NL-23-0908, Cycle 30 Core Operating Limits Report
| ML23347A159 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/13/2023 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NL-23-0908 | |
| Download: ML23347A159 (1) | |
Text
Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 December 13, 2023 Docket No.:
50-364 NL-23-0908 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 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 (COLR) for the Joseph M.
Farley Nuclear Plant (FNP) - Unit 2 Cycle 30 Version 1.
This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.
Respectfully submitted, Jamie Coleman Regulatory Affairs Director JC/was/cbg
Enclosure:
Core Operating Limits Report for FNP Unit 2 Cycle 30 Version 1 cc: Regional Administrator, Region ll NRR Project Manager - Farley Nuclear Plant Senior Resident Inspector - Farley Nuclear Plant RTYPE: CFA04.054
Joseph M. Farley Nuclear Plant - Unit 2 Cycle 30 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 2 Cycle 30 Version 1
Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 - Cycle 30 Version 1 July 2023
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 1 of 15 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 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 1 and 2 (with keff t1)
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 keff < 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 - ()
3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor -
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
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 2 of 15 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 as specified in Technical Specification 5.6.5.
2.1 SHUTDOWN MARGIN - MODES 1 and 2 (with keff t1.0) (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 keff < 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (keff < 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.
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 3 of 15 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOL/ARO-MTC shall be less than or equal to +0.7 x 10-4 'k/k/qF for power levels up to 70 percent RTP with a linear ramp to 0 'k/k/qF at 100 percent RTP.
The EOL/ARO/RTP-MTC shall be less negative than -4.3 x 10-4 'k/k/qF.
2.3.2 The MTC Surveillance limits are:
The 300 ppm/ARO/RTP-MTC should be less negative than or equal to
-3.65 x 10-4 'k/k/qF.
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 pcm/°F or (¨AFD
- AFD Sensitivity)}
ZKHUH ¨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 pcm/°)¨AFD
- Predictive Correction is -3 pcm/°F.
The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 10-4'k/k/qF.
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.
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 4 of 15 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 1.
2.6 Heat Flux Hot Channel Factor - () (Specification 3.2.1) 2.6.1
()
()
for P > 0.5
()
. ()
for P d 0.5 where:
=
2.6.2
= 2.50 2.6.3 K(Z) is provided in Figure 2.
2.6.4
()
()
()
for P > 0.5
()
()
.()
for P d 0.5 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 () penalty factors are provided in Table 1.
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 5 of 15 2.7 Nuclear Enthalpy Rise Hot Channel Factor -
(Specification 3.2.2) 2.7.1
1 + (1 )
where:
=
2.7.2
= 1.70 2.7.3
= 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 1 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.
2.11 Reactor Trip System Instrumentation Overtemperature T (OTT) and Overpower T (OPT)
Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature T (OTT) and Overpower T (OPT) setpoint parameter values for TS 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 t 2209 psig;
- b. RCS average temperature d 580.3qF; and
- c. The minimum RCS total flow rate shall be t 273,900 GPM when using the precision heat balance method and t 274,800 GPM when using the elbow tap method.
1 This concentration bounds the condition of keff d 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 B10 depletion.
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 6 of 15 Table 1 FQ(Z) Penalty Factor Cycle Burnup (MWD/MTU)
FQ(Z) Penalty Factor 0
1.0200 22000 1.0200 Notes:
- 1. The Penalty Factor, to be applied to () in accordance with SR 3.2.1.2, is the maximum factor by which () 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 () 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.
