NL-22-0388, Cycle 29 Core Operating Limits Report

Cycle 29 Core Operating Limits Report

ML22151A309
Person / Time
Site:	Farley
Issue date:	05/31/2022
From:	Gayheart C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-22-0388
Download: ML22151A309 (1)

Text

Cheryl A. Gayheart Regulatory Affairs Director 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5316 tel 205 992 7601 fax cagayhea@southernco.com May 31, 2022 Docket No.:

50-364 NL-22-0388 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 Cycle 29 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 29 Version 1.

This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.

Respectfully submitted, Cheryl A. Gayheart Regulatory Affairs Director CAG/was/cbg

Enclosure:

Core Operating Limits Report for FNP Unit 2 Cycle 29 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 29 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 2 Cycle 29 Version 1

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 - Cycle 29 Version 1 January 2022

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 29 January 2022 Page 1 of 15 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 29 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 29 January 2022 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 29 January 2022 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 29 January 2022 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 29 January 2022 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 29 January 2022 Page 6 of 15 Table 1 FQ(Z) Penalty Factor Cycle Burnup (MWD/MTU)

FQ(Z) Penalty Factor 566 1.0200 773 1.0264 981 1.0324 1189 1.0346 1397 1.0337 1605 1.0309 1812 1.0273 2020 1.0237 2228 1.0210 2436 1.0200 3267 1.0200 3475 1.0262 3683 1.0286 3890 1.0292 4098 1.0282 4306 1.0270 4514 1.0255 4722 1.0237 4929 1.0216 5137 1.0200 10332 1.0200 10540 1.0211 10748 1.0209 10956 1.0207 11164 1.0203 11371 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 29 January 2022 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 29 January 2022 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 29 January 2022 Page 9 of 15 Table 4 RAOC W(Z)

Axial Point Elevation (feet) 150 MWD/MTU 4000 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 1.1328 1.1634 1.2030 1.2429 1.2165 1.2644 7

