitivity = 0.07 pcmr F I ~AFD
- *Predictive Correction is -3 pcmr F.
The 100 ppm/ARO/ RTP-MTC should be less negative than -4.0 x 10 4 ~k/k/°F .
where: BOL stands for Beginnjng of Cycle Life ARO stands for All Rods Out EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.
Page 3 of 15
CORE OPERATING LlMlTS REPORT, FNP UNIT I CYCLE 30 June 2019 2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5 .1 The control rod banks shall be limi ted in physical insettion as shown in Figure l.
2.6 Heat Flux Hot Channe l Factor- F 0 (Z) (Specification 3.2.1)
FliT!'
2.6.1 F0 (Z) ~ __g______
- K(Z) for P > 0.5
- p for P::;; 0.5 where:
p = THERMAL POWER RATED THERMAL POWER 2.6.2 F;m* =2.50 2.6.3 K(Z) is provided in Figure 2.
F 1171' *K(Z) 2.6.4 F (Z) < - 0=-
- --- for P > 0.5 9 - P*W(Z)
F 117 *p
- K(Z)
F ( Z) < --"--
Q- - - for P ::;; 0.5 Q - 0.5*W(Z) 2.6.5 Full Power W(Z) values are provided in Table 4.
Part Power (48% RTP) W(Z) values are provided in Table 5.
2.6.6 The FQ(Z) penalty factors are provided in Table I.
Page 4 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 June 2019 2.7 Nuclear Enthalpy Rise Hot Channel Factor- F; (Specification 3.2.2) 2.7. 1 F NH<- FM1111l , * ( I + PFM l * (1 - P))
THERMAL POWER where: p =-----------
RATED THERMAL POWER 2.7.2 F~J" = 1.70 2.7.3 PF,.,., = 0.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 3.
2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm . 1 2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2 . 1.1) 2.10.1 In MODES I and 2, the combination ofTHERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 4.
2.11 Reactor Trip System Instrumentation Ove1temperature ~T COT~T) and Overpower ~T (OP~T)
Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Ove1temperature ~ T (OT~ T) and Overpower
~ T (OP~ T) setpoint parameter values forTS Table 3.3. 1-1 are listed in COLR Tables 2 and 3.
2.12 RCS DNB Parameters for Pressurizer Pressure. RCS Average Temperature. and RCS Total Flow Rate (Specification 3.4.1)
- 2. 12.1 RCS DNB parameters for pressurizer pressure RCS average temperature, and RCS total flow rate shall be within the limits specified below :
- a. Pressurizer pressure :?: 2209 psig;
- b. RCS average temperature ~ 580.3 °F; and
- c. The minimum RCS total flow rate shall be :?: 273 ,900 GPM when using the precision heat balance method and :?: 274,800 GPM when using the elbow tap method.
This concentration bounds the condition of k,rr ~ 0.95 (all rods in less the most reactive rod) and subcriticality (illl rods out) over the entire cycle. This concentration includes additional boron to address unce1tainties and B 10 depletion.
Page 5 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 June 2019 Table 1 Fo(Z) Penalty Factor Cycle Burnup FQ(Z) Penalty (MWDfMTU) Factor 0 1.0422 150 1.0422 354 1.0506 559 1.0560 763 1.058 I 968 1.0567 1172 1.0520 1377 1.0449 I 58 I 1.0367 1786 1.0283 I990 I.0205 2195 1.0200 7306 1.0200 7510 1.0248 7715 1.0261 7919 I .0274 8I24 1.0233 8328 1.0216 8532 1.0200 Notes:
- 1. The Penalty Factor, to be app lied to F0 (Z) in accordance with SR 3.2.1 .2, is the maximum factor by which F0 (Z) is expected to increase over a 39 EFPD interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) star1ingfrom the burnup at which the F0 (Z) was determined.
- 2. Linear interpolation is adequate for intermediate cycle burnups.
3 . For all cycle burn ups outside the range of the table, a penalty factor of 1.0200 shall be used.