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 7 of 15 Table 2 Reactor Trip System Instrumentation - Overtemperature 'T (OT'T)
Setpoint Parameter Values Tc d 577.2qF Pc = 2235 psig K1 = 1.17 K2 = 0.017/qF K3 = 0.000825/psi W1 t 30 sec W2 d 4 sec W4 = 0 sec W5 d 6 sec W6 d 6 sec f1('I) =
-2.48 {23 + (qt - qb)}
when (qt - qb) d -23% RTP 0% of RTP when -23% RTP < (qt -qb) d 15% RTP 2.05 {(qt - qb) - 15}
when (qt - qb) > 15% RTP
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 8 of 15 Table 3 Reactor Trip System Instrumentation - Overpower 'T (OP'T)
Setpoint Parameter Values Tcc d 577.2qF K4 = 1.10 K5 = 0.02/qF for increasing Tavg K6 = 0.00109/qF when T > Tcc K5 = 0/qF for decreasing Tavg K6 = 0/qF when T d Tcc W3 t 10 sec W4 = 0 sec W5 d 6 sec W6 d 6 sec f2('I) = 0% RTP for all 'I
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 9 of 15 Table 4 RAOC W(Z)
Axial Point Elevation (feet) 150 MWD/MTU 3000 MWD/MTU 6000 MWD/MTU 10000 MWD/MTU 14000 MWD/MTU 18000 MWD/MTU 1
12.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 2
11.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 3
11.60 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
11.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6
11.00 1.1716 1.1937 1.2132 1.2511 1.2218 1.2373 7
10.80 1.1686 1.1899 1.2171 1.2475 1.2174 1.2304 8
10.60 1.1640 1.1842 1.2138 1.2414 1.2098 1.2173 9
10.40 1.1590 1.1780 1.2116 1.2346 1.2044 1.2000 10 10.20 1.1535 1.1710 1.2082 1.2274 1.1860 1.1908 11 10.00 1.1475 1.1672 1.2030 1.2196 1.1877 1.1849 12 9.80 1.1485 1.1679 1.1967 1.2149 1.1944 1.1829 13 9.60 1.1491 1.1666 1.2007 1.2209 1.2020 1.1811 14 9.40 1.1475 1.1630 1.2030 1.2259 1.2031 1.1788 15 9.20 1.1442 1.1577 1.2005 1.2257 1.2154 1.1770 16 9.00 1.1397 1.1514 1.2021 1.2337 1.2238 1.1817 17 8.80 1.1330 1.1422 1.2007 1.2354 1.2270 1.1891 18 8.60 1.1330 1.1380 1.2096 1.2405 1.2295 1.1932 19 8.40 1.1432 1.1464 1.2214 1.2547 1.2401 1.2052 20 8.20 1.1531 1.1553 1.2299 1.2652 1.2557 1.2256 21 8.00 1.1613 1.1623 1.2356 1.2727 1.2674 1.2419 22 7.80 1.1676 1.1675 1.2390 1.2775 1.2764 1.2554 23 7.60 1.1714 1.1703 1.2393 1.2791 1.2824 1.2660 24 7.40 1.1739 1.1719 1.2380 1.2788 1.2867 1.2749 25 7.20 1.1745 1.1715 1.2332 1.2743 1.2864 1.2793 26 7.00 1.1745 1.1705 1.2262 1.2671 1.2837 1.2802 27 6.80 1.1733 1.1683 1.2179 1.2583 1.2802 1.2809 28 6.60 1.1702 1.1645 1.2077 1.2474 1.2745 1.2797 29 6.40 1.1663 1.1597 1.1961 1.2346 1.2666 1.2762 30 6.20 1.1618 1.1543 1.1834 1.2201 1.2566 1.2703 31 6.00 1.1561 1.1478 1.1698 1.2046 1.2450 1.2629 32 5.80 1.1495 1.1405 1.1554 1.1881 1.2321 1.2542 33 5.60 1.1419 1.1327 1.1447 1.1727 1.2174 1.2440 34 5.40 1.1348 1.1305 1.1328 1.1601 1.2035 1.2380 35 5.20 1.1441 1.1387 1.1245 1.1582 1.2034 1.2380 36 5.00 1.1511 1.1453 1.1286 1.1581 1.2014 1.2361 37 4.80 1.1580 1.1517 1.1319 1.1587 1.1984 1.2327 38 4.60 1.1642 1.1574 1.1352 1.1582 1.1939 1.2273 39 4.40 1.1697 1.1626 1.1379 1.1567 1.1879 1.2201 40 4.20 1.1742 1.1668 1.1400 1.1542 1.1807 1.2113 41 4.00 1.1779 1.1703 1.1417 1.1510 1.1724 1.2011 42 3.80 1.1806 1.1727 1.1423 1.1462 1.1619 1.1878 43 3.60 1.1832 1.1759 1.1424 1.1400 1.1496 1.1722 44 3.40 1.1863 1.1789 1.1430 1.1333 1.1365 1.1554 45 3.20 1.1912 1.1857 1.1440 1.1267 1.1267 1.1433 46 3.00 1.2073 1.2002 1.1512 1.1188 1.1270 1.1395 47 2.80 1.2329 1.2201 1.1662 1.1271 1.1360 1.1446 48 2.60 1.2598 1.2400 1.1826 1.1413 1.1468 1.1596 49 2.40 1.2862 1.2657 1.1988 1.1546 1.1595 1.1759 50 2.20 1.3129 1.2945 1.2154 1.1683 1.1726 1.1920 51 2.00 1.3395 1.3229 1.2315 1.1810 1.1844 1.2065 52 1.80 1.3657 1.3509 1.2473 1.1934 1.1957 1.2202 53 1.60 1.3905 1.3775 1.2624 1.2056 1.2073 1.2342 54 1.40 1.4139 1.4025 1.2788 1.2177 1.2189 1.2485 55 1.20 1.4358 1.4257 1.2950 1.2292 1.2303 1.2625 56 1.00 1.4559 1.4468 1.3099 1.2403 1.2416 1.2765 57 0.80 1.0000 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 excluded per Technical Specification B3.2.1.
