BYRON 2023-0012, Cycle 26 Core Operating Limits Report

Cycle 26 Core Operating Limits Report

ML23075A027
Person / Time
Site:	Byron
Issue date:	03/16/2023
From:	Welt H Constellation Energy Generation
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
BYRON 2023-0012
Download: ML23075A027 (1)

Text

,J 1111 Constellation, March 16, 2023 L TR:

BYRON 2023-0012 File:

5A.101 1 D.101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station Unit 1 Renewed Facility Operating License No. NPF-37 NRC Docket No. STN 50-454 Constellation Energy Generation, LLC (CEG)

Byron Station 4450 N, German Church Road Byron, IL 61010-9794 www,constellationenergy,com

Subject:

Byron Station Unit 1 Cycle 26 Core Operating Limits Report In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR),"

we are submitting the Unit 1 COLR, Revision 18, for Cycle 26.

Should you have any questions concerning this report, please contact Ms. Zoe Cox, Regulatory Assurance Manager, at (815) 406-2800.

Respectfully, Harris Welt Site Vice President Byron Generating Station

Attachment:

Byron Station Unit 1 Cycle 26, COLR, Revision 18 HW/JA/hh cc:

Regional Administrator-NRC Region Ill NRC Senior Resident Inspector-Byron Station

CORE OPERATING LIMITS REPORT (COLR)

FOR BYRON UNIT 1 CYCLE 26 CONSTELLATION TRACKING ID:

COLR BYRON UNIT 1 REVISION 18

COLRBYRON I Revision 18 Page I of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 26 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Byron Station Unit 1 Cycle 26 has been prepared in accordance with the requirements of Technical Specification 5.6.5 (ITS).

The Technical Specification Safety Limits and Limiting Conditions for Operation (LCOs) affected by this report are listed below:

SL 2.1.1 Reactor Core Safety Limits (SLs)

LCO 3.1.1 SHUTDOWN MARGIN (SOM)

LCO 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.4 Rod Group Alignment Limits LCO 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.6 Control Bank Insertion Limits LCO 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))

LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN,.,H)

LCO 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)

LCO 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.9 Boron Dilution Protection System (BOPS)

LCO 3.4.1 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.9.1 Boron Concentration The portions of the Technical Requirements Manual (TRM) affected by this report are listed below:

TRM TLCO 3.1.b TRM TLCO 3.1.d TRM TLCO 3.1.f TRM TLCO 3.1.g TRM TLCO 3.1.h TRM TLCO 3.1.i TRM TLCO 3.1.j TRM TLCO 3.1.k Boration Flow Paths - Operating Charging Pumps - Operating Borated Water Sources - Operating Position Indication System - Shutdown Shutdown Margin (SOM) - MODE 1 and MODE 2 with keff ~ 1.0 Shutdown Margin (SOM) - MODE 5 Shutdown and Control Rods Position Indication System - Shutdown (Special Test Exception)

COLRBYRON 1 Revision 18 Page 2 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 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 are applicable for the entire cycle unless otherwise identified. These limits have been developed using the NRG-approved methodologies specified in Technical Specification 5.6.5.

2.1 C

C s.......

Reactor Core Safety Limits (Sls) (SL 2.1.1) 2.1.1 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 limits specified in Figure 2.1.1.

2-P1 pshi 2250 p<-ia 2000 p;;ia

~----

1860 psia 58J-+-.....,___._...__-+---'--'---'--+---'--J..--'--+--'--'--'---+-'---'-........ --l--'---'----'----f 0

0.2 0.4 0.6 0.8 1.2 Fraction of Nominal Power Figure 2.1.1: Reactor Core Limits

COLR BYRON 1 Revision 18 Page 3 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 2.2 SHUTDOWN MARGIN (SOM) 2.3 2.4 2.5 The SOM limit for MODES 1, 2, 3, and 4 is:

2.2.1 The SOM shall be greater than or equal to 1.3% 6k/k (LCOs 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8, 3.3.9; TRM TLCOs 3.1.b, 3.1.d, 3.1.f, 3.1.h, and 3.1.j).

