NL-17-1063, Core Operating Limits Report, Cycle 21 Version 1

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Core Operating Limits Report, Cycle 21 Version 1
ML17157B381
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 06/06/2017
From: Wheat J
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-17-1063
Download: ML17157B381 (15)
v • d • e


Text

~ Southern Nuclear Justin T. Wheat 40 Ill\ em~" C~nter P.u-kway Nuclear Licensing Manager Post Office Box 1295 Bmningham. AI >5242 205 992 599S tel 205 992 760 I fax jt\\ heat C!!' ~outhernco.com JUN 0 6 2017 Docket Nos.: 50-424 NL-17-1 063 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant (Vogtle}- Unit 1 Core Operating Limits Report Cycle 21 Version 1 Ladirs and Gentlemen:

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

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.

Respectfully submitted,

~0-1~

Justin T. Wheat Nuclear Licensing Manager JTW/PDB/Iac

Enclosure:

Vogtle Unit 1 Cycle 21 Core Operating Limits Report Version 1 Cc: Regional Administrator NRR Project Manager- Vogtle 1 & 2 Senior Resident Inspector- Vogtle 1 & 2 RType: CVC7000

Vogtle Electric Generating Plant (Vogtle)- Unit 1 Core Operating Limits Report Cycle 21 Version 1 Enclosure Vogtlle Unit 1 Cycle 21 Core Operating Limits Report Version 1

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 21 DECEMBER 2016 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP Unit 1 Cycle 21 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 The Technical Specifications 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 - FQ(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor- FN t.H 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration Page 1 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 21 DECEMBER 2016 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 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYCLE 21 DECEMBER 2016 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

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

The EOLIARO/RTP-MTC shall be less negative than -5.50 x 104 ~k/k/°F.

1 2.3.2 The MTC Surveillance limits are:

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

-4.75 X 10-4 ~k/k/°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 of300 ppm at RTP conditions,
    • AFD Correction is the more negative value of:

{0 pcrn/°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 pcrn/°F I ~AFD

      • Predictive Correction is -3 pcrn/°F.

The 60 pprn/ARO/RTP-MTC should be less negative than -5.35 x 104 ~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 .I °F.

Page3 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 21 DECEMBER 2016 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)

FR71' 2.6.1 Fa (Z) $; _g__

  • K(Z) for P > 0.5

- p FRTI' Fa (Z) $; _g__

  • K(Z) for P::;; 0.5

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

RATED THERMAL POWER 2.6.2 F~ ' =2.50 77 2.6.3 K(Z) is provided in Figure 4.

FR/1'. K(Z) 2.6.4 F (Z) < Q for P > 0.5 Q - P *W(Z)

FRTI'. 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 FQ(Z) penalty factors are provided in Table 1.

Page 4 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 21 DECEMBER 2016 2.7 Nuclear Enthalpy Rise Hot Channel Factor- FN c.H (Specification 3.2.2) 2.7.1 F~ 5:F:;{P *(1+PFMI *(1-P))

THERMAL POWER where: P=--------------------

RATED THERMAL POWER 2.7.2 F:;JP = 1.65 2.7.3 PFMf = 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 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 1 CYCLE 21 DECEMBER 2016 Table 1 Fo(Z) PENALTY FACTOR Bum up Penalty (MWD/MTU) Factor 0 1.0262 150 1.0262 368 1.0230 585 1.0200 9075 1.0200 9292 1.0205 9510 1.0212 9728 1.0200 9946 1.0205 10163 1.0233 10381 1.0222 10599 1.0216 10816 1.0211 11034 1.0205 11252 1.0201 11469 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 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 1 CYCLE 21 DECEMBER 2016 Table 2 RAOCW(Z)