10.80 1.1326 1.1606 1.2007 1.2400 1.2162 1.2542 8

10.60 1.1368 1.1563 1.1963 1.2343 1.2072 1.2348 9

10.40 1.1416 1.1507 1.1912 1.2332 1.2028 1.2122 10 10.20 1.1445 1.1543 1.1856 1.2314 1.1994 1.1886 11 10.00 1.1433 1.1532 1.1792 1.2282 1.1960 1.1775 12 9.80 1.1482 1.1538 1.1738 1.2239 1.1961 1.1750 13 9.60 1.1512 1.1525 1.1785 1.2274 1.2031 1.1741 14 9.40 1.1520 1.1492 1.1800 1.2313 1.2046 1.1728 15 9.20 1.1510 1.1444 1.1771 1.2304 1.2168 1.1728 16 9.00 1.1490 1.1386 1.1785 1.2376 1.2254 1.1837 17 8.80 1.1443 1.1299 1.1838 1.2388 1.2289 1.1905 18 8.60 1.1438 1.1256 1.1969 1.2436 1.2311 1.1944 19 8.40 1.1530 1.1330 1.2057 1.2564 1.2410 1.2054 20 8.20 1.1620 1.1412 1.2127 1.2654 1.2567 1.2266 21 8.00 1.1691 1.1475 1.2172 1.2713 1.2685 1.2437 22 7.80 1.1745 1.1522 1.2196 1.2747 1.2776 1.2580 23 7.60 1.1772 1.1549 1.2194 1.2749 1.2837 1.2695 24 7.40 1.1786 1.1564 1.2177 1.2733 1.2881 1.2793 25 7.20 1.1780 1.1560 1.2132 1.2676 1.2880 1.2845 26 7.00 1.1769 1.1550 1.2078 1.2593 1.2853 1.2862 27 6.80 1.1747 1.1532 1.2012 1.2496 1.2819 1.2875 28 6.60 1.1706 1.1499 1.1929 1.2379 1.2763 1.2868 29 6.40 1.1658 1.1458 1.1833 1.2244 1.2684 1.2837 30 6.20 1.1602 1.1411 1.1727 1.2094 1.2583 1.2782 31 6.00 1.1536 1.1354 1.1611 1.1934 1.2466 1.2709 32 5.80 1.1461 1.1290 1.1488 1.1767 1.2336 1.2622 33 5.60 1.1377 1.1233 1.1358 1.1618 1.2187 1.2515 34 5.40 1.1305 1.1329 1.1272 1.1580 1.2041 1.2374 35 5.20 1.1370 1.1415 1.1306 1.1579 1.2039 1.2353 36 5.00 1.1452 1.1496 1.1367 1.1567 1.2017 1.2336 37 4.80 1.1536 1.1572 1.1423 1.1555 1.1986 1.2302 38 4.60 1.1614 1.1641 1.1474 1.1552 1.1939 1.2249 39 4.40 1.1686 1.1704 1.1519 1.1539 1.1877 1.2178 40 4.20 1.1747 1.1758 1.1557 1.1517 1.1803 1.2091 41 4.00 1.1799 1.1802 1.1588 1.1486 1.1717 1.1990 42 3.80 1.1844 1.1851 1.1615 1.1440 1.1610 1.1860 43 3.60 1.1881 1.1907 1.1646 1.1380 1.1481 1.1701 44 3.40 1.1910 1.1948 1.1676 1.1316 1.1375 1.1567 45 3.20 1.1922 1.2014 1.1694 1.1248 1.1302 1.1473 46 3.00 1.1986 1.2130 1.1769 1.1211 1.1291 1.1384 47 2.80 1.2213 1.2260 1.1857 1.1287 1.1377 1.1471 48 2.60 1.2485 1.2369 1.2050 1.1421 1.1509 1.1633 49 2.40 1.2746 1.2604 1.2282 1.1549 1.1637 1.1790 50 2.20 1.3013 1.2880 1.2512 1.1680 1.1767 1.1948 51 2.00 1.3279 1.3147 1.2738 1.1803 1.1884 1.2090 52 1.80 1.3542 1.3412 1.2960 1.1923 1.1996 1.2224 53 1.60 1.3791 1.3664 1.3172 1.2043 1.2110 1.2361 54 1.40 1.4029 1.3902 1.3374 1.2161 1.2226 1.2501 55 1.20 1.4252 1.4124 1.3562 1.2274 1.2339 1.2639 56 1.00 1.4456 1.4325 1.3735 1.2382 1.2451 1.2777 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 29 January 2022 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 1.1630 7

10.80 1.1602 8

10.60 1.1580 9

10.40 1.1547 10 10.20 1.1475 11 10.00 1.1360 12 9.80 1.1286 13 9.60 1.1182 14 9.40 1.1056 15 9.20 1.0929 16 9.00 1.0799 17 8.80 1.0652 18 8.60 1.0572 19 8.40 1.0588 20 8.20 1.0619 21 8.00 1.0650 22 7.80 1.0676 23 7.60 1.0679 24 7.40 1.0670 25 7.20 1.0676 26 7.00 1.0688 27 6.80 1.0676 28 6.60 1.0665 29 6.40 1.0656 30 6.20 1.0619 31 6.00 1.0592 32 5.80 1.0562 33 5.60 1.0532 34 5.40 1.0525 35 5.20 1.0644 36 5.00 1.0781 37 4.80 1.0924 38 4.60 1.1066 39 4.40 1.1195 40 4.20 1.1315 41 4.00 1.1428 42 3.80 1.1551 43 3.60 1.1671 44 3.40 1.1777 45 3.20 1.1867 46 3.00 1.2004 47 2.80 1.2306 48 2.60 1.2651 49 2.40 1.2989 50 2.20 1.3338 51 2.00 1.3699 52 1.80 1.4057 53 1.60 1.4406 54 1.40 1.4742 55 1.20 1.5057 56 1.00 1.5342 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 29 January 2022 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 29 January 2022 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 29 January 2022 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 29 January 2022 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 29 January 2022 Page 15 of 15 Figure 5 Predicted HFP 300 ppm MTC versus Cycle Burnup Cycle Burnup Moderator Temperature (MWD/MTU)

Coefficient (pcm/°F) 16000

-24.84 17000

-25.11 18000

-25.42 19000

-25.68 20000

-25.96

-26.0

-25.5

-25.0

-24.5 16000 17000 18000 19000 20000 Moderator Temperature Coefficient (pcm/°F)

Cycle Burnup (MWD/MTU)