The SOM limit for MODE 5 is:

2.2.2 SOM shall be greater than or equal to 1.3% 6k/k (LCO 3.1.1, LCO 3.3.9; TRM TLCOs 3.1.i and 3.1.j).

Moderator Temperature Coefficient {MTC) (LCO 3.1.3)

The Moderator Temperature Coefficient (MTC) limits are:

2.3.1 The BOL/ARO/HZP-MTC upper limit shall be +2.550 x 10-5 6k/k/°F.

2.3.2 The EOL/ARO/HFP-MTC lower limit shall be -4.6 x 10-4 6k/k/°F.

2.3.3 The EOL/ARO/HFP-MTC Surveillance limit at 300 ppm shall be -3.7 x 10-4 6k/k/°F.

2.3.4 The EOL/ARO/HFP-MTC Surveillance limit at 60 ppm shall be -4.3 x 10-4 6k/k/°F.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life HFP stands for Hot Full Thermal Power Shutdown Bank Insertion Limits (LCO 3.1.5) 2.4.1 All shutdown banks shall be fully withdrawn to at least 224 steps.

Control Bank Insertion Limits (LCO 3.1.6) 2.5.1 The control banks, with Bank A greater than or equal to 224 steps, shall be limited in physical insertion as shown in Figure 2.5.1.

2.5.2 Each control bank shall be considered fully withdrawn from the core at greater than or equal to 224 steps.

2.5.3 The control banks shall be operated in sequence by withdrawal of Bank A, Bank B, Bank C and Bank D. The control banks shall be sequenced in reverse order upon insertion.

2.5.4 Each control bank not fully withdrawn from the core shall be operated with the following overlap limits as a function of park position:

Park Position (step)

Overlap Limit (step) 231 115

224 220 200 180 C:

3: 160 rn...

"C

.I::. -

~ 140 ti)

C.

QJ -

~ 120 C:

0 E

ti) 100 0

a.

.x:

C:

rn 80 OJ "C

0 0::

60 40 20 0

COLR BYRON 1 Revision 18 Page 4 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 26 Figure 2.5.1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power (27%, 224)

(77%, 224) 3/4 "'

r r

/ V V

/

/

VrsANK s I

~v V

/

1(0%, 163) I

/

/

(100%, 161)

/

IBANK CI

/

/

V

/

/

V

/

V !BANKO I

/ V

/

/

V

'lrn3/4, 47l I

/

~v j(30%.0)v 0

10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

The bank position is given as follows:

Control Bank D: (161/70) * (P-100) + 161 (for 30 :5 P :5 100)

Where P is defined as the core power (in percent).

2.6 N

0 LL "C

(I) n:s E

0 z N

~

COLRBYRON 1 Revision 18 Page 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 Heat Flux Hot Channel Factor (Fa(Z)) (LCO 3.2.1) 2.6.1 Total Peaking Factor:

1.2 (0.0 1.0 0.8 0.6 0.4 0.2 0.0 pRTP F0 (Z) ~-0-xK(Z) for P ~ 0.5 0.5 pRTP F0 (Z) ~ xK(Z) for P > 0.5 p

where: P = the ratio of THERMAL POWER to RATED THERMAL POWER Fam= 2.60 K(Z) is provided in Figure 2.6.1.

Figure 2.6.1 K(Z) - Normalized F0(Z) as a Function of Core Height

, 1.0)

(6.0, 1.0)

(12.0, 1.0)

--LOCA Limiting l Envelope 0

2 4

6 8

10 12 BOTTOM Core Height (ft)

TOP

COLR BYRON 1 Revision 18 Page 6 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 2.6.2 W(Z) Values:

a) When the Power Distribution Monitoring System (PDMS) is OPERABLE, W(Z) = 1.00000 for all axial points.

b) When PDMS is inoperable, W(Z) is provided as:

1) Table 2.6.2.a are the normal operation W(Z) values that correspond to the NORMAL AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.a. The Normal AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values.

