NL-15-1602, Cycle 19 Core Operating Limits Report Version 2

From kanterella
(Redirected from NL-15-1602)
Jump to navigation Jump to search
Cycle 19 Core Operating Limits Report Version 2
ML15237A433
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 08/21/2015
From: Pierce C
Southern Co, Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-15-1602
Download: ML15237A433 (17)


Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN << \

NUCLEAR A SOUTHERN COMPANY August 21, 2015 Docket Nos.: 50-424 NL-15-1602 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant, Unit 1 Cycle 19 Core Operating Limits Report Version 2 Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company (SNC) submits the enclosed Core Operating Limits Report (COLR) for the Vogtle Electric Generating Plant (VEGP) - Unit 1, Cycle 19, Version 2.

Version 2 includes an algorithm and figure for calculating the revised predicted near End of Life (EOL) moderator temperature coefficient {MTC). The Nuclear Regulatory Commission approved the use of this methodology with the issuance of Technical Specification amendment number 174 (Unit 1).

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at {205) 992-7369 .

C. R. Pierce Regulatory Affairs Director CRP/RMJ

Enclosure:

Unit 1 Cycle 19 Core Operating Limits Report Version 2

U.S. Nuclear Regulatory Commission NL-15-1602 Page2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Mr. D. R. Madison, Vice President- Fleet Operations Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. B. K. Taber, Vice President- Vogtle 1 & 2 Mr. B. J. Adams, Vice President- Engineering Mr. G.W. Gunn, Regulatory Affairs Manager- Vogtle 1 & 2 RType: CVC7000 U.S. Nuclear Regulatorv Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager- Vogtle 1 & 2 Mr. L. M. Cain, Senior Resident Inspector- Vogtle 1 & 2

Vogtle Electric Generating Plant, Unit 1 Cycle 19 Core Operating Limits Report Version 2 Enclosure Unit 1 Cycle 19 Core Operating Limits Report Version 2

VOGTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 1 CYCLE 19 CORE OPERATING LIMITS REPORT Version 2 June 2015

CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE 2015 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP Unit 1 Cycle 19 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 - Fo(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor- FN m 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration Page 1 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE2015 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 1 and 2 (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent &/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 19 JUNE 2015 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 1O"" Aklk/°F for power levels up to 70% RTP with a linear ramp to 0 Aklk/°F at 100% RTP.

The EOLIARO/RTP-MTC shall be less negative than -5.50 x 10"" Aklk/°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"" 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 burnup corresponding to the measurement of300 ppm at RTP conditions,
    • AFD Correction is the more negative value of:

{0 pcm/°F or (b.AFD

  • AFD Sensitivity)}

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

  • ..Predictive Correction is -3 pcmfDF.

The 60 ppm/ARO/RTP-MTC should be less negative than -5.35 x tO"" Aklk/°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 584.1 to 587.1 °F.

Page3 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE2015 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- F Q(Z) (Specification 3.2.1)

FRTP 2.6.1 FQ (Z) ~ _Q_

  • K(Z) for P > 0.5 p

FRTP FQ (Z) ~ _Q_

  • 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.

FRTP. K(Z) 2.6.4 F (Z) ~ Q for P > 0.5 Q P*W(Z)

FRTP. 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 F 0 (Z) penalty factors are provided in Table I.

Page 4 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE2015

  • 2.7 Nuclear Enthalpy Rise Hot Channel Factor- pN Mi (Specification 3.2.2)

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

RATED THERMAL POWER 2.7.2 F:JP = 1.65 2.7.3 PFMI =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 1880 ppm. 2 2

This concentration bounds the condition ofkerr~ 0.95 (all rods in less the most reactive rod) and subcriticality (ru! rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B 10 depletion.

