NL-17-2053, Submittal of Cycle 26 Core Operating Limits Report
| ML17346B172 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/12/2017 |
| From: | Wheat J Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-17-2053 | |
| Download: ML17346B172 (18) | |
Text
~ Southern Nuclear Regulatory Affairs 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 205 992 5000 tel 205 992 7601 fax December 12, 2017 Docket Nos.: 50-348 NL-17-2053 50-364 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Unit 2 Cycle 26 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 2 Cycle 26 Version 1.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.
Respectfully submitted, Justin T. Wheat Regulatory Affairs Manager JTW/NDJ/CJ
Enclosure:
Core Operating Limits Report for FNP Unit 2 Cycle 26 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 2 Cycle 26 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 2 Cycle 26 Version 1
SOUTHERN*\
COMPANY Energy to Serve Your WOrtJ*
Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 - Cycle 26 Version 1 July 2017
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 26 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 1 and 2 (with ketr;?: 1)
The Technical Specifications affected by this report are listed below:
2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN- MODES 2 (with ketr< 1), 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~
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 1 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using NRC-approved methodologies, including those specified in Technical Specification 5.6.5.
2.1 SHUTDOWN MARGIN- MODES 1 and 2 (with Kef£ 2: 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent ~k/k.
2.2 SHUTDOWN MARGIN - MODES 2 (with kerr< 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (k.ff< 1.0), 3 and 4- The SHUTDOWN MARGIN shall be greater than or equal to 1. 77 percent ~k/k.
2.2.2 Mode 5 -The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent ~k/k.
Page 2 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOLIARO-MTC shall be less than or equal to +0.7 x 104 ilk/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 ilklk/°F at 100 percent RTP.
The EOLIARO/RTP-MTC shall be less negative than -4.3 x 10'4 ilk/k/°F.
2.3.2 The MTC Surveillance limits are:
The 300 pprn/AROIRTP-MTC should be less negative than or equal to
-3.65 X 10'4 flk/k/°F.
The revised predicted near-EOL 300 ppm MTC shall be calculated 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 pcrn/°F or (ilAFD
- AFD Sensitivity)}
where: ilAFD 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 pcrn/°F I ilAFD
- Predictive Correction is -3 pcrn/°F.
The 100 pprn/ARO/RTP-MTC should be less negative than -4.0 x 104 ilk/k/°F.
where: BOL stands for Beginning 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 LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure I.
2.6 Heat Flux Hot Channel Factor- FQ(Z) (Specification 3.2.1) for P > 0.5 for P :5 0.5 THERMAL POWER where: p = ----~-----
RATED THERMAL POWER 2.6.2 F~lTP =2.50 2.6.3 K(Z) is provided in Figure 2.
FRTP *K(Z) 2.6.4 F (Z) <-0 =---- - - for P> 0.5 Q - P*W(Z)
FRTP *K(Z)
F (Z) < ---'Q=------ for P :5 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 1.
Page 4 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July2017 2.7 Nuclear Enthalpy Rise Hot Channel Factor- F~ (Specification 3.2.2) 2.7.1 F~ ~ F~P *(1+ PFMI *(1- P))
THERMAL POWER where: p =-----------
RATED THERMAL POWER 2.7.2 2.7.3 PFMI =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. I 0. I In MODES I and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 4.
- 2. I I Reactor Trip System Instrumentation Overtemperature ~T (OT~T) and Overpower ~T (OP~T)
Setpoint Parameter Values for Table 3.3. I -I (Specification 3.3. I) 2.11. I The Reactor Trip System Instrumentation Overtemperature ~T (OT~T) and Overpower
~T (OP~T) setpoint parameter values forTS Table 3.3. I- I are listed in COLR Tables 2 and 3.
- 2. I 2 RCS DNB Parameters for Pressurizer Pressure. RCS Average Temperature, and RCS Total Flow Rate (Specification 3.4. I)
- 2. I2. I 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 kerr::; 0.95 (all rods in less the most reactive rod) and subcriticality (all rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and 8 10 depletion.
