NL-16-2491, Cycle 28 Core Operating Limits Report
| ML16326A250 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/21/2016 |
| From: | Pierce C Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-16-2491 | |
| Download: ML16326A250 (18) | |
Text
~ Southern Nuclear Charles R. Pierce Regulatory Affairs Director 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 205 992 7872 tel 205 992 7601 fax crpierce@ southemco.com November 21, 2016 Docket Nos.: 50-348 NL-16-2491 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Cycle 28 Core Operating Limits Report Ladies and Gentlemen:
In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company (SNC) submits the enclosed Core Operating Limits Report (COLA) for the Joseph M. Farley Nuclear Plant (FNP) - Unit 1 Cycle 28 Version 1.
This letter contains no NRC commitments. If you have any questions, please contact Ken p;;d, McElroy at 205.992.7369.
Rc.~lly C.R. Pierce Regulatory Affairs Director CRP/RMJ
Enclosure:
Core Operating Limits Report for FNP Unit 1 Cycle 28 Version 1 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Best, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President- Farley Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Ms. B. L. Taylor, Regulatory Affairs Manager- Farley RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager- Farley Mr. P. K. Niebaum, Senior Resident Inspector- Farley
Joseph M. Farley Nuclear Plant- Unit 1 Cycle 28 Core Operating Limits Report Enclosure Core Operating Limits Report for FNP Unit 1 Cycle 28 Version 1
SOUTHERN*\
COMPANY Energy to Serve YOur World*
Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 - Cycle 28 Version 1 June 2016
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 CYCLE 28 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 (with ketr~ 1)
The Technical Specifications affected by this report are listed below:
2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN- MODES 2 (with ketr< 1), 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- F!
3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature ~T (OT~T) and Overpower ~T (OP~T) Setpoint Parameter Values for Table 3.3.1-1 3.4.1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration Page 1 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 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 1 and 2 (with k..w~ 1.0) {Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent ilklk.
2.2 SHUTDOWN MARGIN- MODES 2 (with~< 1.0), 3. 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (keff < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Llklk.
2.2.2 Mode 5- The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent Llklk.
Page 2 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOLIARO-MTC shall be less than or equal to +0.7 x 104 ~k/k/°F for power levels up to 70 percent RTP with a linear ramp to 0 ~oF at 100 percent RTP.
The EOL/AROIRTP-MTC shall be less negative than -4.3 x 104 ~°F.
2.3.2 The MTC Surveillance limits are:
The 300 ppm/AROIRTP-MTC should be less negative than or equal to
-3.65 x 104 ~k/k/°F.
The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5 and the following algorithm:
Revised Predicted MTC Predicted MTC* + AFD Correction** + Predictive Correction***
where,
- Predicted MTC is calculated from Figure 5 at the burnup corresponding to the measurement of300 ppm at RTP conditions,
- AFD Correction is the more negative value of:
{0 pcmJDF or (~D
- AFD Sensitivity)}
where: ~D 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 = 0.07 pcrnloF I ~D
- Predictive Correction is -3 pcmrF.
The 100 ppm/AROIRTP-MTC should be less negative than -4.0 x 104 ~°F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 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.
Page 3 ofl5
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 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 I.
2.6 Heat Flux Hot Channel Factor- FQ (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) forP::::;; 0.5 0.5 THERMAL POWER where: P=----------
RATEDTHERMALPOWER 2.6.2 F;TP =2.50 2.6.3 K(Z) is provided in Figure 2.
FRTP *K(Z) 2.6.4 F (Z) <--=-Q- - - forP> 0.5 Q - P*W(Z)
FRTP *K(Z)
F (Z)<---=-Q- - - forP::::;; 0.5 Q - 0.5*W(Z) 2.6.5 Full Power W(Z) values are provided in Table 4.
Part Power (48% RTP) W(Z) values are provided in Table 5.
2.6.6 The FQ (Z) penalty factors are provided in Table I.
Page4 ofl5
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 2.7 Nuclear Enthalpy Rise Hot Channel Factor- F~ (Specification 3.2.2) 2.7.1 F~ ~F:JP *(l+PFMI *{1-P))
THERMAL POWER where: p =----------
RATED THERMAL POWER 2.7.2 F:JP = 1.70 2.7.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 3.
2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm. 1 2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1.1) 2.1 0.1 In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 4.