2) Table 2.6.2.b are the Expanded normal operation W(Z) values that correspond to the EXPANDED AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits provided in Figure 2.8.1.b. The Expanded AFD Acceptable Operation Limits may be invoked at any time and must be used with the corresponding W(Z) values.

Table 2.6.2.c shows the Foc(Z) penalty factors that are greater than 2% per the allowable surveillance frequency. These values shall be used to increase the Fow(Z) as per Surveillance Requirement 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 2.6.2.c.

Table 2.6.2.d contains the required operating space reduction values for THERMAL POWER and AXIAL FLUX DIFFERENCE (AFD) when Fow(z) is not within its limits. These values are used in conjunction with Technical Specification LCO 3.2.1 Required Actions B.1 and B.2.

2.6.3 Uncertainty

The uncertainty, UFO, to be applied to the Heat Flux Hot Channel Factor Fo(Z) shall be calculated by the following formula l/ F(J = [/ (JI/

• l/ (!

where:

Uqu = Base Fo measurement uncertainty= 1.05 when PDMS is inoperable (Uqu is defined by PDMS and cannot be less than 1.05 when OPERABLE.)

Ue = Engineering uncertainty factor= 1.03 2.6.4 PDMS Alarms:

Fo(Z) Warning Setpoint = 2% Fo(Z) Margin Fo(Z) Alarm Setpoint = 0% Fo(Z) Margin

COLR BYRON I Revision 18 Page 7 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 Table 2.6.2.a W(Z) versus Core Height for Normal AFD Acceptable Operation Limits in Figure 2.8.1.a (Top and Bottom 8% Excluded per Byron SR 3.2.1.2 Bases)

Height 150 6000 14000 (feet)

MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.2373 1.3435 1.2553 0.20 1.2318 1.3333 1.2491 0.40 1.2335 1.3299 1.2541 0.60 1.2392 1.3303 1.2602 0.80 1.2499 1.3342 1.2725 1.00 1.2511 1.3277 1.2749 1.20 1.2433 1.3134 1.2680 1.40 1.2315 1.2948 1.2568 1.60 1.2195 1.2752 1.2454 1.80 1.2065 1.2540 1.2329 2.00 1.1921 1.2313 1.2189 2.20 1.1767 1.2076 1.2039 2.40 1.1610 1.1838 1.1886 2.60 1.1457 1.1607 1.1733 2.80 1.1289 1.1363 1.1568 3.00 1.1202 1.1275 1.1461 3.20 1.1203 1.1261 1.1426 3.40 1.1209 1.1234 1.1412 3.60 1.1212 1.1208 1.1414 3.80 1.1211 1.1177 1.1435 4.00 1.1210 1.1142 1.1466 4.20 1.1213 1.1099 1.1488 4.40 1.1224 1.1053 1.1505 4.60 1.1228 1.1043 1.1514 4.80 1.1228 1.1044 1.1515 5.00 1.1220 1.1056 1.1508 5.20 1.1213 1.1068 1.1490 5.40 1.1218 1.1072 1.1462 5.60 1.1237 1.1076 1.1431 5.80 1.1274 1.1107 1.1419 6.00 1.1375 1.1163 1.1451 6.20 1.1531 1.1221 1.1557 6.40 1.1663 1.1266 1.1642 6.60 1.1782 1.1330 1.1729 6.80 1.1887 1.1413 1.1803 7.00 1.1976 1.1517 1.1857 7.20 1.2045 1.1629 1.1893 7.40 1.2095 1.1726 1.1909 7.60 1.2126 1.1811 1.1904 7.80 1.2119 1.1882 1.1879 8.00 1.2134 1.1938 1.1832 8.20 1.2202 1.1980 1.1783 8.40 1.2249 1.2008 1.1767 8.60 1.2324 1.2014 1.1753 8.80 1.2398 1.2046 1.1766 9.00 1.2502 1.2173 1.1841 9.20 1.2644 1.2398 1.1977 9.40 1.2716 1.2657 1.2136 9.60 1.2743 1.3002 1.2331 9.80 1.2892 1.3369 1.2528 10.00 1.3146 1.3711 1.2702 10.20 1.3341 1.4032 1.2856 10.40 1.3449 1.4314 1.3018 10.60 1.3562 1.4557 1.3168 10.80 1.3704 1.4764 1.3201 11.00 1.3889 1.4968 1.3204 11.20 1.3955 1.5109 1.3204 11.40 1.3358 1.4859 1.2872 11.60 1.2860 1.4644 1.2501 11.80 1.2814 1.4719 1.2454 12.00 (core top) 1.2750 1.4823 1.2314 Note: W(Z) values at 22000 MWD/MTU may be applied to cycle burn ups greater than 22000 MWD/MTU to prevent W(Z) function extrapolation 22000 MWD/MTU 1.1861 1.1785 1.1806 1.1884 1.2032 1.2087 1.2034 1.1941 1.1853 1.1760 1.1657 1.1547 1.1435 1.1323 1.1215 1.1095 1.1042 1.1125 1.1234 1.1363 1.1495 1.1617 1.1728 1.1827 1.1911 1.1980 1.2028 1.2059 1.2100 1.2156 1.2248 1.2361 1.2449 1.2523 1.2575 1.2599 1.2596 1.2567 1.2509 1.2427 1.2310 1.2183 1.2107 1.2096 1.2139 1.2245 1.2335 1.2389 1.2425 1.2520 1.2686 1.2865 1.3008 1.3121 1.3224 1.3288 1.3243 1.2896 1.2481 1.2456 1.2330