Page 5 of IS
CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 26 July 2017 Tablet FQ(Z) Penalty Factor Cycle Burnup FQ(Z) Penalty (MWD/MTU) Factor 0 1.0339 150 1.0339 354 1.0298 559 1.0248 763 1.0201 968 1.0200 6282 1.0200 6487 1.0242 6691 1.0293 6896 1.0321 7100 1.0295 7304 1.0267 7509 1.0239 7713 1.0210 7918 1.0200 Notes:
- 1. The Penalty Factor, to be applied to FQ(Z) in accordance with SR 3.2.1.2, is the maximum factor by which FQ(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) starting from the burnup at which the FQ(Z) was determined.
- 2. Linear interpolation is adequate for intermediate cycle burnups.
- 3. For all cycle burnups 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 2 CYCLE 26 July2017 Table2 Reactor Trip System Instrumentation- Overtemperature L\T (OTL\T)
Setpoint Parameter Values P' = 2235 psig K1 = 1.17 1<.3 = 0.000825/psi
'tl :2:30 sec -r2:S; 4 sec
't4 = 0 sec -rs:S; 6 sec h(t11) = -2.48 {23 + (qt- qb)} when (qt- qb) :S; -23 % RTP 0% ofRTP when -23% RTP < (qt -qb) :S; 15% RTP 2.05 {(qt- qb)- 15} when (qt- qb) > 15% RTP Page 7 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 Table3 Reactor Trip System Instrumentation- Overpower .dT (OP.dT)
Setpoint Parameter Values T" :::;; 577.2°F 1<4= 1.10 Ks = 0.02;oF for increasing Tavg 1<6 = 0.00109;oF when T > T" Ks = o;oF for decreasing Tavg K6 = o;oF when T :::;; T" t3~ 10 sec t4= 0 sec ts::;; 6 sec t6=:;; 6 sec fz(~I) = 0% RTP for all ~I Page 8 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 Table4 RAOCW(Z)
Axial Elevation 150 3000 6000 10000 14000 18000 Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 1 12.00 1.0000 I 0000 I 0000 I 0000 I 0000 I 0000 2 II 80 1.0000 I 0000 I 0000 I 0000 1.0000 1.0000 3 11.60 1.0000 1.0000 I 0000 I 0000 I 0000 I 0000 4 1140 1.0000 1.0000 I 0000 1.0000 I 0000 I 0000 5 11.20 1.0000 1.0000 I 0000 1.0000 I 0000 I 0000 6 II 00 1.1255 1.1449 12133 I 2457 I 2563 I 2149 7 10 80 I 1254 I 1465 I 2117 1.2474 I 2540 I 2067 8 10 60 I 1210 1.1427 I 2054 I 2405 1.2342 1.195 I 9 10 40 I 1195 1.1545 12114 1.2272 I 2216 I 1865 10 10 20 I 1208 1.1617 I 2177 I 2148 I 2148 I 1790 11 10 00 I 1302 1.1583 I 2146 1.2113 I 2081 I 1720 12 9 80 I 1357 I 1506 1.2077 I 2108 1.2009 1.1753 13 9 60 I 1384 1.1450 I 2029 I 2133 I 1934 I 1831 14 9 40 I 1402 I 1352 I 1918 I 2165 I 1887 I 1892 15 9.20 1.1384 1.1357 1.1925 I 2155 I 2009 I 1936 16 9 00 I 1418 I 1356 I 1904 I 2233 I 2094 I 2001 17 8 80 1.1423 I 1397 I 1863 I 2250 I 2128 I 2234 18 8 60 I 1464 I 1511 I 1885 1.230 I 1.2163 I 2459 19 8 40 I 1590 1.1612 I 1989 I 2436 I 2279 I 2661 20 8 20 I 1686 I 1697 I 2058 I 2535 1.2427 I 2854 21 8.00 I 1766 I 1763 I 2105 1.2605 1.2540 1.3013 22 7.80 1.1826 1.1809 1.2133 I 2649 I 2627 I 3138 23 7.60 I 1859 I 1830 I 2134 I 2663 12686 I 3229 24 7.40 I 1878 I 1838 I 2121 I 2659 I 2727 I 3299 25 7 20 I 1873 1.1821 I 2079 1.2615 1.2725 1.3315 26 7 00 I 1853 I 1787 12028 I 2545 I 2699 I 3293 27 6 80 I 1819 