Page 5 ofl3

CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE2015 Tablel FQ(Z) PENALTY FACTOR Cycle Burnup FQ(Z) Penalty Factor (MWDIMTU) 30 1.0348 150 1.0348 368 1.0391 585 1.0417 803 1.0423 1020 1.0410 1238 1.0366 1456 1.0308 1673 1.0248 1891 1.0200 6242 1.0200 6460 1.0204 6678 1.0260 6895 1.0262 7113 1.0261 7330 1.0244 7548 1.0214 7765 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 bum up at which the FQ(Z) was determined.
2. Linear interpolation is adequate for intermediate cycle bumups.
3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.

Page 6 ofl3

CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE 2015 Table 2 RAOCW(Z)

Axial Elevation ISO 3000 12000 20000 Point (reet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 1-5 12.072- 11.267 1.0000 1.0000 1.0000 1.0000 6 11.066 1.3172 1.3495 1.3279 1.2728 7 10,865 1.3162 1.3440 1.3244 1.2665 8 10.664 1.3018 1.3350 1.3164 1.2561 9 10.462 1.2808 1.3167 1.3051 1.2430 10 10.261 1.2615 1.2912 1.2919 1.2294 11 10.060 1.2467 1.2683 1.2775 1.2189 12 9.859 1.2503 1.2431 1.2614 1.2150 13 9.658 1.2444 1.2130 1.2438 1.2096 14 9.456 1.2373 1.1979 1.2384 1.2144 15 9.255 1.2278 1.1893 1.2286 1.2272 16 9.054 1.2168 1.1763 1.2165 1.2359 17 8.853 1.2020 1.1662 1.2092 1.2397 18 8.652 1.1893 1.1670 1.2141 1.2426 19 8.450 1.1900 1.1724 l.llJO 1.2438 20 8.249 1.1889 1.1761 1.2290 1.2500 21 8.048 1.1918 1.1783 1.2332 1.2591 22 7.847 1.1940 1.1780 1.2344 1.2670 23 7.646 1.1935 1.1761 1.2336 1.2800 24 7.444 1.1914 1.1728 1.2315 1.2895 25 7.243 1.1867 1.1674 1.2259 1.2944 26 7.042 1.1802 1.1604 1.2178 1.2950 27 6.841 1.1724 1.1523 1.2083 1.2931 l8 6.640 1.1633 1.1459 1.1918 1.2890 29 6.438 1.1529 1.1393 1.1896 1.2819 30 6.237 1.1452 l.ln6 1.1101 1.2719 31 6,036 1.1401 1.1279 1.1696 1.2596 32 5.835 1.1344 1.1252 1.1608 1.2478 33 5.634 1.1321 1.1225 1.1560 1.2400 34 5.432 1.1309 1.1258 1.1590 1.2349 35 5.231 1.1317 1.1378 1.1648 1.2349 36 5.030 1.1386 1.1484 1.1706 1.2348 37 4.829 1.1477 1.1587 1.1753 1.2344 38 4.628 1.1561 1.1683 1.1790 1.2333 39 4.426 1.1640 1.1775 1.1815 1.2302 40 4.225 1.1710 1.1856 1.1829 1.2254 41 4.024 1.1770 1.1930 1.1133 1.2191 42 3,823 1.1826 1.1994 1.1822 1.2100 43 3.622 1.1872 1.2065 1.1795 1.1985 44 3.420 1.1925 1.2159 1.1763 1.1861 45 3.219 1.1985 1.2241 1.1722 1.1765 46 3.018 1.2057 1.2377 1.1765 1.1776 47 2.817 1.2190 1.2562 1.1889 1.1890 48 2.616 1.2337 1.2794 1.2020 1.2019 49 2.414 1.2476 1.3058 1.2149 1.2147 50 2.213 1.2616 1.3328 1.2279 1.2275 51 2.012 1.2755 1.3595 1.2399 1.2386 52 1.811 1.2893 1.3858 1.2514 1.2491 53 1.610 1.3024 1.4105 1.2627 1.2601 54 1.408 1.3149 1.4336 1.2737 1.2714 55 1.207 1.3269 1.4550 1.2843 1.2828 56 1.006 1.3380 1.4742 1.2943 1.2945 57-61 0.805 - 0.000 1.0000 1.0000 1.0000 1.0000 Top and Bottom 5 Points Excluded per Technical Specification B3.2.1.

