NL-17-1757, Core Operating Limits Report, Cycle 20, Version 1

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Core Operating Limits Report, Cycle 20, Version 1
ML17306A755
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 11/02/2017
From: Hutto J
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-17-1757
Download: ML17306A755 (16)


Text

"*' Southern Nuclear J. J. Hutto Regulatory AHairs Director 40 lm cm~s~ Center Parkway Post Office Box 1295 Btmungham. AI 3'\242 205 992 5872 tel 205 992 760 I fa~

NOV 0 2 2017 jjhutto@southcmco.corn Docket No.: 50-425 NL-17-1757 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant- Unit 2 Core Operating Limits Report. Cycle 20, Version 1 Ladies and Gentlemen:

fn 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 (COLA) for Unit 2, Cycle 20, Version 1.

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

Respectfully submitted, J. J. Hutto Regulatory Affairs Director jjh/kgl/cg

Enclosure:

VEGP Unit 2 COLA, Cycle 20, Version 1 Cc: Regional Administrator NRR Project Manager- Vogtle 1 & 2 Senior Resident Inspector- Vogtle 1 & 2 RType: CVC7000

ENCLOSURE to NL-17-1757 Vogtle Electric Generating Plant- Unit 2 Core Operating Limits Report. Cycle 20, Version 1 Vogtle Electric Generating Plant (VEGP) Unit 2 Cycle 20 Core Operating Limits Report Version 1

V<XiTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 2 CYCLE 20 CORE OPERATING LIMITS REPORT (COLR)

Version I June 2017

CORE OPERATING LIMITS REPORT. VEGP UNJT 2 CYCLE 20 JUNE2017 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP Unit 2 Cycle 20 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 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 - Fo(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor- FNAH 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration Page 1 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 20 JUNE2017 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~

22 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 I and 2.

Page 2 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 20 JUNE2017 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOUAROIHZP-MTC shall be less positive than +0. 7 x I o-t L\k/k/°F for power levels up to 700/o RTP with a linear ramp to 0 L\k/k/°F at 100% RTP.

4 The EOL/AROIRTP-MTC shall be less negative than -5.50 x 10 AlclkflF. 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 104 Aklk/°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 of300 ppm at RTP conditions,
    • AFD Correction is the more negative value of:

{0 pcrni°F or (MFD

  • AFD Sensitivity)}

where: t..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 pcrnloF I t.AFD

      • Predictive Correction is -3 pcm/°F.

The 60 ppm/ARO/RTP-MTC should be less negative than -5.35 x 104 t..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 I Applicable for full-power T-average of 583.8 to 586.8 °F.

Page3 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 20 JUNE2017 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4. I The shutdown banks shaiJ be withdrawn to a position greater than or equal to 225 steps.

2.5 Control Bank Insertion Limits (Specification 3. I .6) 2.5. I The control rod banks shaiJ be limited in physical insertion as shown in Figure 3.

2.6 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3.2. I)

FR17' 2.6. I F0 ( Z) ~ ___2___

  • K (Z) for P > 0.5

- p FRJP F0 (Z) ~ ___2___

  • K(Z) for P ~ 0.5

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

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

F 1111'

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

F 1171'. 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 OPERATlNG LIMITS REPORT. VEGP UNIT 2 CYCLE 20 JUNE2017 2.7 Nuclear EnthaJpy Rise Hot Channel Factor- FN~"(Specification 3.2.2) 2.7.1 F:ft 5,F:Jr *(l+PF.v~ *(1-P))

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

RATED THERMAL POWER 2.7.2 F:J~' = 1.65 2.7.3 PFMl = 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 ofk.,ff::; 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 10 address uncertainties and B depletion.