COLR BYRON 1 Revision 18 Page 8 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 Table 2.6.2.b W(Z) versus Core Height for Expanded AFD Acceptable Operation Limits in Figure 2.8.1.b (Top and Bottom 8% Excluded per Byron SR 3.2.1.2 Bases)

Height 150 6000 14000 (feet)

MWD/MTU MWD/MTU MWD/MTU 0.00 (core bottom) 1.3530 1.4323 1.3444 0.20 1.3456 1.4208 1.3381 0.40 1.3458 1.4163 1.3400 0.60 1.3503 1.4160 1.3466 0.80 1.3598 1.4192 1.3585 1.00 1.3589 1.4113 1.3597 1.20 1.3484 1.3953 1.3512 1.40 1.3334 1.3748 1.3382 1.60 1.3179 1.3530 1.3247 1.80 1.3011 1.3295 1.3098 2.00 1.2825 1.3043 1.2933 2.20 1.2626 1.2777 1.2754 2.40 1.2422 1.2513 1.2570 2.60 1.2218 1.2290 1.2384 2.80 1.1997 1.2069 1.2184 3.00 1.1865 1.1897 1.2042 3.20 1.1827 1.1788 1.1973 3.40 1.1787 1.1712 1.1924 3.60 1.1742 1.1686 1.1893 3.80 1.1692 1.1661 1.1875 4.00 1.1629 1.1627 1.1857 4.20 1.1573 1.1590 1.1830 4.40 1.1546 1.1547 1.1795 4.60 1.1510 1.1497 1.1752 4.80 1.1467 1.1441 1.1698 5.00 1.1418 1.1378 1.1642 5.20 1.1362 1.1309 1.1590 5.40 1.1302 1.1232 1.1528 5.60 1.1252 1.1137 1.1444 5 80 1.1269 1.1130 1.1442 6.00 1.1352 1.1163 1.1528 6.20 1.1452 1.1223 1.1632 6.40 1.1537 1.1278 1.1715 6.60 1.1618 1.1366 1.1797 6.80 1.1702 1.1457 1.1867 7.00 1.1789 1.1555 1.1915 7.20 1.1874 1.1664 1.1944 7.40 1.1944 1.1758 1.1953 7.60 1.1997 1.1838 1.1940 7.80 1.2035 1.1905 1.1909 8.00 1.2055 1.1956 1.1848 8.20 1.2059 1.1993 1.1783 8.40 1.2046 1.2016 1.1769 8.60 1.2008 1.2018 1.1747 8.80 1.2007 1.2048 1.1769 9.00 1.2060 1.2181 1.1855 9.20 1.2235 1.2406 1.1993 9.40 1.2452 1.2664 1.2197 9.60 1.2637 1.3008 1.2414 9.80 1.2812 1.3374 1.2621 10.00 1.2999 1.3715 1.2809 10.20 1.3152 1.4033 1.2975 10.40 1.3217 1.4314 1.3148 10.60 1.3289 1.4555 1.3310 10.80 1.3392 1.4759 1.3344 11.00 1.3543 1.4961 1.3351 11.20 1.3569 1.5100 1.3368 11.40 1.2994 1.4847 1.3033 11.60 1.2587 1.4630 1.2606 11.80 1.2587 1.4703 1.2511 12.00 (core top) 1.2587 1.4804 1.2299 Note: W(Z) values at 22000 MWD/MTU may be applied to cycle burn ups greater than 22000 