NL-18-1356, Core Operating Limits Report, Cycle 22, Version 1

Core Operating Limits Report, Cycle 22, Version 1

ML18303A397
Person / Time
Site:	Vogtle
Issue date:	10/30/2018
From:	Gayheart C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-18-1356
Download: ML18303A397 (16)

Text

A Southern Nuclear Cheryl A. Gayheart Regulatory Affairs Director 3535 Colonnade Parkway Birmingham. AL 35243 205 992 5316 tel 205 992 7601 fax OCT 3 0 2018 cagayhea@southernco.com Docket No.: 50-424 NL-18-1356 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant- Unit 1 Core Operating Limits Report. Cycle 22, Version1 Ladies and Gentlemen:

In accordance with Technical Specifications (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 1, Cycle 22, Version 1.

This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.

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

Enclosure:

VEGP Unit 1 COLR, Cycle 22, Version 1 Cc: Regional Administrator NRR Project Manager- Vogtle 1 & 2 Senior Resident Inspector- Vogtle 1 & 2 RType: CVC7000

Vogtle Electric Generating Plant - Unit 1 Core Operating Limits Report, Cycle 22, Version 1 ENCLOSURE to NL-18-1356 Vogtle Electric Generating Plant (VEGP) Unit 1 Cycle 22 Core Operating Limits Report Version 1

VOGTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 1 CYCLE 22 CORE OPERATING LIMITS REPORT Version 1 June 2018

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYC LE 22 JUNE2018 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP Unit I Cycle 22 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 I and 2 The Technical Specitications affected by this report are listed below:

3.1.1 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- FNL\11 3.2.3 Axial Flux Difference 3.9. 1 Boron Concentration Page I of 13

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYC LE 22 JUNE 2018 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 including those specified in Technical Specification 5.6.5 .

2.1 SHUTDOWN MARGIN- 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 MARGIN- MODES 3, 4 and 5 (Specification 3.1.1) 2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1 and 2.

Page 2 of 13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 22 JUNE 2018 Moderator Tem perature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOLl ARO/HZP-MTC shall be less positive than 0. 7 x I o-4 ~k/k/° F for power levels up to 70% RTP with a linear ramp to 0 ~klk/° F at 100% RTP.

The EOLIARO/RTP-MTC shall be less negative than -5.50 X I 0'4 ~k/k/° F . I 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 1o--~ ~klki° 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 burnup corresponding to the measurement of 300 ppm at RTP conditions,

• • AFD Correction is the more negative value of:

{0 pcmr F or (~AFD

• AFD Sensitivity)}

where: ~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 = 0.08 pcmr F I ~AFD

• • • Predictive CorTection is -3 pcmr F.

4 The 60 ppm/ARO/RTP-MTC should be less negative than -5 .35 x 10" ~k/k/° 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 584.1 to 587.1 °F.

Page 3 of 13

CORE OPERATING LIMITS REPORT. VEGP UN IT I CYCLE 22 JUNE 2018 2.4 Shutdown Bank Insertion Limits (Specification 3. I .5) 2.4. I The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.

2. 5 Control Bank Insertion Limits (Specification 3. I .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 - F0 (Z) (Specification 3.2.1)

FRTf' 2.6. I FQ (Z) :s; _ Q

_

• K(Z) for P > 0.5 p

FRTf' FQ(Z) :s; ~

• K(Z) for P :s; 0.5 0.5 THERMAL POWER where: p =- - - - - - - - - -

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

FRTf'. K(Z) 2.6.4 F (Z) < Q for P > 0.5 Q - P*W(Z)

FRTf'. K(Z)

F (Z) < Q 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.

Page 4 of 13

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYCLE 22 JUNE 2018 2.7 Nuclear Enthal pv Rise Hot Channel Factor- FN '" (Specitication 3.2.2) where: p =- -THERMAL

---

POWER RATED THERMAL POWER 2.7.3 PFMI =0.3 2.8 Axial Flux Difference (Specitication 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. ~

This concentration bounds the condition of k., 1T:::> 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 8 10 depletion.

Page 5 of 13

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYC LE 22 JUNE ?018 Table 1 FQ(Z) PENALTY FACTOR Burn up Penalty (MWD/MTU) Factor 0 1.0421 150 1.0421 368 1.0562 585 1.0601 803 1.0613 1020 1.0592 1238 1.0516 1456 1.0433 1673 1.0347 1891 1.0264 2108 1.0200 8419 1.0200 8636 1.0203 8854 1.0222 9071 1.0221 9289 1.0209 9507 1.0200 Notes:

1. The Penalty Factor, to be applied to Fo(Z) in accordance with SR 3.2 . 1.2, is the maximum factor by which Fo(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 Fo(Z) was detennined.