Page 5 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 20 JUNE2017 Tablet FQ(Z) PENALTY FACTOR Bumup Penalty (MWDIMil.J) Factor 0 1.0276 150 1.0276 368 1.0370 585 1.0483 803 1.0536 1021 1.0548 1238 1.0501 1456 1.0415 1674 1.0322 1891 1.0233 2109 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 bumup at which the Fo(Z) was determined.
2. Linear interpolation is adequate for intermediate cycle bumups.
3. For all cycle bumups 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 20 JUNE2017 Table2 RAOCW(Z)

Adal Eln'atioD ISO 4000 8000 12000 16000 20000 Poiot (feet) MWD~rru MWD~ITU MWD~ITU 1\IWD~ITU MWD~ITU 1\1\\'00ITU 1-5 12.072 - 11.267 UJOOO 1.0000 1.0000 1.0000 1.0000 1.0000 6 11.066 1.3235 1.4111 12431 1.2572 1.1130 1.2139 7 10.865 1.30S4 1.3879 1.2425 usn 1.2111 1.2250 8 10.664 1.3027 1.3653 1.1270 1.2482 1.2029 1.2100 9 10.462 1.3085 1.3551 12184 1.2353 1.1888 1.1907 10 18.261 1.1929 1.3343 1.2165 12244 un3 I 1804 II 10.060 12428 1.29-tl 1.2142 1.2118 U814 11824 12 9.859 1.2421 1.2706 1.2103 1.1966 1.1859 1.1850 13 9.658 12685 1.2644 1.2075 usn 1.1830 1.1886 14 9.456 12610 '-2404 1.2022 11860 1.1835 Ll919 IS 9.255 1.2417 1.2413 Ll954 Ll843 1.1890 1. 1935 16 9.054 1.2307 1.2411 1.1897 1.1811 1.1912 11974 17 &.853 12286 1.2361 1.1820 1.1763 11896 1.2084 18 8.652 12230 1.2314 Ll805 uno 1.1012 1.2234 19 8.450 1.1212 1.2229 1.1874 Ll803 12131 1.2333 20 8.249 12213 12150 1.1910 I 1820 12248 1.1460 21 8.048 12246 1.2086 1.1925 1.1875 1.1343 1.2580 22 7.847 1.2269 1.2022 1.1923 I 1945 1.2416 12686 23 7.646 12256 I 1996 11900 1.1986 1.1466 1.2811 24 7.444 12214 1.1943 1.1865 1.1013 11503 12907 25 7.243 12163 1.1859 1.1800 1.2004 1.2497 1.1950 26 7.042 1.2083 1.1757 11719 I 1972 1.2463 1.2952 27 6.841 1. 1989 Ll644 1.1628 1.1927 1.2415 1.2933 28 6.640 1.1875 I 1515 I 1547 1.1864 12353 12887 29 6.438 1.1751 1.1387 1.1469 1.1787 1.2297 1.2813 30 6.237 1.1629 1.1344 I 1394 1.1708 1.2230 12710 31 6.036 1.1523 1.1302 1.1311 I 1623 1.2153 1.2587 32 5.835 1.1441 I 1251 I 1247 1.1531 12063 1.2472 33 5.634 1.1357 1.1198 1.1211 1.1538 I 1992 12391 34 5.432 1.1321 I 1189 I 1206 1.1602 11998 1.2338 35 5.231 1.1334 1.1255 1.1311 1.1665 1.2050 1.2336 36 5.030 I 1388 1.1340 1.1399 1.1710 1.2098 12332 37 4.829 1.1431 1.1419 I 1485 1.1780 1.2131 1.2327 38 4.628 1.1478 1.1494 1.1566 1.1836 1.2148 1.2313 39 4.426 1.1528 1.1563 I 1640 I 1880 L2149 1.2278 40 4.225 I 1567 1.1624 1.1706 I 1912 1.2135 1.2228 41 4.024 1.1598 I 1678 1.1766 1.1934 1.2108 12177 42 3.823 1.1620 1.1725 I 1815 I 1945 1.2059 1.2107 43 3.622 1.1648 1.1763 I 1854 1.1949 1.1991 I 2011 44 3.420 I 1698 I 1797 1.1885 1.1949 I 1914 1.1911 45 3.219 I 1747 1.1810 1.1916 1.1936 I 1854 1.1794 46 3.018 I 1784 I 1943 1.2027 I 1959 1.1834 I 1780 47 2.817 1.1843 I 2175 1.2222 1.2086 1.1862 1.1869 48 2.616 1.1972 1.2415 1.2429 1.2237 1.1962 1.1992 49 2.414 1.2115 I 2655 I 2634 1.2381 I 2076 1.2112 so 2.213 I 2257 I 2900 I 2843 1.2527 1.2187 I 2233 51 2.012 1.2406 I 3143 13045 1.2661 1.2284 1.2336 52 1.811 1.2556 13382 I 3243 1.2789 1.2376 I 2*133 53 1.610 12700 1.3610 I 3432 12915 1.2472 1.2537 54 1.408 1.2840 1.3824 I 3611 1.3036 1.2570 1.2645 55 1.207 1.2975 14023 1.3777 1.3151 I 2666 I 2755 56 1.006 I 3102 14204 1.3929 1.3260 1.2763 1.2868 57-61 0.805 - 0.000 1.0000 I 0000 1.0000 1.0000 1.0000 1.0000 Top and BottomS 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 20 JUNE2017 FIGUREl REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FD.LED AND VENTED AND AT LEAST ONE REACTOR COOLANT PUMP RUNNING) 5.0 4.0 ACCEPTABLE OPERATING REGION I

