NL-22-0887, Cycle 32 Core Operating Limits Report

Cycle 32 Core Operating Limits Report

ML22327A227
Person / Time
Site:	Farley
Issue date:	11/21/2022
From:	Gayheart C Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NL-22-0887
Download: ML22327A227 (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 November 21, 2022 Docket No.:

50-348 NL-22-0887 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Cycle 32 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 1 Cycle 32 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 1 Cycle 32 Version 1 cc: Regional Administrator, Region ll NRR Project Manager - Farley Nuclear Plant Senior Resident Inspector - Farley Nuclear Plant RTYPE: CFA04.054

~ Southern Nuclear

Joseph M. Farley Nuclear Plant - Unit 1 Cycle 32 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 1 Cycle 32 Version 1

Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 - Cycle 32 Version 1 June 2022 SOUTHERI\\I <<\\

COMPANY Energy to Serve Your World$

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 32 June 2022 Page 1 of 15 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 CYCLE 32 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 1 CYCLE 32 June 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 1 CYCLE 32 June 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 1 CYCLE 32 June 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 1 CYCLE 32 June 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 1 CYCLE 32 June 2022 Page 6 of 15 Table 1 FQ(Z) Penalty Factor Cycle Burnup (MWD/MTU)

FQ(Z) Penalty Factor 2643 1.0200 2851 1.0201 3059 1.0200 7838 1.0200 8045 1.0300 8253 1.0281 8461 1.0262 8669 1.0243 8877 1.0225 9084 1.0207 9292 1.0200 10331 1.0200 10539 1.0277 10746 1.0277 10954 1.0276 11162 1.0274 11370 1.0270 11578 1.0257 11785 1.0242 11993 1.0224 12201 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 1 CYCLE 32 June 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 1 CYCLE 32 June 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 1 CYCLE 32 June 2022 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 1.1740 1.2261 1.2207 1.2089 1.2217 1.2361 7

10.80 1.1754 1.2215 1.2229 1.2113 1.2183 1.2241 8

10.60 1.1751 1.2148 1.2190 1.2061 1.2125 1.2158 9

10.40 1.1747 1.2074 1.2166 1.2049 1.2060 1.2091 10 10.20 1.1728 1.2006 1.2129 1.1975 1.1997 1.2030 11 10.00 1.1692 1.1958 1.2115 1.1947 1.1972 1.1972 12 9.80 1.1648 1.1951 1.2195 1.1910 1.1953 1.1909 13 9.60 1.1629 1.1925 1.2214 1.1866 1.1994 1.1842 14 9.40 1.1648 1.1874 1.2197 1.1814 1.2064 1.1785 15 9.20 1.1662 1.1806 1.2131 1.1796 1.2091 1.1917 16 9.00 1.1650 1.1727 1.2134 1.1865 1.2212 1.2030 17 8.80 1.1627 1.1616 1.2110 1.1878 1.2263 1.2092 18 8.60 1.1706 1.1561 1.2165 1.1948 1.2305 1.2117 19 8.40 1.1811 1.1642 1.2281 1.2089 1.2426 1.2206 20 8.20 1.1888 1.1720 1.2360 1.2196 1.2606 1.2406 21 8.00 1.1947 1.1778 1.2413 1.2279 1.2744 1.2570 22 7.80 1.1985 1.1817 1.2442 1.2339 1.2852 1.2705 23 7.60 1.1997 1.1832 1.2439 1.2372 1.2928 1.2811 24 7.40 1.1993 1.1834 1.2421 1.2390 1.2985 1.2899 25 7.20 1.1969 1.1815 1.2366 1.2371 1.2995 1.2939 26 7.00 1.1936 1.1788 1.2290 1.2335 1.2971 1.2945 27 6.80 1.1892 1.1751 1.2201 1.2293 1.2929 1.2946 28 6.60 1.1829 1.1697 1.2093 1.2233 1.2862 1.2926 29 6.40 1.1757 1.1633 1.1970 1.2157 1.2772 1.2883 30 6.20 1.1678 1.1562 1.1837 1.2065 1.2658 1.2814 31 6.00 1.1588 1.1481 1.1695 1.1961 1.2529 1.2729 32 5.80 1.1489 1.1393 1.1545 1.1848 1.2387 1.2631 33 5.60 1.1382 1.1297 1.1434 1.1726 1.2226 1.2517 34 5.40 1.1280 1.1228 1.1310 1.1660 1.2083 1.2451 35 5.20 1.1304 1.1303 1.1223 1.1681 1.2076 1.2441 36 5.00 1.1374 1.1358 1.1265 1.1689 1.2042 1.2409 37 4.80 1.1435 1.1413 1.1297 1.1690 1.2003 1.2361 38 4.60 1.1493 1.1461 1.1329 1.1679 1.1967 1.2293 39 4.40 1.1543 1.1503 1.1355 1.1658 1.1921 1.2205 40 4.20 1.1584 1.1537 1.1376 1.1627 1.1862 1.2101 41 4.00 1.1617 1.1566 1.1389 1.1587 1.1792 1.1983 42 3.80 1.1641 1.1602 1.1404 1.1530 1.1697 1.1833 43 3.60 1.1657 1.1638 1.1420 1.1458 1.1587 1.1653 44 3.40 1.1666 1.1664 1.1429 1.1388 1.1511 1.1498 45 3.20 1.1685 1.1702 1.1439 1.1338 1.1432 1.1383 46 3.00 1.1791 1.1861 1.1502 1.1336 1.1439 1.1332 47 2.80 1.1920 1.2069 1.1609 1.1420 1.1565 1.1406 48 2.60 1.2120 1.2261 1.1726 1.1548 1.1709 1.1541 49 2.40 1.2344 1.2524 1.1915 1.1671 1.1851 1.1677 50 2.20 1.2567 1.2813 1.2125 1.1798 1.1995 1.1838 51 2.00 1.2790 1.3096 1.2326 1.1916 1.2125 1.1984 52 1.80 1.3010 1.3375 1.2524 1.2031 1.2251 1.2122 53 1.60 1.3220 1.3641 1.2715 1.2147 1.2378 1.2264 54 1.40 1.3420 1.3894 1.2898 1.2262 1.2507 1.2408 55 1.20 1.3610 1.4129 1.3070 1.2373 1.2633 1.2550 56 1.00 1.3785 1.4343 1.3228 1.2481 1.2757 1.2692 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 1 CYCLE 32 June 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 1.2880 7