These W(Z) values are consistent with Figure 5, and are valid over the HFP T avg temperature range from 584.1 to 587 .I °F.

Page 7 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE2015 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 b>

L/

vv SHUTDOWN MARGIN!

vv RE~UIRED (1 00 , .2 5)

/

v

/

/

/

/

/

/

!UNACCEPTABLE OPERATING REGION I

(~SC, . 0) 1.0 0.0 0 SOD 1000 1500 2000 2500 RCS BORON CONCBNTRATION (ppm)

Page 8 ofl3

CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE 2015 FIGURE2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE) 5.0 (2 00 I '

.9

~

v vv

.~v 4.0 vv

!ACCEPTABLE OPERATING REGION I v

vv /

i

....... v v

.II! /

<] 3.0 rJP

!REQUIRED SHUTDOWN MARGIN~ (1 50 I * .8 ~)

~

v H

a

! v 2.0 v

m v v

11.1 I UNACCEPTABLE OPERATING REGION 1.0

( 11:6( 1

  • c0) 0.0 0 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 9 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE2015 FIGURE3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER (Fully Withdrawn*)

V I( .Oils 225 / 18. I) 220 v /

200

..... BANK B

~ 180 I/

w / v

8 v

/

1:115 .61 v

/

ll I ( 115 ~61

160

~

Ill PI

!J140 til BANK C I§ 120 /

  • .I'

/

/

H E-1 / k" H

til

'/

v v

/

~ 100 a 80

§

~ 1.1' BANK D I/ .1' 60 v .1' v /

'/

I Olli 4161) 40 20 i l .::.n 0) .1' 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 ~ 23 I 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 I CYCLE 19 JUNE 2015 FIGURE4 K(Z)- NORMALIZED F o(Z) AS A FUNCTION OF CORE HEIGHT 1.4 1.2

~ ~

Eo!

~ 1.0

~ -

a p.. 0. 8 FQ = 2.50

&I CORE ig N

HT. K(Z) 0.00 1.00

0. 6 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 ofl3

CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE 2015 FIGURES AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF %RATED THERMAL POWER FORRAOC 120 110

{-15, 100) {+10, 100) 100 I \

~

90 u ~AC ~EP' ABI E I \ UN CCI PTJl BLE

~

Po II \

80 \

a I \

I \

Ql

.r:l A~CE ~TAl LE E-4 70 "Cj ~

Ql Ill 60 I \

I \

ll!i 0

so 1/ 1\

rJP ll!i I { -30, 50) I (+26, SO)

~

Po 40 30 20 10 0

-so -40 -30 -20 -10 0 10 20 30 40 so AXIAL FLUX DIFFERENCE {percent ~I)

Page 12 of13

CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE2015 FIGURE6 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP

-f-L

-28.0 I I I r; - -

0 I I

' i 1

I

~I I I

' ...... I I

~ -28.5 I I

~ I I l

  • 1'1 0
  • 1'1 """ K

~ I

~0 I ~

u .......

Gl -29.0 I I I I I II ...... I B

-='-- "' -...,,I I

Ill I I T!

' I...... i'o-It 1--- -

E-1 -29.5 I I .......

1-1 I -- ----

llIll -I-

~ I I I

i I -I

-30.0 I ' I i I I 17000 18000 19000 20000 21000 Cycle Burnup (MHD/MTU)

CycleBumup Moderator Temperature (MWD/MTU) Coefficient (pcm/°F) 17000 -28.33 18000 -28.65 19000 -28.93 20000 -29.23 21000 -2954 Page 13 of13