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 10 of 15 Table 5 Part Power (48%) RAOC W(Z)
Axial Point Elevation (feet) 150 MWD/MTU 1
12.00 1.0000 2
11.80 1.0000 3
11.60 1.0000 4
11.40 1.0000 5
11.20 1.0000 6
11.00 1.2806 7
10.80 1.2677 8
10.60 1.2532 9
10.40 1.2384 10 10.20 1.2220 11 10.00 1.2145 12 9.80 1.2017 13 9.60 1.1772 14 9.40 1.1582 15 9.20 1.1335 16 9.00 1.1061 17 8.80 1.0854 18 8.60 1.0750 19 8.40 1.0750 20 8.20 1.0778 21 8.00 1.0796 22 7.80 1.0818 23 7.60 1.0820 24 7.40 1.0825 25 7.20 1.0831 26 7.00 1.0844 27 6.80 1.0848 28 6.60 1.0845 29 6.40 1.0841 30 6.20 1.0817 31 6.00 1.0795 32 5.80 1.0755 33 5.60 1.0697 34 5.40 1.0655 35 5.20 1.0769 36 5.00 1.0863 37 4.80 1.0979 38 4.60 1.1095 39 4.40 1.1208 40 4.20 1.1313 41 4.00 1.1401 42 3.80 1.1497 43 3.60 1.1598 44 3.40 1.1698 45 3.20 1.1818 46 3.00 1.2048 47 2.80 1.2375 48 2.60 1.2712 49 2.40 1.3048 50 2.20 1.3395 51 2.00 1.3748 52 1.80 1.4095 53 1.60 1.4429 54 1.40 1.4756 55 1.20 1.5078 56 1.00 1.5385 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 Technical Specification B3.2.1.
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 11 of 15 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive Fully Withdrawn shall be the condition where control rods are at a position within the interval t 225 and d 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.
0 25 50 75 100 125 150 175 200 225 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Rod Bank Position (Steps Withdrawn)
Fraction of RATED THERMAL POWER Bank D
(.070, 0)
(1, 187)
Bank C (0, 114)
(.552, 225)
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 12 of 15 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 0
0.2 0.4 0.6 0.8 1
1.2 0
2 4
6 8
10 12 K(Z) - Normalized Peaking Factor Core Height (feet)
Core Height (ft.)
0.000 6.000 12.000 K(Z) 1.000 1.000 1.000 FQ = 2.50
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 13 of 15 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC
(-12, 100)
(-25, 50)
(+9, 100)
(+24, 50) 0 10 20 30 40 50 60 70 80 90 100 110 120
-60
-50
-40
-30
-20
-10 0
10 20 30 40 50 60 Power (% of RATED THERMAL POWER)
Axial Flux Difference (Delta I) %
UNACCEPTABL E OPERATION UNACCEPTABL E OPERATION UNACCEPTABLE OPERATION UNACCEPTABLE OPERATION ACCEPTABLE OPERATION
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 14 of 15 Figure 4 Reactor Core Safety Limits 560 580 600 620 640 660 680 0
0.2 0.4 0.6 0.8 1
1.2 Tavg (degree F)
Power (Fraction of RATED THERMAL POWER) 2425 psig 2235 psig 1985 psig 1831 psig UNACCEPTABLE OPERATION ACCEPTABLE OPERATION
CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 30 July 2023 Page 15 of 15 Figure 5 Predicted HFP 300 ppm MTC versus Cycle Burnup Cycle Burnup Moderator Temperature (MWD/MTU)
Coefficient (pcm/°F) 16000
-25.11 17000
-25.36 18000
-25.60 19000
-25.85 20000
-26.08
-26.5
-26.0
-25.5
-25.0 16000 17000 18000 19000 20000 Moderator Temperature Coefficient (pcm/°F)
Cycle Burnup (MWD/MTU)