NL-19-0361, Core Operating Limits Report, Cycle 21, Version 1

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Core Operating Limits Report, Cycle 21, Version 1
ML19112A090
Person / Time
Site: 05000426
Issue date: 04/22/2019
From: Gayheart C
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-19-0361
Download: ML19112A090 (16)
v • d • e


Text

~ Southern Nuclear Cheryl A. Gayheart Regulatory Affa1rs Director 3535 Colonnade Parkway B1rm1ngham, AL 35243 205 992 5316 tel 205 992 7601 fax cagayhea@ southernco.com APR 2 2 2019 Docket Nos.: 50-426 NL-19-0361 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant- Unit 2 Core Operating Limits Report. Cycle 21. Version 1 Ladies and Gentlemen:

In accordance with Technical Specification (TS) 5.6.5.d for Vogtle Electric Generating Plant (VEGP), Southern Nuclear Operating Company (SNC) submits the VEGP Core Operating Limits Report (COLR for Unit 2, Cycle 21, Version 1).

This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992-6611.

Respectfully submitted, Cheryl . ayheart Regulatory Affairs Director CAG/kgl/sm

Enclosure:

VEGP Unit 2 COLR, Cycle 21, Version 1 Cc: Regional Administrator NRR Project Manager- Vogtle 1 & 2 Senior Resident Inspector- Vogtle 1 & 2 RType: CVC7000

Vogtle Electric Generating Plant - Unit 2 Core Operating Limits Report, Cycle 21, Version 1 Enclosure VEGP Unit 2 COLR, Cycle 21, Version 1

VOGTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 2 CYCLE 21 CORE OPERATING LIMITS REPORT Version 1 December 2018

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 21 DECEMBER 2018 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP Unit 2 Cycle 21 has been prepared in accordance with the requirements ofTechnical Specification 5.6.5.

The Technical Requirement affected by this report is listed below:

13.1.1 SHUTDOWN MARGIN - MODES I and 2 The Technical Specifications affected by this report are listed below:

3.l.l SHUTDOWN MARGIN - MODES 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 - Fo(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor- FN H 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration Page 1 of13

CORE OPERATfNG LIMITS REPORT. VEGP UNIT 2 CYCLE 21 DECEMBER2018 2.0 OPERATrNG 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 MARGrN - MODES I and 2 (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent ~k/k.

2.2 SHUTDOWN MARGrN - MODES 3. 4 and 5 (Specification 3.1.1) 2.2.1 The SHUTDOWN MARGrN shall be greater than or equal to the limits shown in Figures I and 2.

Page2 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 21 DECEMBER 2018 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOLIARO/HZP-MTC shall be less positive than +0.7 x 10-4 ~k/k/°F for power levels up to 70% RTP with a linear ramp to 0 ~k/k/°F at I 00% RTP.

The EOLIAROIRTP-MTC shall be less negative than -5.50 x 10-4 ~klk/°F. 1 2.3.2 The MTC Surveillance limits are:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to

-4.75 X 10-4 ~k/k/0 f. 1 The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 6 and the following algorithm:

Revised Predicted MTC Predicted MTC* + AFD Correction** + Predictive Correction***

where,

  • Predicted MTC is calculated from Figure 6 at the bumup corresponding to the measurement of 300 ppm at RTP conditions,
    • AFD Correction is the more negative value of:

{0 pcmrF or (~AFD

  • AFD Sensitivity)}

where: ~AFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the bumup corresponding to 300 ppm, AFD Sensitivity= 0.08 pcm/°F I ~AFD

      • Predictive Correction is -3 pcm/°F.

The 60 ppm/ARO/RTP-MTC should be less negative than -5.35 x 10-4 ~klk/°F. 1 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 RTP stands for RATED THERMAL POWER 1

Applicable for full-power T-average of 583.8 to 586.8 °F.

Page 3 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 21 DECEMBER 2018 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.

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 3.

2.6 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3.2.1)

F/171' 2.6.1 F 0 (Z) ~ __5L_

  • K(Z) for P > 0.5

- p FIll/'

F0 (Z) ~ __5L_

  • K(Z) for P ~ 0.5

- 0.5 THERMAL POWER where: p =----------

RATED THERMAL POWER 2.6.2 2.6.3 K(Z) is provided in Figure 4.

1111 F '

  • K(Z) 2.6.4 F (Z) < Q for P > 0.5 Q - p. W(Z)

FiliP

  • K(Z)

F (Z) < (} for P ~ 0.5 Q - 0.5

  • W(Z) 2.6.5 W(Z) values are provided in Table 2.