2. Linear interpolation is adequate for intermediate cycle burnups.

3. For all cycle bumups outside the range of the table, a penalty factor of 1.020 shall be used.

Page 6 of 13

CORE OPERATING LIMITS REPORT, YEGP UNIT I CYCLE 22 JUNE 2018 Table 2 RAOC W(Z)

Axial Elc\ltlion 150 4000 8000 12000 16000 20000 Poi nt (feet) 1\IWD/i\IT U MWD/i\ITU MWD/i\ITU MWD/MTU MWD/i\ITU MWD/MTU 1-5 12.072 - 11 .267 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 11.066 1.~888 1.3603 \.}6~9 1.}570 1.2289 1.2306 7 10.865 1.~776 1.3455 1.2633 1.~595 1.2317 1.:!3 13 8 10.664 1.~611 1.32}6 1.}582 1.~5:!2 1.2131 1.}169 9 10.462 1. ~ 433 1.3015 1.~579 1.}410 1.1900 1.1981 10 10.261 1.::!239 1.}780 1.2496 1.}319 1.1885 1.1861 II 10.060 1.~0 3 6 1.~55::! 1.}446 1.~309 1.1876 1.1885 12 9.859 1.19'1 \.}299 1.2361 1.::!312 1.1894 1.1909 u 9.658 1.1915 1.}006 1.}260 1.~239 1.1866 1.1943 14 9.456 1.187 1 1.1 78} 1.~ 131 1.~168 1.1876 1.1975 15 9.255 \.1M3 1.1 73 7 1.}015 1.~161 1.1926 1.1996 16 9.054 1.1853 1.1 702 1.1916 1.~118 1.1979 1.}020 11 8.853 1.1910 1.1666 1.1806 1.1977 1.2035 1.2059 18 8.652 1.196~ 1.1648 1.1778 1.1911 1.}087 1.:!243 19 8.450 1.~001 1.1691 1.1842 1.1941 1.}167 1.2375 20 8.249 1.~030 1.17}3 1.1871 1.1969 1.2274 1.}511 21 8.048 1.~040 1.1735 Ll882 1.2048 1.2369 1.2628 22 7.847 1.~05~ 1.173 3 1.1876 1.}103 1.2443 1.2730 23 7.646 1.~053 1.1708 1.1849 1.2136 1.}493 1.}846 24 7.444 1.~033 1.1673 1.18 11 1.2153 1.::!531 1.2935 25 7.243 1.1986 1.1613 1.1745 1.}133 1.2525 1.2969 26 7.042 1.1921 1.1540 1.1662 1.2088 1.2491 1.}962 27 6.841 1.1843 1.1460 1.1571 1.}030 1.2443 1.2935 28 6.640 1.1746 1.1393 1.1489 1.1954 1.2379 1.}883 29 6.438 1.1048 1.13~6 1.1409 1.1862 1.::!3::!0 1.2802 30 6.23 1.1598 1.1261 1.1333 1.1767 1.}248 1.2691 31 6.036 1.1547 1.1219 1.1251 1.1664 \.}166 1.~563 32 5.835 1.1485 1.1192 1.12}0 1.1584 1.2070 1.2445 33 5.634 1.14}7 1.1169 1.1187 1.1556 1.199} 1.~359 34 5.432 1.1409 1.1 249 1.1193 1.1571 1.1949 1.:!303 35 5.231 1.1407 1.1366 1.1299 1.1619 1.1969 1.~299 36 5.030 1.1427 1.1474 j_J 391 1.1660 1.1980 1.}292 37 4.829 1.1511 1.1578 1.1480 1.1712 1.2000 1.2288 38 4.628 1.1584 1.1677 1.1564 1.1751 1.2004 1.}270 39 4.426 1.165} 1.1769 1.1641 1.1781 1.1993 1.2231 40 4.225 1.1710 1.1852 1.1709 1.1797 1.197} 1.~185 41 4.024 1.1758 1.19}7 1.1771 1.1812 1.1953 1.} 142 42 3.823 1.180 I 1.1995 1.18~ 2 1.18}2 1.1918 1.}069 43 3.622 1.1833 1.~048 1.1885 1.1816 1.1862 1.1970 44 3.420 1.1873 1.21 ~3 1.1952 1.1807 1.1803 1.1869 45 3.219 1.19~9 1.2216 1.200.1 1.1785 1.1735 1.1754 46 3.018 1.1976 1.2356 1.2062 1.1839 1.1780 1.1773 47 2.81 7 1.} 13} 1.}532 1.2125 1.1968 1.189} 1.1892 48 2.616 1.}331 1.~761 1.2281 1.}094 1.2000 1.2012 49 2.414 1.}518 1.3015 1.2466 1.2219 1.}108 1.} 133 50 2.113 1.}707 1.3173 1.2655 1.}344 1.}217 1.2254 51 2.012 1.}896 1.3530 1.2845 \.}459 1.2311 1.}357 52 1.811 1.3081 1.3783 1.3032 1.2568 1.2400 1.2454 53 1.610 1.3256 1.4022 1.3209 1.}676 1.}494 1.}558 54 1.408 1.34~2 1.4247 1.33 78 1.}782 1.}589 1.2666 55 1.20 1.3579 1.4456 1.3534 1.2883 1.}684 1.}776 56 1.006 1.37~4 1.4644 1.3677 1.2980 1.}779 1.}890 57-61 0.805 - 0.000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 Top and Bottom 5 Points Excluded per Technical Specification 83.2.1.