2.11 Reactor Trip System Instrumentation Overtemperature ~T COT~T) and Ovemower ~T (OP~T)
Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11 .1 The Reactor Trip System Instrumentation Overtemperature ~T (OT ~T) and Overpower
~T (OP~T) setpoint parameter values forTS Table 3.3.1-1 are listed in COLR Tables 2 and 3.
2.12 RCS DNB Parameters for Pressurizer Pressure. RCS Average Temperature. and RCS Total Flow Rate (Specification 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:
- a. Pressurizer pressure ~ 2209 psig;
- b. RCS average temperature$ 580.3°F; and
- c. The minimum RCS total flow rate shall be~ 273,900 GPM when using the precision heat balance method and ~ 274,800 GPM when using the elbow tap method.
This concentration bounds the condition ofkeff$ 0.95 (all rods in less the most reactive rod) and subcriticality (IDl rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B 10 depletion.
Page 5 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 Tablet F Q(Z) Penalty Factor Cycle Burnup F Q(Z) Penalty (MWDIMTU) Factor 30 1.0510 150 1.0510 354 1.0478 559 1.0438 763 1.0387 967 1.0336 1172 1.0299 1376 1.0242 1581 1.0200 6894 1.0200 7099 1.0233 7303 1.0256 7507 1.0268 7712 1.0262 7916 1.0256 8120 1.0249 8325 1.0242 8529 1.0225 8734 1.0204 8938 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 bumup at which the FQ(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 1.0200 shall be used.
Page 6 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 Table2 Reactor Trip System Instrumentation- Overtemperature ~T (OT~T)
Setpoint Parameter Values T' ::;;577.2°F P' = 2235 psig K1 = 1.17 K2=0.017rF 1<.3 = 0.000825/psi
'tl ~ 30 sec 1:2:::;; 4 sec
-c4= 0 sec ts::;; 6 sec 't6::;; 6 sec fi(M) = -2.48 {23 + (qt- qb)} when (qt- qb) :::;; -23% RTP 0% ofRTP when -23% RTP < (qt -qb) :::;; 15% RTP 2.05 {(qt- qb) -15} when (qt- qb) > 15% RTP Page 7 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 Table3 Reactor Trip System Instrumentation- Overpower .L\T (OP.L\T)
Setpoint Parameter Values 1<4= 1.10 Ks = 0.02jDF for increasing Tavg 1<6 = 0.00109 jDF when T > T" Ks = 0/ °F for decreasing T avg 1<6 = OjDF when T ~ T"
't3~ 10 sec
-r4= 0 sec
-rs~ 6 sec
't6~ 6 sec 6(M) = 0% RTP for all ill Page 8 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 28 June 2016 Table 4 RAOCW(Z)
Axial Elevation 150 3000 6000 10000 14000 18000 Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU MWD/MTU