2.6.6 The F0 (Z) penalty factors are provided in Table I.

Page4 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 21 DECEMBER 2018 2.7 Nuclear Enthalpy Rise Hot Channel Factor- FN H (Specification 3.2.2) 2.7.1 F~ 5, F~"~' *(1+PFMI *(1 - P))

THERMAL POWER where: p =----------

RATED THERMAL POWER 2.7.2 F:/,~' = 1.65 2.7.3 Pf'.lll = 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 5.

2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm. 2 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 B 10 depletion.

Page 5 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 21 DECEMBER2018 Tablet F Q(Z) PENALTY FACTOR Bum up Penal ty (MWD/MTU) Factor 0 1.0298 150 1.0298 367 1.0284 584 1.0216 801 1.0348 1018 1.0426 1235 1.0434 1453 1.0443 1670 1.0452 1887 1.0418 2104 1.0335 2321 1.0259 2538 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 1.020 shall be used.

Page 6 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 21 DECEMBER2018 Table2 RAOCW(Z)

Axial Elevation ISO 4000 8000 12000 16000 20000 Point (feet) MWD/l\ITU MWD/MTU MWD/1\tTU MWD/MTll MWD/MTU MWD/MTU 1-3 12.072 - 11.669 I 0000 0000 I 0000 I 0000 I 0000 I 0000 4 11.468 I 3014 3489 I 2782 I 2732 I 1733 I 2077 5 11.261 I 3186 3837 I 2964 I 2785 I 1767 I 2064 6 11.066 I 3519 4323 I 3104 I 2772 I 1761 I 2003 7 10.865 I 3382 4275 I 3117 I 2713 I 1829 I 2058 8 10.664 I 3291 4072 12995 I 2559 I 1850 I 1881 9 10.462 13323 3921 I 2848 I 2361 I 1834 I 1756 10 10.261 I 3173 3722 I 2695 I 2218 I 1808 I 1754 II 10.060 12843 3337 I 2529 I 2035 I 1834 I 1755 12 9.859 I 2661 3074 I 2347 I 1963 I 1823 I 1751 13 9.658 I 2837 2923 I 2377 I 1914 I 1808 I 1742 14 9.456 12771 2607 I 2355 I 1851 I 1797 I 1735 15 9.255 I 2670 2573 I 2348 I 1794 I 1819 I 1836 16 9.054 12564 2578 I 2293 I 1757 I 1828 I 1981 17 8.853 I 2519 I 2538 I 2174 I 1695 I 1793 I 1996 18 8.652 I 2487 I 2515 I 2089 I 1664 I 1771 I 2079 19 8.450 12477 I 2416 I 2037 I 1731 I 1786 I 2220 20 8.249 I 2462 I 2323 I 1997 I 1795 I 1884 I 2345 21 8.048 I 2517 I 2246 I 1960 I 1837 I 1981 I 2498 22 7.847 I 2544 I 2173 I 1931 I 1862 I 2059 I 2622 23 7.646 I 2536 I 2144 I 1931 I 1867 I 2118 I 2721 H 7.444 I 2508 I 2085 I 1907 I 1862 I 2165 I 2802 25 7.243 I 2447 I 1996 I 1852 I 1825 I 2175 I 2832 26 1.042 I 2365 I 1887 I 1776 I 1768 I 2159 I 2825 27 6.841 12267 I 1767 I 1689 I 1704 I 2132 I 2801 28 6.640 I 2147 I 1630 I 1586 I 1628 I 2086 I 2753 29 6.438 I 2014 I 1481 I 1471 I 1568 I 2047 I 2678 30 6.231 I 1880 I 1355 I 1346 I 1504 I 1999 I 2583 31 6.036 I 1744 I 1297 I 1220 I 1439 I 1947 I 2479 32 5.835 I 1597 I 1236 I 1181 I 1367 I 1882 I 2360 33 5.634 I 1496 I 1173 I 1155 I 1364 I 1835 2250 34 5.432 1435 I 1160 I 1147 I 1447 I 1839 2199 35 5.231 1436 I 1180 I 1217 I 1540 I 1889 2215 36 5.030 1471 I 1261 I 1308 I 1623 I 1935 2236 37 4.829 1505 I 1331 I 1394 I 1700 I 1966 2258 38 4.628 1536 I 1399 I 1475 I 1766 I 1984 2271 39 4.426 1558 I 1461 I 1551 I 1824 I 1987 2266 40 4.225 1568 I 1516 I 1617 I 1869 I 1977 2244 41 4.024 1569 I 1564 I 1691 I 1907 I 1953 2207 42 3.823 1559 I 1606 I 1772 I 1924 I 1924 2143 43 3.622 1556 I 1637 I 1838 I 1957 I 1923 2055 44 3.420 1578 I 1679 I 1895 I 2006 I 1938 1961 45 3.219 1613 I 1732 I 1941 I 2034 I 1935 I 1865 46 3.018 1626 I 1795 I 2000 I 2093 I 1993 I 1847 47 2.817 1707 I 1987 I 2133 I 2186 I 2129 I 1963 48 2.616 1854 I 2223 I 2337 I 2293 I 2266 I 2105 49 2.414 I 2004 I 2450 I 2551 I 2433 I 2400 I 2242 50 2.213 I 2154 I 2684 I 2767 I 2582 I 2534 I 2379 51 2.012 I 2304 I 2915 12978 I 2721 I 2653 I 2497 52 1.811 I 2453 I 3144 I 3185 I 2856 I 2765 I 2609 53 1.610 I 2595 I 3361 I 3381 I 2988 I 2879 I 2724 54 1.408 I 2731 I 3566 I 3568 I 3117 I 2991 I 2843 55 1.207 I 2863 I 3758 I 3742 I 3240 I 3101 I 2961 56 1.006 I 2988 13932 I 3901 I 3357 I 3209 I 3082 57 0.805 I 3099 I 4082 I 4036 I 3457 I 3303 I 3190 58 0.604 I 3186 14198 I 4134 I 3523 I 3362 I 3260 59-61 0.402- 0.000 I 0000 I 0000 I 0000 I 0000 I 0000 I 0000 Top and Bottom 3 Points Excluded per Technical Specification 83.2.1.