Axial Elevation 150 4000 8000 12000 16000 20000 Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU 1-5 12.072 - 11.267 I 0000 I 0000 1.0000 I 0000 I 0000 I 0000 6 I 1.066 I 3165 I 3710 I 3480 I 2691 I 2150 1.1937 7 10.865 I 3056 I 3567 I 3361 I 2652 I 2155 I 1927 8 10.66~ I 2983 I 3369 I 3209 I 2532 I 2005 I 1853 9 10.462 I 2966 I 3211 I 3045 I 2389 1.1962 1.1838 10 10.261 I 2833 I 3134 I 2856 I 2260 I 1965 I 1835 II 10.060 I 2651 I 2966 I 2646 I 2240 I 2034 I 1832 12 9.859 I 2476 I 2875 I 2602 I 2162 I 2027 I 1854 13 9.658 1.2445 I 2860 I 2565 I 2087 I 2001 I 1940 I~ 9.456 I 2394 I 2705 I 2460 I 2008 I 1977 I 1986 IS 9.255 1.2306 I 2578 I 2371 1.1938 I 1973 I 2144 16 9.054 1.2245 I 2389 I 2233 I 1895 I 1971 I 2245 17 8.853 1.2277 12204 I 2068 1.1826 I 1937 I 2181 18 8.652 I 2316 I 2094 I 2007 1.1800 I 1909 1.2191 19 8.450 1.2368 I 2070 I 2010 I 1882 I 1938 I 2284 20 8.2~9 1.2387 I 1995 I 1964 I 1940 I 2049 1.2374 21 8.0~8 I 2383 I 1992 I 1993 I 1977 1.2143 I 2528 22 7.847 I 2360 I 1966 I 1998 I 1997 I 2217 1.2650 23 7.646 I 2307 I 1918 I 1980 I 1995 I 2270 I 2747 24 7.4~~ 1.2239 I 1855 I 1947 I 1982 I 2310 I 2826 25 7.2~3 I 2144 I 1765 I 1882 I 1937 I 2311 I 2853 26 7.0~2 1.2035 I 1659 I 1797 I 1871 I 2286 1.2844 27 6.841 I 1916 I 1545 I 1702 I 1796 I 2248 I 2816 28 6.640 1.1784 I 1416 I 1593 I 1715 I 2192 I 2764 29 6.~38 I 1671 I 1340 I 1476 I 1644 I 2147 1.2685 30 6.237 1.1559 I 1268 I 1363 I 1573 I 2090 I 2590 31 6.036 1.1490 I 1235 I 1238 I 1497 I 2026 I 2483 32 5.835 I 1419 I 1201 I 1200 I 1414 I 1947 I 2361 33 5.63~ I 1374 I 1161 I 1181 I 1426 I 1889 I 2261 3~ 5.432 I 1341 I 1147 I 1186 I 1504 I 1902 I 2230 35 5.231 I 1333 I 1235 I 1273 I 1580 I 1939 1.2240 36 5.030 I 1363 I 1319 I 1366 1.1646 I 1967 I 2253 37 4.829 1.1419 I 1401 I 1455 1.1703 I 2000 I 2248 38 4.628 I 1466 I 1477 I 1538 1.1751 1.2022 I 2224 39 4.426 I 1507 I 1548 I 1615 I 1788 I 2030 I 2181 40 4.225 1.1539 I 1611 I 1684 1.1814 I 2024 1.2123 41 4.024 1.1561 1.1663 I 1745 1.1832 I 2006 I 2052 42 3.823 1.1580 I 1730 I 1802 1.1833 I 1969 I 1952 43 3.622 I 1614 I 1810 I 1866 I 1833 I 1914 I 1869 4~ 3.420 1.1662 I 1877 I 1928 I 1858 I 1853 I 1811 45 3.219 1.1703 1.1933 I 1976 I 1886 I 1821 I 1746 46 3.018 I 1741 I 2010 I 2047 1.1955 I 1892 I 1766 47 2.817 I 1802 I 2139 I 2186 1.2094 I 2023 I 1876 48 2.616 I 1946 I 2361 I 2387 1.2244 I 2141 I 2002

~9 2.414 1.2107 I 2603 I 2598 I 2389 I 2259 I 2127 so 2.213 I 2264 I 2846 I 2810 1.2534 I 2377 I 2252 51 2.012 I 2423 I 3088 I 3016 1.2669 I 2481 I 2359 52 1.811 1.2580 I 3327 I 3218 I 2798 I 2581 I 2460 53 1.610 I 2728 I 3552 I 3409 I 2923 I 2681 I 2566 s~ 1.408 1.2870 I 3764 I 3589 I 3043 I 2781 I 2675 55 1.207 1.3004 I 3960 I 3756 I 3156 I 2879 1.2783 56 1.006 I 3129 14136 I 3907 I 3262 I 2976 I 2893 57-61 0.805- 0.000 1.0000 I 0000 I 0000 1.0000 I 0000 I 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 Tavg temperature range from 584.1 to 587.1 °F.