Page 6 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT I CYCLE 30 June2019 Table 2 Reactor Trip System Instrumentation- Overtemperature 11T (OT/1T)
Setpoint Parameter Values T' $ 577.2°F P' = 2235 psig K1 = 1.17 1<3 = 0.000825/psi
'tl :::: 30 sec -r2 $ 4 sec
'!4 = 0 sec -rs ~ 6 sec h(/11) = -2.48 {23 + (qt- qb)} when (qt- qb) $-23% RTP 0% ofRTP when -23 % RTP < (qt -qb) ~ 15% RTP 2.05 {(qt- qb) -15} when (qt- qb) > 15% RTP Page 7 of 15
CORE OPERATING LIMITS REPORT, FN P UNIT I CYCLE 30 June 20 19 Table 4 RAOCW(Z)
Axia l Elevation ISO 3000 6000 10000 14000 18000 Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTll MWD/MTU 1 12 .00 1. 0000 1.0000 1. 0000 1.0000 1.0000 1.0000 2 I 1.80 1.0000 1.0000 1.0000 1.0000 1. 0000 1.0000 3 I 1.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 4 11 .40 1.0000 1.0000 1.0000 1. 0000 1.0000 1.0000 5 I 1.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 I 1.00 LI992 1.1842 1.2322 1.2369 1.2118 1.2384 7 10.80 1.2003 1.1842 1.2303 1.2358 1.2 11 2 1_2304 8 10.60 1.1 955 LI 78 1 1.2228 1.2294 1.2039 1.2121 9 10 .40 1.1 933 1.1 754 1_2 190 1_2228 LI 97 1 LI976 10 10.20 Ll899 Ll71 6 1. 2 178 L2 16 1 1. 1905 1.1 904 I 11 10.00 1.1 848 1.1 66 1 1.2 111 1.2089 LI 856 LI837 12 9.80 1.1 790 LI 600 1.21 00 1.20 14 1.1 883 Ll 765 13 9.60 1.1 727 1. 1534 1.2070 1.1937 Ll 945 Ll7 14 14 9.40 1.1 654 1.14 69 1_2018 1. 1857 1. 20 15 LI703 15 9.20 1.1588 1.1457 LI 948 1.1 802 1.2044 Ll 737 "16 9.00 1.1 539 1.1 599 1.1 897 1.1 813 1.2 167 Ll 86 1 17 8.80 1. 1460 1.1 687 1.1 972 1.1 787 1.222 1 1.1924 18 8.60 1. 1432 1.17 72 1. 2039 1.1 8 14 1. 2329 Ll955 19 8.40 1.1 524 1.1 863 1.2 127 1.1 946 1.25 13 1.2046 20 8.20 1.1 606 Ll940 1.2 190 1.205 1 1.2659 1.2251 21 8.00 1.1 673 LI 994 1.2230 1.2134 1. 2775 1.2422 22 7.80 1.1 721 1. 2028 1. 2249 1.2 194 1.2865 1.2565 23 7.60 1. 1746 1.2035 1. 224 1 1.2230 1. 2925 1.2679 24 7.40 Ll 758 1.2028 1.2220 1.225 1 1. 2966 1.2777 25 7.20 1.1 748 1.1 99' 1. 2 167 1.2237 1.2961 1_2828 26 7.00 Ll 73 1 Ll 94 1 1. 2 105 1.2204 1.2930 1.2845 27 6.80 1.1708 Ll 877 1.2036 1_2 169 12891 1.2857 28 6.60 LI 668 1.1 795 1.1 948 1.2 117 1.2830 1.285 1 29 6.40 1. 162 1 Ll 703 Ll 848 1.2050 1.2 745 1.282 1 30 6.20 1.1 568 1.1603 1.1 738 1.1970 12637 1.2766 31 6.00 1.1505 1.1493 LI 6 19 1.1878 1.25 13 1.2696 32 5.80 1.1 434 Ll 376 1.1 494 1. 1777 1.2376 L26 11 33 5.60 1.1 357 1.1 252 1.1 39 1 1.1 666 1.2220 1.2509 34 5.40 1.1286 1.11 76 1.1 298 1.1 584 1.2073 1.241 3 35 5.20 LI 265 1.1 276 1.1 226 1.1 590 1. 2070 1.2400 36 5.00 1.1 336 1. 1354 1.123 1 1.1 598 1.2045 1.2390 37 4.80 1. 