MWD/MTU to prevent W(Z) function extrapolation 22000 MWD/MTU 1.3016 1.2917 1.2923 1.2991 1.3133 1.3170 1.3092 1.2970 1.2849 1.2720 1.2577 1.2422 1.2261 1.2097 1.1927 1.1775 1.1728 1.1810 1.1878 1.1941 1.2011 1.2076 1.2127 1.2163 1.2181 1.2196 1.2209 1.2205 1.2224 1.2310 1.2448 1.2585 1.2691 1.2767 1.2814 1.2830 1.2815 1.2767 1.2691 1.2568 1.2464 1.2409 1.2334 1.2311 1.2282 1.2266 1.2298 1.2404 1.2465 1.2582 1.2755 1.2888 1.2991 1.3071 1.3124 1.3179 1.3158 1.2747 1.2267 1.2245 1.2103

COLR BYRON I Revision 18 Page 9 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 Table 2.6.2.c Penalty Factors in Excess of 2%

Cycle Burnup Penalty Factor (MWD/MTU)

Foc(Z) 0 1.0200 592 1.0250 1034 1.0350 1917 1.0400 2138 1.0400 2580 1.0450 3464 1.0450 4127 1.0400 4568 1.0250 4789 1.0200 7440 1.0200 7600 1.0260 8100 1.0280 8600 1.0280 9500 1.0230 9650 1.0200 21359 1.0200 21580 1.0220 21801 1.0230 24987 1.0230 Notes:

Linear interpolation is adequate for intermediate cycle burnups.

All cycle burnups outside the range of Table 2.6.2.c shall use a 2% penalty factor for compliance with the 3.2.1.2 Surveillance Requirements.

Table 2.6.2.d Required Operating Space Reduction When Fow(Z) Exceeds Its Limits Required Fow(Z)

THERMAL POWER Negative AFD Band Positive AFD Band Marqin Improvement Reduction (% RTP)

Reduction (% AFD)

Reduction (% AFD)

5 1%

c

3%

1%

1%

>1%AND:52%

c

6%

2%

2%

> 2% AND :5 3%

c

9%

c

3%

c

3%

>3%

50%

NIA NIA

2.7 COLRBYRON 1 Revision 18 Page 10 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 Nuclear Enthalpy Rise Hot Channel Factor (FNtiH) (LCO 3.2.2) where: P = the ratio of THERMAL POWER to RATED THERMAL POWER (RTP)

F~~P = 1.70 PFtiH = 0.3

2.7.2 Uncertainty

The uncertainty, UFtiH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FNtiH shall be calculated by the following formula:

UFtiH = UFtiHm where:

UFtJHm = Base FNtiH measurement uncertainty= 1.04 when PDMS is inoperable (UFtiHm is defined by PDMS and cannot be less than 1.04 when OPERABLE.)