10.80 1.2813 8

10.60 1.2713 9

10.40 1.2594 10 10.20 1.2428 11 10.00 1.2225 12 9.80 1.1969 13 9.60 1.1725 14 9.40 1.1522 15 9.20 1.1337 16 9.00 1.1141 17 8.80 1.0986 18 8.60 1.0963 19 8.40 1.0971 20 8.20 1.0973 21 8.00 1.0972 22 7.80 1.0970 23 7.60 1.0946 24 7.40 1.0932 25 7.20 1.0909 26 7.00 1.0888 27 6.80 1.0873 28 6.60 1.0840 29 6.40 1.0806 30 6.20 1.0770 31 6.00 1.0720 32 5.80 1.0665 33 5.60 1.0606 34 5.40 1.0541 35 5.20 1.0612 36 5.00 1.0738 37 4.80 1.0856 38 4.60 1.0972 39 4.40 1.1083 40 4.20 1.1187 41 4.00 1.1277 42 3.80 1.1374 43 3.60 1.1466 44 3.40 1.1551 45 3.20 1.1646 46 3.00 1.1823 47 2.80 1.2025 48 2.60 1.2294 49 2.40 1.2591 50 2.20 1.2886 51 2.00 1.3202 52 1.80 1.3512 53 1.60 1.3810 54 1.40 1.4095 55 1.20 1.4363 56 1.00 1.4615 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 1 CYCLE 32 June 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)

~'

I I I I I 1..,-

i.,

r

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~

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~

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i.,

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1,11"'

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r I I I I I

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 32 June 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 1 CYCLE 32 June 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 I

__ I I

\\

r-

_____ J

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L __

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I

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CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 32 June 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 I.._

le...._

.......... r--...

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CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 32 June 2022 Page 15 of 15 Figure 5 Predicted HFP 300 ppm MTC versus Cycle Burnup Cycle Burnup Moderator Temperature (MWD/MTU)

Coefficient (pcm/°F) 15000

-24.91 16000

-25.15 17000

-25.44 18000

-25.71 19000

-25.96

-26.5

-26.0

-25.5

-25.0 16000 17000 18000 19000 Moderator Temperature Coefficient (pcm/°F)

Cycle Burnup (MWD/MTU) 1"""'-....... ~,...

1"""'-r-,..._

.......... I",,,.._

r-,.....