I 1741 I 1969 I 2460 I 2667 I 3250 28 6.60 1.1766 1.1679 I 1891 I 2355 I 2615 I 3183 29 6 40 I 1705 I 1607 I 1802 I 2233 I 2542 I 3089 30 6 20 I 1637 I 1528 I 1702 I 2095 I 2449 12968 31 6.00 I 1558 1.1439 1.1594 I 1947 I 2341 I 2831 32 5.80 I 1469 1.1342 I 1478 I 1791 I 2222 I 2680 33 5 60 I 1371 I 1273 I 1353 I 1646 I 2087 I 2506 34 540 I 1286 I 1303 I 1219 I 1577 1.1947 1.2308 35 5 20 I 1357 1.1417 1.1227 I 1588 I 1930 I 2294 36 5 00 I 1433 I 1518 1.1293 I 1588 I 1899 I 2256 37 4 80 I 1515 1.1616 I 1350 I 1581 I 1877 I 2230 38 4 60 I 1608 I 1708 1.1404 1.1563 1.1837 I 2181 39 4 40 I 1693 I 1794 I 1451 I 1537 I 1785 I 2115 40 4 20 I 1770 I 1870 1.1491 I 1501 I 1719 I 2033 41 4.00 1.1832 I 1938 I 1525 I 1458 I 1657 I 1937 42 3 80 I 1921 I 1995 I 1549 I 1397 I 1600 I 1813 43 3 60 I 2031 12061 1.1564 I 1340 1.1530 I 1656 44 3.40 I 2123 I 2142 1.1573 I 1320 1.1452 I 1538 45 3 20 I 2207 1.2223 1.1596 I 1298 I 1374 I 1441 46 3.00 I 2271 I 2290 I 1679 I 1312 I 1273 I 1381 47 2 80 I 2415 1.2513 I 1892 1.1431 1.1339 1.1465 48 2 60 1.2686 1.2826 1.2141 I 1577 I 1468 I 1622 49 2 40 I 2975 1.3136 1.2385 I 1718 I 1587 I 1771 50 2.20 I 3262 I 3450 1.2634 I 1863 I 1711 I 1924 51 2.00 I 3548 1.3762 1.2877 1.1997 1.1822 I 2060 52 I 80 I 3830 1.4068 13116 I 2128 1.1929 I 2189 53 1.60 I 4095 I 4357 13344 I 2257 I 2040 I 2323 54 1.40 1.4346 1.4629 1.3560 I 2382 I 2152 1.2460 55 I 20 I 4579 1.4881 13761 I 2503 I 2262 I 2596 56 1.00 I 4791 1.5107 1.3944 I 2617 I 2372 I 2733 57 0.80 1.0000 1.0000 I 0000 1.0000 I 0000 I 0000
- 58 0.60 I 0000 1.0000 I 0000 I 0000 I 0000 I 0000 59 0.40 1.0000 1.0000 I 0000 I 0000 1.0000 I 0000 60 0.20 1.0000 1.0000 I 0000 1.0000 1.0000 I 0000 61 0.00 1.0000 1.0000 I 0000 I 0000 I 0000 I 0000
- Top and bottom 5 axial points excluded per Technical Specification 83.2.1.
Page 9 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 TableS Part Power (48%) RAOC W(Z)
.. Axial Point 1
2 Elevation (feet) 12.00 II 80 150 MWD/MTU I 0000 I 0000
- 3 11.60 I 0000
- 4 11.40 I 0000
- 5 11.20 1.0000 6 11.00 I 1692 7 10.80 1.1626 8 10.60 I 1483 9 10.40 1.1372 10 10.20 I 1295 11 10.00 1.1289 12 9 80 I 1220 13 960 I 1115 14 940 I 1001 15 9 20 I 0867 16 9.00 1.0788 17 8.80 I 0704 18 860 I 0677 19 8 40 1.0733 20 8 20 1.0782 21 8 00 1.0814 22 7 80 I 0840 23 7 60 1.0844 24 7.40 1.0855 25 7 20 1.0857 26 7 00 1.0848 27 6 80 1.0816 28 6 60 I 0793 29 640 I 0776 30 6.20 1.0714 31 600 1.0674 32 5 80 1.0639 33 5 60 1.0613 34 5 40 1.0563 35 5 20 1.0675 36 5 00 I 0802 37 4.80 1.0939 38 4 60 I 1089 39 440 I 1226 40 4 20 I 1355 41 4 00 I 1473 42 3 80 I 1630 43 3.60 I 1811 44 3 40 I 1975 45 3 20 I 2131 46 3.00 1.2264 47 2 80 I 2477 48 2 60 1.2814 49 2 40 I 3173 50 2.20 1,3537 51 2 00 I 3913 52 1.80 14284 53 1.60 1.4640 54 140 14984 55 120 I 5310 56 I 00 I 5609 57 0 80 I 0000 58 0 60 I 0000 59 040 1.0000 60 0.20 I 0000 61 0 00 I 0000
- Top and bottom 5 axial points excluded per Technical Specification 83.2.1.