Page 7 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYCLE 21 DECEMBER 2016 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 I

I ACCEPTABLE OPERATING REGION I I (2~ 00, .1 ())

/

v v REQUIRED SHUTDOWN MARGIN!

v v /

{1 00 . .2 ~)

v v ......

v

~

v

./

v v

...,..v IUNACCEPTABLE OPERATING REGION I

( ~5C , .3 0) 1.0 0.0 0 500 1000 1 500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 8 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 21 DECEMBER 2016 FIGURE2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE) 5.0 (2 00 .9 /

/

~

v

/

4.0 I I I I

/v

/'f' I

!ACCEPTABLE OPERATING REGION I

/

v I

.!oe

.!oe

<1 3.0

/v /

  • /

z H

t!J IREQUIRED SHUTDOWN MARGIN!

v (1 50, .8 5)

/

v p:;

~

v

~

0 2.0

~

E-t

/

=

til

/

1.0 /

v UNACCEPTABLE OPERATING REGION I

( t6C , .0 0) 0.0 0 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 9 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 21 DECEMBER 2016 FIGURE3 ROD BANK INSERTION LIMITS VERSUS% OF RATED THERMAL POWER (Fully Withdrawn*)

I I / I I I I I I 220 II II I I

IC .10"' 22 J l jt' vr

[181._0_!i IZ25)

IY I I I I I I I I I I I I I Yl I l I I I I 'I I r 1 I I I I I I I I I I I I I I I I I I 200 I I I I I I I I I y I I I I I j_ l I I I I I I I I

/. .I I.

" I I

I I

I I

E180 BANK B I I I I I I/ I 1/ I I II 1/

g

~

VI Ill

~ 160 I I [( ~ l!611 v I (!1.. H!lf! 6il

~

I v ID p,

I

~ 140 I til I/ BANK C /

~ 120 I/ I/

H 1.1 IL E-t 1/

v

~

H til v

v g 100 II I/

I/

BANK D I/ 1.1 60 II II v II v v 40

c% ~ 61) 20 0
  • 2% ICI>

0 I/

0 10 20 30 40 so 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 1 CYCLE 21 DECEMBER 2016 FIGURE4 K(Z)- NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.4 1.2 P:

0 E-t u I

~ 1.0

~

H

~

IZI p, 0, 8 FQ = 2.50 r:a IZI N

CORE H HT. K(Z)

~ 0.6 0.00 1.00 I

~ 6.00 1.00 12.0 . 925

~

N

~

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

Page 11 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 2 I DECEMBER 20 I 6 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF %RATED THERMAL POWER FORRAOC 120 I I I 110 I I

I I I

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

100 I I II 1\

~

GJ 90 ufAC ~'EPTAB1 I

E I I I \ IUN.l CC1 PTl !BLE I

!t 0

llo II II \ I r-f 80 J ~

e I I I aS

~

GJ

.s::

E-t 70 I II I A~"'CE PTAJ LE

\

'tJ 1\

I _1 GJ

.1.1 aS 60 I \

~

IW 0

1/ 1\

aP

~

50

~

n (-3o, 50) I (+26, 50)

~

0 40 llo 30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (percent di}

Page 12 of13

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYCLE 21 DECEMBER 2016 FIGURE6 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

- 27 . 5

' ~

......... ~

........ ~

i".~

~

-29 . 5 18000 19000 20000 21000 22000 CYCLE BURNUP (MWD/MTU)

Cycle Burnup Moderator Temperature Coefficient (MWD/MTU) (pcrn/ 0 f) 18000 -27.96 19000 -28.26 20000 -28.53 21000 -28.80 22000 -29.04 Page 13 of13

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