ML020580392

From kanterella
Jump to navigation Jump to search
Unit 1 Cycle 18 Core Operating Limits Report Revision 2
ML020580392
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 02/04/2002
From: Dennis Morey
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML020580392 (18)
v • d • e


Text

Dave Morey Southern Nuclear Vice President Operating Company, Inc.

Farley Project Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5131 SOUTHERN N..

COMPANY February 4, 2002 Energy to Serve Your World SM Docket No.: 50-348 NEL-02-0027 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant - Unit 1 Cycle 18 Core Operating Limits Report Revision 2 Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company submits the enclosed Core Operating Limits Report (COLR) revision for Farley Nuclear Plant Unit 1 Cycle 18. The Revision 2 COLR reflects changes to the W(Z) Curves (Figures 4 - 7).

If there are any questions, please advise.

Respectfully submitted, Dave Morey MGE/kw: colr08.doc

Enclosure:

FNP Core Operating Limits Report Unit 1 - Cycle 18 Revision 2 1ý()\ '

-- \,

-\

Page 2 U. S. Nuclear Regulatory Commission cc: Southern Nuclear Operating Company Mr. L. M. Stinson, General Manager - Farley U. S. Nuclear Regulatory Commission, Washington, D. C.

Mr. F. Rinaldi, Licensing Project Manager - Farley U. S. Nuclear Regulatory Commission, Region I Mr. L. A. Reyes, Regional Administrator Mr. T. P. Johnson, Senior Resident Inspector - Farley

ENCLOSURE Core Operating Limits Report Joseph M. Farley Nuclear Plant Unit 1 - Cycle 18 Revision 2 December 2001

,* CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 CYCLE 18 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 l and 2 (with keff> 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 kff < 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 - FH 3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) 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

S CORE OPERATIN G LIM ITS REPORT, FNP UNIT 1 CYCLE 18, REV . 2 DECEM BER 2001 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(f-Ž 1.0') (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent A/k.

2.2 SHUTDOWN MARGIN - MODES 2 (with fr < 1.0), 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (kfr < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Ak/k.

2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent Ak/k.

2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOL/ARO/HZP-MTC shall be less than or equal to +0.7 x 10-4 Ak/'/°F for power levels up to 70 percent RTP with a linear ramp to 0 Ak/k/°F at 100 percent RTP.

The EOL/ARO/RTP-MTC shall be less negative than -4.3 x 1 0 -4 Ak/k/°F.

2.3.2 The MTC Surveillance limits are:

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

-3.65 x 10-4 Ak'k/0 F.

The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 10-4 Ak/k/°F.

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 Page 2 of 15

4A CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 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 1.

2.6 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3.2.1)

F RTP 2.6.1 FQ(Z)<* Q P *JK(Z) for P > 0.5 F RTP FQ(Z)< -

  • K(Z) for P _<0.5

0.5 where

P THERMAL POWER RATED THERMAL POWER 2.6.2 F"r? =2.50 2.6.3 K(Z) is provided in Figure 2.

FRTP . K(Z) 2.6.4 FQ(Z) <- Q for P > 0.5 P*W(Z)

FRTP , K(Z)

FQ(Z) 0 ." *K(Z) for P < 0.5 0.5**w(z) 2.6.5 W(Z) values are provided in Figures 4 through 7.

2.6.6 The FQ (Z) penalty factors are provided in Table 1.

Page 3 of 15

4L CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F.N. (Specification 3.2.2) 2.7.1 FL <-FfP *(1+ PF,,, *(1- P))

where: P THERMAL POWER RATED THERMAL POWER 2.7.2 F]f4p = 1.70 2.7.3 PFA =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 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) 2.10.1 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 8.

2.11 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT)

Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) setpoint parameter values for TS 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 > 263,400 GPM when using the precision heat balance method and > 264,200 GPM when using the elbow tap method.

This concentration bounds the condition of klff* 0.95 (all rods in less the most reactive rod) and subcriticality (411 rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B'° depletion.