Page 10 oflS
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225
(.552, 225)
.~
'/
200
~
II' (1, 187) -
175
, '/
I~
, .I I"
Banke c iJI
./
150 ~
~
~
"0
.c ~ 1,1 i ~
I" II'
"'Q. 125
-= ,
~ 1,1
~
rJ:J (0, 114) II' c
- 100 iJI g.=
..:.=
'/ BankO c
== 75 ,
~
~
.I "0
==
I~
50 II'
- ~
'/
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
~ 231 steps withdrawn.
Note: The Rod Bank Insertion 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 11 of 15
CORE OPERATrNG LIMITS REPORT. FNP UNIT 2 CYCLE 26 July 2017 Figure 2 K(Z) -Normalized F Q(Z) as a Function of Core Height 1.2
- I.
Q u
co:
[;!;, 0.8
=
~
- i!
co:
qj g.
"CI qj
-; 0.6 E
I.
Q Core Height (ft.)
z K(Z) 0.000 1.000 N 6.000 1.000
- t 12.000 1.000 0.4 FQ =2.50 0.2 0 '
0 2 4 6 8 10 12 Core Height (feet)
Page 12 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 2 CYCLE 26 July 2017 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110
(-12, 100) (+9, 100)
I 100
..-. 90 UNACCEPTABLE OPERATION l ~ I UNACCEPTABLE OPERATION -
\
c:z:: 1--
J I I
~
~
v 0 80
=-
~
..J ACCEPTABLE
- r OPERATION 70 c
- z::
\
I
~
- c 1\
1\
F- 60 Q
~
F-50 I
...~
Q
(-25, 50) (+24, 50)
- R
,_ 40 Col
- 1:
=-
Q 30 20 10 0
-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 Axial Flux Difference (Delta I) %
Page 13 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 Figure 4 Reactor Core Safety Limits 680 UNACCEPTABLE OPERATION I
IO... I 660 r--... r-....
r--.....
lo... r--... ...........
r--... ........... ......~'--
I'-..
r--... r--... .............
r--... r-....
640 1'-....
r--... ............. ...........
............ r--... r--... ........
I'-.. ......... ""q_
.......... r--... ....... \ ---->--- 2425 psig X....
............ r--... .......... ............
r--... r-..... \ --o-- 2235 psig
'I'-.. ............
\
............. ........... -..r-1985 psig r--..... ........ ............
........ -x-1825 psig
............. \
')
~""'- ...........
I'-.. ....... I'-.. r........
600 ............. ...........
r----:-... ...........
I ACCEPTABLE I I'-.. ['..
I OPERATION I ~
580 560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)
Page 14 of 15
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 26 July 2017 Figure 5 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP
- 24 . 0
"'s" y
c.
~
r-..... .....
=
.y~ -24 . 5 E ~ .....
u Q
~
....... ~
...= """"' ....... ......
~
E c.
~
s ......
r-.....
~ -25 . 0
...E I. ~~
Q
'C
~
Q
- ....... ~
-25 . 5 16000 17000 18000 19000 20000 Cycle Burnup (MWD/MTU)
Cycle Burnup Moderator Temperature (MWD/MTU) Coefficient (Ecm/°F) 16000 -24.37 17000 -24.62 18000 -24.84 19000 -25.08 20000 -25.31 Page 15 of 15