2.7.3 PDMS Alarms:

FNtiH Warning Setpoint = 2% FNtiH Margin FNtiH Alarm Setpoint = 0% FNtiH Margin 2.8 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3) 2.9 2.8.1 The AXIAL FLUX DIFFERENCE (AFD) Acceptable Operation Limits are provided in the Figures described below.

a) Figure 2.8.1.a is the Normal AFD Acceptable Operation Limits associated with the W(Z) values in Table 2.6.2.a. These limits may be modified in accordance with Table 2.6.2.d if LCO 3.2.1 Required Actions B.1 and B.2 must be taken. Prior to changing to Figure 2.8.1.a, confirm that the plant is within the specified AFD envelope.

b) Figure 2.8.1.b is the Expanded AFD Acceptable Operation Limits associated with the W(Z) values in Table 2.6.2.b.

These limits may be modified in accordance with Table 2.6.2.d if LCO 3.2.1 Required Actions B.1 and B.2 must be taken.

Departure from Nucleate Boiling Ratio {DNBR) (LCO 3.2.5) 2.9.1 DNBRAPSL;;: 1.563 The Axial Power Shape Limiting DNBR (DNBRAPSL) is applicable with THERMAL POWER

50% RTP when PDMS is OPERABLE.

2.9.2 PDMS Alarms:

DNBR Warning Setpoint = 2% DNBR Margin DNBR Alarm Setpoint = 0% DNBR Margin

COLR BYRON 1 Revision 18 Page 11 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 26 Figure 2.8.1.a:

-50

-40 Normal Axial Flux Difference Limits as a Function of Rated Thermal Power Normal Axial Flux Difference Limits

-30

-20

-10 0

10 20 AXIAL FLUX DIFFERENCE{%}

30 40 50

COLR BYRON 1 Revision 18 Page 12 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 Figure 2.8.1.b:

120 Expanded Axial Flux Difference Limits as a Function of Rated Thermal Power Expanded Axial Flux Difference Limits

(-15, 100) 100 l---- -+--------------f-,,,,,,,,,,, __,,,,_,........... -~

... *k---,,,,,,,,t----------- +,,,_, __,,_,,,,,,+-------------,

~ 80.l _

U n~cce pta b-+_e __ ---,,1'--f---------*-*-,~-------,.---------1---~*----+---------+------*----,

0, eration

...I

<(

~

0::

w

c

~

0 w I I I

60 I

~ 40,, ______,_,,_,

0::

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL FLUX DIFFERENCE(%)

COLR BYRON l Revision 18 Page 13 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT I CYCLE 26 2.10 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overtemperature ll T Setpoint Parameter Values 2.10.1 The Overtemperature ll T reactor trip setpoint K1 shall be equal to 1.325.

2.10.2 The Overtemperature ll T reactor trip setpoint Tavg coefficient K2 shall be equal to 0.0297 I °F.

2.10.3 The Overtemperature ll T reactor trip setpoint pressure coefficient K3 shall be equal to 0.00135 I psi.

2.10.4 The nominal Tavg at RTP (indicated) T' shall be less than or equal to 588.0 °F.

2.10.5 The nominal RCS operating pressure (indicated) P' shall be equal to 2235 psig.

2.10.6 The measured reactor vessel ll T lead/lag time constant T1 shall be equal to 8 sec.

2.10. 7 The measured reactor vessel ll T lead/lag time constant T2 shall be equal to 3 sec.