- 1 12.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- 2 11.80 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- 3 11.60 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- 4 11.40 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- 5 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 11.00 1.1146 1.1174 1.2319 1.2307 1.2073 1.2290 7 10.80 1.1121 1.1244 1.2278 1.2291 1.2045 1.2265 8 10.60 1.1084 1.1366 1.2214 1.2236 1.2002 1.2214 9 10.40 1.1042 1.1445 1.2142 1.2223 1.1978 1.2155 10 10.20 1.1095 1.1438 1.2062 1.2205 1.1980 1.2101 11 10.00 1.1215 1.1384 I 1973 1.2203 1.2014 1.2047 12 9.80 1.1279 1.1314 1.1880 1.2221 1.2041 1.1989 13 9.60 1.1346 1.1274 1.1804 1.2244 1.2090 1.1925 14 9.40 1.1329 1.1188 1.1727 1.2207 1.2081 1.1884 15 9.20 1.1269 1.1203 1.1726 1.2254 1.2174 1.1935 16 9.00 1.1291 1.1256 1.1698 1.2272 1.2233 1.1959 17 8.80 1.1276 1.1299 1.1657 1.2243 1.2244 1.1947 18 8.60 1.1306 1.1353 1.1681 1.2261 1.2248 1.1904 19 8.40 1.1444 1.1455 1.1777 1.2365 1.2309 1.1959 20 8.20 1.1552 1.1547 1.1842 1.2434 1.2459 1.2159 21 8.00 1.1645 1.1620 1.1887 1.2479 1.2571 1.2319 22 7.80 1.1718 1.1676 1.1915 1.2501 1.2658 1.2454 23 7.60 1.1763 1.1706 1.1919 1.2497 1.2717 1.2562 24 7.40 1.1793 1.1724 1.1911 1.2479 1.2761 1.2655 25 7.20 1.1802 1.1718 1.1876 1.2422 1.2762 1.2704 26 7.00 1.1795 1.1697 1.1834 1.2353 1.2740 1.2722 27 6.80 1.1774 1.1663 1.1784 1.2276 1.2708 1.2734 28 6.60 1.1733 1.1614 1.1718 1.2181 1.2655 1.2726 29 6.40 1.1685 1.1555 1.1642 1.2071 1.2579 1.2696 30 6.20 1.1630 1.1490 1.1558 1.1948 1.2483 1.2643 31 6.00 1.1563 1.1415 1.1465 1.1815 1.2371 1.2573 32 5 80 1.1486 1.1331 1.1367 1.1675 1.2245 1.2490 33 5.60 1.1405 1.1257 1.1260 1.1526 1.2101 1.2386 34 5.40 1.1389 1.1328 1.1164 1.1419 1.1926 1.2249 35 5.20 1.1497 1.1420 1.1219 1.1415 1.1861 1.2217 36 5.00 1.1584 1.1510 1.1274 1.1406 1.1858 1.2208 37 4.80 1.1677 1.1613 1.1328 1.1409 1.1835 1.2182 38 4.60 1.1782 1.1713 1.1377 1.1408 1.1801 1.2139 39 4.40 1.1879 1.1806 1.1421 1.1399 1.1753 1.2078 40 4.20 1.1966 1.1889 1.1462 1.1382 1.1694 1.2002 41 4.00 1.2044 1.1964 1.1515 1.1358 1.1625 1.1913 42 3,80 1.2117 1.2033 1.1567 1.1317 1.1534 1.1795 43 3.60 1.2214 1.2084 1.1606 1.1280 1.1435 1.1655 44 3.40 1.2321 1.2180 1.1649 1.1266 1.1373 1.1507 45 3.20 1.2402 1.2286 1.1687 1.1249 1.1307 1.1373 46 3.00 1.2541 1.2461 1.1734 1.1251 1.1332 1.1265 47 2.80 1.2758 1.2756 1.1782 1.1351 1.1441 1.1300 48 2.60 1.2984 1.3074 1.1961 1.1479 1.1555 1.1377 49 2.40 1.3200 1.3384 1.2179 1.1604 1.1670 1.1494 50 2.20 1.3416 1.3698 1.2394 1.1732 1.1787 1.1629 51 2.00 1.3644 1.4008 1.2604 1.1851 1.1891 1.1746 52 1.80 1.3915 1.4312 1.2811 1.1967 1.1992 1.1857 53 1.60 1.4172 1.4597 1.3007 1.2082 1.2095 1.1973 54 1.40 1.4412 1.4862 1.3193 1.2195 1.2200 1.2093 55 1.20 1.4633 1.5106 1.3365 1.2303 1.2304 1.2212 56 1.00 1.4831 1.5323 1.3521 1.2406 1.2407 1.2332
- 57 0.80 1.0000 1.0000 1.0000 1.0000 LOOOO 1.0000
- 58 0.60 1.0000 1.0000 1.0000 I 0000 1.0000 LOOOO
- 59 0.40 1.0000 1.0000 LOOOO 1.0000 LOOOO 1.0000
- 60 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- 61 0.00 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- Top and bottom 5 axial points excluded per Technical Specification B3.2.1.