These W(Z) values are consistent with Figure 5, and are valid over the HFP Tavg temperature range from 583.8 to 586.8°F.

Page 7 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 21 DECEMBER2018 FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED AND VENTED AND AT LEAST ONE REACTOR COOLANT PUMP RUNNING) 5.0 4.0 ACCEPTABLE OPERATING REGION

~

~ (2 00, .1 0)

~

<l 3.0 /

dP v v z /

H REQUIRED SHUTDOWN MARGIN! /

C!l /

a (1 00, .2 5)

/

/

/

~1::1 2.0 /

/

~ /

til

/

/'

!UNACCEPTABLE OPERATING REGION I

( 95 ( ' . 3 0) 1.0 0.0 0 SOD 1 000 15 00 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 8 ofl3

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 21 DECEMBER2018 FIGURE2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE) 5.0 (2 00, .9

~

v

.. v v ~

4.0 vv v

!ACCEPTABLE OPERATING REGION I

/

~

........ v v

~

/

0 1.1 0 10 20 30 40 50 60 70 80 90 1 0 POWER (% of Rated Thermal Power)

  • Fully withdrawn shall be the condition where control rods are at a position within the interval ~ 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 115 steps.

Page 10 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 2 I DECEMBER 20 I 8 FIGURE4 K(Z)- NORMALIZED Fo(Z) AS A FUNCTION OF CORE HEIGHT 1.4 1.2 PI 0

E-1 u

r:: 1. 0

~ -

~

Po 0. 8 FQ = 2.50

~

l"z1 CORE N

HT. K(Z)

~

0.00 1. 00

~ 0.6 6.00 1. 00 12.0 .925 N

to::

0.4 0.2 0.0 0 2 4 6 8 10 12 CORE HEIGHT (feet)

Page 11 of 13

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 21 DECEMBER 20 18 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF% RATED THERMAL POWER FORRAOC 120 110

(-15, 100) (+10, 100)

I 1 00 I ~

w u ~AC 'EP~ ABlE I \ UN cc PTJ! BLE Gl 90

~ I \

~

as 80 \

e Gl I \

~

E-1 70 IJ I A "'CE PTAl LE

\

'tl \

cu

-1..1 Cl Ill: 60 I \

11-1 I \

0 I 1\

50 Ill: l ( -30, 50) I (+26, 50)

~ 40 I 0

~

30 20 10 0

-50 -40 -30 -20 - 10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (percent ~ I)

Page 12 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 21 DECEMBER 2018 FIGURE 6 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

-27.5

~ -28 . 0 ....... :-.....

Ql

  • .-I 0 .......
  • .-I .......

lj.j I'...

lj.j Ql ....... :-.......

0 u ....... :-.......

Ql -28 . 5 1-1 ............

BIll i'-.

1-1 .......

Ql I'...

~

Ql E-t

-29.0 r....

i'-. .......

-29 . 5 17 000 18000 19000 20000 21000 Cycle Burnup (MWD/MTU)

Cycle Burnup Moderator Temperature Coefficient (MWD/MTU) (pcrn/°F) 17000 -28.00 18000 -28.30 19000 -28.57 20000 -28.86 21000 -29.14 Page 13 of13

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