1408 1.1 43 2 1.1 290 1.1610 1.20 II 1.2363 38 <1.60 1.1 475 1.1 503 1.1 339 1.1 609 1.1 960 1.23 17 39 4.40 1. 1536 1.1 568 1.1 384 1.1 599 1.1 895 1.225 1 40 4.20 1.1587 1.1 623 1.142 1 1.1 578 1.1 8 16 1.2 168 41 4.00 1.1 63 1 1.1 67 1 1.1 452 1. 1548 1.1 725 1.207 1 42 3.80 1.1 664 1.1 7 10 1.1 471 1.1 50 1 1.1 6 12 1.1 942 43 3.60 1.1 707 1.1 740 1.1 497 1.1 440 Ll 474 1.1 786 41 3.40 1. 1765 1.1 756 1.1 540 I. 1373 1.1 388 1.1 63 1 45 3.20 1.1 8 18 1.1 797 1.1 572 1.1 306 1.1 33 1 1.1 452 46 3.00 1.1 85 ~ 1.188 1 1.1 633 1.1 288 1.1 29 1 1.1468 47 2.80 1.1 949 1. 2 123 1.1 751 1.1 373 1.1 369 1.1 6 13 48 2.60 1.2 183 1. 2422 1.1 883 1.1 5 11 1.1 5 12 1.1 777 49 2.40 1.2446 1.27 13 1.2003 1.1642 1.1 647 1.1 949 50 2.20 1.2707 1.301 2 1. 2 189 1.1 777 l.l 785 1.2 120 5"1 2.00 1.2969 1.33 10 1.2385 1.1 904 1.1 909 1.2274 52 1.80 1.3228 1.3604 1.2576 1.2026 1.2028 1.2420 53 1.60 1.3475 1.3885 1. 276 1 1.2149 1.2 150 1.2569 5! 1.40 1.37 11 1.415 1 1.2938 1.2270 1.2272 1.27 19 55 1.20 1.3933 1.4400 1.3 104 1.2386 1.239 1 1.2868 56 1.00 1.4 137 1.4626 1.3258 1.2497 1.2509 1.3016 57 0 .80 LOOOO 1.0000 1. 0000 1.0000 1.0000 1.0000 58 0.60 1.0000 1.0000 1. 0000 1.0000 1.0000 1. 0000 59 0.40 1.0000 1.0000 1. 0000 1.0000 1.0000 1.0000 60 0.20 1.0000 1. 0000 1. 0000 1.0000 1.0000 1.0000 61 0.00 1.0000 1.0000 1. 0000 1.0000 1.0000 1.0000
- Top and bottom 5 axial points excl uded per Technical Specification 83.2.1.
Page 9 of IS
CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 June 2019 Table 5 Part Power (48%) RAOC W(Z)
Axial Point E leva tion (feet) ISO t'\'IWD/MTll 1 12.00 1.0000 2 11.80 1.0000
- 3 I 1.60 1.0000
- 4 11.40 1.0000
- 5 11.20 1.0000 6 11.00 1.2722 7 10.80 1.2648 8 10.60 1.2525 9 10.40 1.2396 10 10.20 1.2 194 11 10.00 1.2072 12 9.80 L 1872 13 9.60 L 1598 14 9.40 1.1 389 15 9 .20 L 11 94 16 9.00 1.102 1 17 8.80 1.0854 18 8.60 1.0750 19 8.40 1.076 1 20 8.20 1.0762 21 8.00 1.0792 22 7.80 7.60
- 1. 0803 1.0794 24 7.40 1.080 1 25 7.20 1.0788 26 7.00 1.0775 27 6.80 1.0776 28 6.60 1.0759 29 6.40 1.0740 30 6.20 1. 0724 31 6.00 1.0700 32 5.80 1.0667 33 5.60 1.0632 34 5.40 1.0622 35 5.20 1.066 1 36 5.00 1.0790 37 4 .80 1.09 14 38 4 .60 1.1 033 39 4.40 1.11 48 40 4 .20 1.1 254 41 4 .00 1.1 347 42 3.80 1.144 5 43 3.60 1.1 560 44 3.40 1.1697 45 3.20 1.1829 46 3.00 1.1 938 47 2.80 1.2 102 48 2.60 1.2385 49 2.40 1.1701 50 2.20 1.302.1 51 2.00 1.3369 52 1. 80 1.37 13 53 1.60 1.4050 54 1.40 1.4 .172 55 1.20 1.4 672 56 1.00 1.4953 57 0.80 1.0000 58 0.60 1.0000 59 0.40 1.0000 60 0.20 1.0000 61 0.00 1.0000
- Top and bottom 5 axial points excluded per Tcchnic.al Specification B3.2.l.