Page 9 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 Table 5 Part Power (48%) RAOC W(Z)
Axial Point Elevation (feet) 150MWDIMTU
- 1 12.00 1.0000
- 2 11.80 1.0000
- 3 11.60 1.0000
- 4 11.40 1.0000
- 5 11.20 1.0000 6 11.00 1.2144 7 10.80 1.2010 8 10.60 1.1847 9 10.40 1.1664 10 10.20 1.1552 11 10.00 1.1513 12 9.80 1.1395 13 9.60 1.1289 14 9.40 1.1123 15 9.20 1.0931 16 9.00 1.0821 17 8.80 1.0688 18 8.60 1.0618 19 8.40 1.0653 20 8.20 1.0741 21 8.00 1.0721 22 7.80 1.0755 23 7.60 1.0774 24 7.40 1.0832 25 7.20 1.0817 26 7.00 1.0772 27 6.80 1.0753 28 6.60 1.0775 29 6.40 1.0794 30 6.20 1.0701 31 6.00 1.0679 32 5.80 1.0677 33 5.60 1.0699 34 5.40 1.0676 35 5.20 1.0813 36 5.00 1.0952 37 4.80 1.1099 38 4.60 1.1259 39 4.40 1.1410 40 4.20 1.1552 41 4.00 1.1689 42 3.80 1.1829 43 3.60 1.1990 44 3.40 1.2168 45 3.20 1.2321 46 3.00 1.2528 47 2.80 1.2816 48 2.60 1.3111 49 2.40 1.3397 50 2.20 1.3678 51 2.00 1.3992 52 1.80 1.4348 53 1.60 1.4687 54 1.40 1.5028 55 1.20 1.5376 56 1.00 1.5685
- 57 0.80 1.0000
- 58 0.60 1.0000
- 59 0.40 1.0000
- 60 0.20 1.0000
- 61 0.00 1.0000
- Top and bottom 5 axial points excluded per Technical Specification 83.2.1.
Page 10 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn- 225 to 231 steps, inclusive 225
!.; (.552, 225) 1,1
~
200
~
(1, 187) -
~
175 ~ ~
~
Banke
.., ~
~
~
~
~ ~
1,1 'f'
~
~
~
1- (0, 114)
~
~ BankO
~
1,1
~
50 ~
'f' 25
~
0
,.. 1,1 (.070,0)
I I I I I 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction ofRATED 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, D and a control bank tip-to-tip distance of 128 steps.
Page 11 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 Figure2 K(Z)- Normalized FQ(Z) as a Function of Core Height 1.2 I
.s""
r-.= 0.8 y
- !2=
1:)!)
=
=-'1:1 Ill Ill
.!::l
-; 0.6 E
c"" Core Height (ft.)
z K(Z)
I 0.000 1.000
~ 6.000 1.000
~ 12.000 1.000 0.4 FQ=2.50 0.2 0
0 2 4 6 8 10 12 Core Height (feet)
Page 12 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 Figure3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110
(-12, 100) (+9, 100)
I 100 UNACCEPTABLE I '~ I UNACCEPTABLE
=
~
~
0 90 r-- OPERATION I
I \
I OPERATION r--
vI 80
\
=- ACCEPTABLE
~ OPERATION
'\
70
~
= 60
~
I 1\
v E-o Q
~
E-o
...~
Cl 50
(-25, 50) (+24, 50)
~ 40 a.
Gl
- =
Cl
=- 30 20 10 0
50 -40 -30 -20 -10 0 10 20 30 40 50 60 Axial Flux Difference (Delta 1) %
Page 13 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 28 June 2016 Figure 4 Reactor Core Safety Limits 680 IQ...
UNACCEPTABLE OPERATION l
r--.... r-.. I 660 .........
r---...
lo... ..........
r-...... .......... r-......
~
r-...... ......... r-......
640 ...... r--.... .....
I'- .....
r--... r--....
r--.... ......... ..........
~ r-.... r--.... ~
................ 1""-- ..........
t...... ..... i\ ~2425psig lx.... ............... 1""-- ......... \
I'- ..........
..... ~2235psig
\
.......... r-.... .......... r-.... t-- -.z-1985 psig
...... ....... -x-1825 psig
~"-- .......
~"-- r-....
1\
~"-- ....... I'-1'-..... \
~"-- r-.. .......... .......
600 I'- .......... 1""-- ..........
r......
~"-- ...........
I ACCEPTABLE I r-.... I'-
l OPERATION J ...... ~
580 560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of RATED THERMAL POWER)
Page 14 of 15
CORE OPERATING LIMITS REPORT. FNP UNIT I CYCLE 28 June 2016 Figure 5 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP
-24.0 r;;
~u Cl. ......
=
.!:! -24.5 """""' r-...
u ............
IS .....
u" I"r-....
Q
~ ........ .....
.s E ~""-
"Cl. ~"-~
~... -25.0 ........
~""-
.s !".
E ........
"0 Q
~
-25.5 16000 17000 18000 19000 20000 Cycle Burnup (MWD/MTU)
Cycle Burnup Moderator Temperature (MWD/MTU) Coefficient (pcm/°F) 16000 -24.36 17000 -24.57 18000 -24.77 19000 -24.96 20000 -25.16 Page 15 of 15