(2 00, .1 D)

/

/

/

/

REQUIRED SHUTDOWN MARGIN!

.,... v /

(1 00, .2 5)

/

v/

/

/

v /

.//

!UNACCEPTABLE OPERATING REGION I

( ~sc , .:i 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 2 CYCLE 20 JUNE2017 FIGURE2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE) 5.0 (2 00 ~ . .9

~

l/

v v

~

l/

vv

/

4.0 7

!ACCEPTABLE OPERATING REGIONl vv /

~

........ /

v

~ /

<l 3.0 df' IREQUIRED SHUTDOWN MARGIN~ (1 50, .a ~)

z; v

H CJ

~

v

~

§ 0 2.0 v

v t:l

~

1:1:

v til I

/ UNACCEPTABLE OPERATING REGION 1.0

(!16(, . ( 0) 0.0 0 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 9 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 2 CYCLE 20 JUNE2017 FIGUREJ ROD BANK INSERTION LIMITS VERSUS% OF RATED THERMAL POWER (Fully Withdrawn *)

220 I v ( .0, 22 1) I ,/ l118 . ~~ ~ SIJ

,/

v v

200

/ BANK B

/

1/ /

ll' 1/

v v v (J% 6 1. '/ L( I(% .6 l.

'/

v m

Ill

!l 140 til BANK C

/ I/

~ 120 ,/ v v

H E-t ,/

H v v v v til

i! 100

~

lQ RO Q

0 ./

P'. / BANK D Ll /

60 v Ll k"' v v /

40

[(J% .IJ 6[)

v v

20 u

  • 21t 0) L 0

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 ::2: 225 and :s; 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 20 JUNE2017 FIGURE4 K(Z)- NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.4 1.2 FQ = 2.50 CORE HT. K(Z) 0.00 1.00 6.00 1. 00 12.0 .925 N

Ill:

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 20 JUNE2017 FIGURES AXIAL FLUX DIFFERENCE LIMITS AS A FUNCfiON OF% RATED mERMAL POWER FORRAOC 120 110

(-15, 100) (+10, 100) 100 I 1\

~

CD 90 u ~AC EP~ ABIE I \ UN cc PTJl BLE

)

0 Po I \

I \

e r-1 as 80 I \

CD

..c:=

E-1 70 I L A""CE PTAl LE

\

'1:1 li I \

CD

.1.)

liS 60 I \

PI

""'0 I dP 50 1\

PI l ( -30, 50) I (+26, 50) I

~ 40 0

p.

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 20 JUNE2017 FIGURE6 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

-27 . 5 I I I I I i ' .....

~

Gl

  • rl

-28.0

,...... !'oo..

........,I I 0 ~

"l

  • rl

""'""'Gl I I ........

0 u

Gl - 28 . 5 I I 1-1 i"'-...

.flIll ......

1-1 Gl """"" ......

ftGJ """""

E-t -29 . 0 I 1-1 0

.jJ Ill 1-1

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

Cycle Burnup Modemtor Tempemture Coefficient (MWD/MTU) (pcm/0 f) 17000 -27.76 18000 -28.02 19000 -28.33 20000 -28.58 21000 -28.84 Page 13 of13