Page 10 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT l CYCLE 30 June 2019 Figure I Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 I 1/ (.552, 225) 1/
II""
200
, ~ (1, 187) -
175 ~ 1/
~ v
~ il"'"
BankC
= 150
~ 1/ ~
~
II' "0
.c ~
~ 1/ ~
~ 125 II'
~ 1/
(f) ~
=
'-" ~
(0, 114)
.8 il"'"
- ~ 100 0 1/*
c.. ~ Bank D
=
e.:
il"'"
~ 75 1/
~
~
_/
50 -
r
~
~
25 - ~
~
~ (.070, 0)
I I I I I 0 ' '
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of RATED THERMAL POWER Fully Withdrawn shall be the condition where control rods are at a position within the interval ::2:225 and
- 23 I steps withdrawn.
Note: The Rod Bank Lnse rtion Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip-to-tip distance of 128 steps.
Page II of 15
CORE OPERA TJNG LIMITS REPORT, FNP UNIT I CYCLE 30 June 2019 Figure 2 K(Z)- Normalized FQ(Z) as a Function of Core Height 1.2 0
co; eo.. 0.8 OJ) c
- i!
co;
~
Cl..
"0 4.1
.!::l co;
...0E 0.6 -
z Core Height (ft.) K(Z)
.--- 0.000 1.000 N
'-' 6.000 1.000
~
12.000 1.000 0.4 FQ = 2.50 0.2 - I 0
0 2 4 6 8 10 12 Core Height (feet)
Page 12 of 15
CORE OPERATING LIM ITS REPORT. FNP UNIT I CYCLE 30 June 2019 Figure 3 Axia l Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110
(-12, 100) (+9, 100) v 100 J
,..., UNACCEPTABLE I ~ U 'ACCE J>TABL E
\
1:1:: 90 f-- OPERATIO ' OPERATION -
I l -
/
~ ,----
~
vr 0 80 Q.,
~
...:l ACCF:JYrABLE OPERATIO
'1\
~
~ 70 1:1::
=
~
I v
E- 60 Q
~
E-
~ 50 0
(-25, 50) (+24, 50)
- R 40
~
~
0 Q., 30 20 10 0
-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 Axia l Flu x Difference (Delta I) %
Page 13 of 15
CORE OPERAT ING LIMITS REPORT, FNP UNIT I CYCLE 30 June 2019 Figure 4 Reactor Core Safety Limits 680 NACCEPTABL E I lo.....
I'- r-......
OP ERATIO I
660 - .......,
lo.... I'-I'-
I'- ......., ..........
I'-
I'- r-....
r-..... r-.....
640 t-.... ......., .......,
i"-- .......,
~J
!"'--- !"'--- r-...... 1'--M 1'--
.......... I'-
I'- !'--, 1'\ -v- 2425 psig x..... i'-- !"'--- .......... \ -a- 2235 psig 1'-- r-......
\
.......... I'- -..r- 1985 psig
!"'--- j--..,.-,
1'-- ' -.....
1'-- b-., 1\
-x- 1825 psig
""' ' "" ' i"--
\
1'-- r-....
600 i'-- "" .......,!"'--- r-......
I ACCEPTA BLE I !"'---
I OJ>ERATION I f'.....x 580 560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)
Page l4 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 30 June 2019 Figure 5 PREDICTED HFP 300 PPM MTC VS CYCLE BURN UP
- 23 . 5 1- *
+l d
Q)
'8 - 24 . 0 r--.... .........
- .-I 11-1 11-1 r--....
Q) .........
u 0 ........
Q) ........
1-1
- l
+l ........ ,____ 1--
I'd 1-1 ~
~ - 24 . 5 ...... I al 1- -
E-<
1-1 0
+l I'd ........
1-1 Q)
'0 ........ 1'-o..
~
- 25 . 0 16000 17000 18000 19000 20000 Cycle Burnup (MWD/MTU )
Cycle Burnup Moderator Temperature (MWD/ MTU) Coefficient (pcm/°F)
!6000 -23.95
!7000 -24.20
!8000 -24.43 19000 -24.69 20000 -24.9 1 Page 15 of 15