2.10.8 The measured reactor vessel ll T lag time constant T3 shall be less than or equal to 2 sec.

2.10.9 The measured reactor vessel average temperature lead/lag time constant T4 shall be equal to 33 sec.

2.10.10 The measured reactor vessel average temperature lead/lag time constant T5 shall be equal to 4 sec.

2.10.11 The measured reactor vessel average temperature lag time constant T6 shall be less than or equal to 2 sec.

2.10.12 The f1 (lll) "positive" breakpoint shall be +10% L1.I.

2.10.13 The f1 (lll) "negative" breakpoint shall be -18% L1.I.

2.10.14 The f1 (lll) "positive" slope shall be +3.47% / % L1.I.

2.10.15 The f1 (lll) "negative" slope shall be -2.61 % / % L1.I.

COLR BYRON 1 Revision 18 Page 14 of 15 CORE OPERA TING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 2.11 Reactor Trip System (RTS) Instrumentation (LCO 3.3.1) - Overpower 6 T Setpoint Parameter Values 2.11.1 The Overpower 6 T reactor trip setpoint K4 shall be equal to 1.072.

2.11.2 The Overpower 6 T reactor trip setpoint Tav9 rate/lag coefficient Ks shall be equal to 0.02 I °F for increasing Tavg.

2.11.3 The Overpower 6 T reactor trip setpoint Tav9 rate/lag coefficient Ks shall be equal to 0 I °F for decreasing Tav9.

2.11.4 The Overpower 6 T reactor trip setpoint Tavg heatup coefficient K6 shall be equal to 0.00245 I °F when T > T".

2.11.5 The Overpower 6 T reactor trip setpoint Tav9 heatup coefficient Ke shall be equal to 0 / °F when T :s: T".

2.11.6 The nominal Tavg at RTP (indicated) T" shall be less than or equal to 588.0 °F.

2.11. 7 The measured reactor vessel 6 T lead/lag time constant,1 shall be equal to 8 sec.

2.11.8 The measured reactor vessel 6 T lead/lag time constant,2 shall be equal to 3 sec.

2.11.9 The measured reactor vessel 6 T lag time constant,3 shall be less than or equal to 2 sec.

2.11.10 The measured reactor vessel average temperature lag time constant,6 shall be less than or equal to 2 sec.

2.11.11 The measured reactor vessel average temperature rate/lag time constant,7 shall be equal to 10 sec.

2.11.12 The f2 (61) "positive" breakpoint shall be 0 for all 61.

2.11.13 The f2 (61) "negative" breakpoint shall be 0 for all 61.

2.11.14 The f2 (61) "positive" slope shall be 0 for all 61.

2.11.15 The f2 (61) "negative" slope shall be 0 for all 61.

COLR BYRON 1 Revision 18 Pagel 5 of 15 CORE OPERATING LIMITS REPORT (COLR) for BYRON UNIT 1 CYCLE 26 2.12 Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (LCO 3.4.1) 2.12.1 The pressurizer pressure shall be greater than or equal to 2209 psig.

2.12.2 The RCS average temperature (Tavg) shall be less than or equal to 593.1 °F.

2.12.3 The RCS total flow rate shall be greater than or equal to 386,000 gpm.

2.13 Boron Concentration 2.13.1 The refueling boron concentration shall be greater than or equal to the applicable value given in the Table below (LCO 3.9.1). The reported "prior to initial criticality" value also bounds the end-of-cycle requirements for the previous cycle.

2.13.2 To maintain keff -s: 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or 5 (TRM TLCO 3.1.g Required Action 8.2 and TRM TLCO 3.1.k.2), the Reactor Coolant System boron concentration shall be greater than or equal to the applicable value given in the Table below.

COLR Conditions Boron Concentration Section (ppm) 2.13.1 a) prior to initial criticality 1758 b) for cycle burnups 2- 0 MWD/MTU 1899 and < 16000 MWD/MTU c) for cycle burnups 2-16000 1540 MWD/MTU 2.13.2 a) prior to initial criticality 1838 b) for cycle burnups 2- 0 MWD/MTU 2145 and < 16000 MWD/MTU c) for cycle burnups 2-16000 1682 MWD/MTU