These W(Z) values are consistent with Figure 5, and are valid over the HFP Ta"g temperature range from 584. I to 587.1 °F.

Page 7 of 13

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYCLE 2? JUNE ?018 FIGURE 1 REQUIRED SHUTDOWN l\IARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED AND VENTED AND AT LEAST ONE REACTOR COOLANT PUMP RUNNING) 5.0 I I I

4 .0 I

ACCEPTABLE OPERATING REGION I

I I (2 t***

I

.II:

'.II:

<l 3.0 I .10)

/

v*J_....v o'f' /

zH REQUIRED SHUTDOWN MARGIN i

{.!) I /

11::

(1 00, *2 5)

~ / I

/

~r:l 2.0

/

~

/

II: / I til

/

/ I

!UNACCEPTABLE OPERATING REGION I 1.0

( ~5( I 0)

I I

0.0 0 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 8 of 13

CORE OPERATI NG LIMITS REPORT. VEGP UNIT I CYC LE 22 JUNE 1018 FIGURE 2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE I NOT APPLICABLE) 5.0 (2 00 I <

Jv

.9e,Y v v

/

)/

4.0 vv

!ACCEPTABLE OPERATING REGION l

/

v v

~

~ /

v v

<l 3. 0 o'P IREQU IRED SHUTDOWN MARGIN~ (1 50 I ' .8 5 )

zH 7

t!)

Ill:

~

~ v 0

Q E-4 2.0 v

=

~

tl) /

/

1.0

/

v UNACCEPTABLE OPERATING REGION

( ~ 6( I . ( 0}

0.0 0 500 1000 1 500 2000 2500 RCS BORON CONCENTRATION (ppm}

Page 9 of 13

CORE OPERATI NG LIMITS REPORT, VEGP UNIT I CYCLE 2? JUNE 2018 FIGURE 3 ROD BANK INSERTION LIMITS\ ERSUS% OF RATED THERMAL POWER (Fully W1thdrawn )

v Ll .0 ~ 212 ~ '/ 78

• D ~' 9) 220 I'

v v v

I 200 I / BANK B I /

~ 180 / /

J.4  !/ /

'tS /_ I /

.c:

.'!:: I' C% I 6 1 v ( I(! ~ l6 1

~

160 v I Ill p.

I

~ 140 til BANK C I/

I/ /

~ 120

/ v v

H E-4 /

H v I' til

~ 100

'/ v I

I

/

I I I/ / 1_1

'/ I/

I/ / I BANK D 60 v / I v

v v k' 1 0% ~1 6 ) I' I 40 20 I( ~

• 2ft a> v 0 L I 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 s; 231 steps withdrawn.

NOTE : The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, B, C, 0 and a control bank tip-to-tip distance of 115 steps.

Page 10 of 13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 22 JUNE 2018 FIGURE 4 K(Z)- NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.4 1.2 11::

0 E-1 u

~ 1. 0 I

(!)

z H

~

1:&1 ll. 0.8 FQ = 2 . 50 0

1:&1 t'l CORE H HT . K(Z)

~

~ 0.6 0 . 00 1 . 00 6 . 00 1 . 00 12 . 0 . 925

~

t'l I.:

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

Page II of 13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 22 JUNE ?018 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF% RATED THERMAL POWER FORRAOC 120 110

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

1-1 4J 90 u ~AC rEpr ABI E I \ UN CCE PTJl BLE

~

0 ll. II \

.-t ns 80 I ll e l _1 4J

..c:

~ 70 1/

I Af'CE )TA LE

\

~ 1\

I \

4J

.j.)

ns 60 j \

P::

lj..l 0

I i\

o'P 50 P:: I (-3o, 50) L (+26, 50) r:0 40 ll.

30 20 10 0

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

Page 12 of 13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 22 JUNE 2018 FIGURE6 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

-27 . 5

~ -28 . 0

....QJ

....u lH lH QJ 0

u QJ -28 . 5 1-l Bnl 1-l t

QJ E-t -29 . 0 1-l Bnl 1-l

~

~

-29 . 5 L 17000 18000 19000 20000 21000 Cycle Burnup (MWD/MTU)

Cycle Burnup Moderator Temperature Coefficient (MWD/MTU) (pcm/°F) 17000 -27.83 18000 -28.11 19000 -28.38 20000 -28.62 21000 -28.89 Page 13 of 13