Page 4 of 15

4L CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Table 1 FQ(Z) PENALTY FACTOR Cycle FQ(Z)

Burnup Penalty (MWD/MTU) Factor 4644 1.020 4848 1.023 5052 1.021 5256 1.020 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 burnup 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 5 of 15

4 CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)

Setpoint Parameter Values T' < 577.20 F P' = 2235 psig K1 = 1.17 K2 = 0.017/OF Ks = 0.000825/psi t 1 >30 sec ",2:54 sec "r4 = 0 sec -,5 6 sec ,!< 6 sec f1(AI) = -2.48 {23 + (q, - qb)} vv'hen (q, - qb) < -23% RTP 0% of RTP vwhen -23% RTP < (q, --q) < 15% RTP 2 .05 {(q, - q)-15} vvihen (q, - qb) > 15% RTP Page 6 of 15

    1. CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)

Setpoint Parameter Values T" < 577.20 F K 4 = 1.10 K, = 0.02/°F for increasing Tavg K6 = 0.00109/°F when T > T" K, = 0/'F for decreasing Tavg K6 = 0/7F when T < T"

"¶3>10 sec 4 = 0 sec 5< 6 sec 65 6 sec f2(AI) = 0% RTP for all Al Page 7 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 1 (.55,2, 225; 11 111 or 200 I I tA I Loll 1 8 Yl I I `l' 1 171 175 I I Lori Bank C I I LOT I I IA1 I I . I .

Loor I I I I I JýA I I 3 150 1 .001 1 1 1 1 1 Y l I I I I

I I I IA 1 1 1.4 111 11 1 1 LA I I bn I I I I I

c. 125 V1 I I I I I I I I jrl I I II I I I 0 (0, 114) 0 11011 1 a.

C Bank D

-V - - - . -t to 75 0

cc 50 25 1 1 1 11 1 00

.(.070,0)-

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction 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 128 steps.

Page 8 of 15

4 CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1

0 0.8 LL C

"0.6 a Core Height (ft.) KQZ 0.000 1.000 E

0he 6.000 1.000 z 12.000 1.000 N 0.4

____________- F0 2.50- ___

0.2 0

0 2 4 6 8 10 12 Core Height (feet)

Page 9 of 15

A CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110 -!- 21! 222221F1111L L J (-12, 100)

I I

(+9, 100) ilia 4 4 -b-4i I 1.i i . I__ I __I I I I I I UU 90 -

UNACCEPTABLE /4.4,cc-4,-, \

I I I UNACCEPTABLE I I

/

"I 0

80 OPERATION I I II / \ II OPERATION I I I

__ACCEPTABLE _

70 V"Cu OPERATION 4

I, 60 0

50 I. (-30, 50) (+24, 50) 0 40 90 30 20 10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (Delta I) %

Page 10 of 15

4 CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Figure 4 RAOC W(Z) at 150 MWD/MTU Axial Elevation BOL Point (fet) w(z)

  • 1 12.00 1.0000
  • 2 11.80 1.0000 1.60
  • 3 11.60 1.0000
  • 4 11.40 1.0000
  • 5 11.20 1.0000
  • 6 11.00 1.0000
  • 7 10.80 1.0000
  • 8 10.60 1.0000
  • 9 10.40 1.0000
  • 10 10.20 1.0000 11 10.00 1.2141 12 9.80 1.2076 13 9.60 1.2024 14 9.40 1.1975 15 9.20 1.1911 16 9.00 1.1812 17 8.80 1.1783 18 8.60 1.1871 19 8.40 1.1982 20 8.20 1.2069 21 8.00 1.2134 22 7.80 1.2178 23 7.60 1.2201 24 7.40 1.2205 25 7.20 1.2201 26 7.00 1.2186 27 6.80 1.2156
  • 1.30 28 6.60 1.2111 29 6.40 1.2055 30 6.20 1.1989 31 6.00 1.1450 32 5.80 1.1385 33 5.60 1.1392 34 5.40 1.1491 35 5.20 1.1604 36 5.00 1.1712 37 4.80 1.1814 38 4.60 1.1907 39 4.40 1.1990 40 4.20 1.2063 41 4.00 1.2124 42 3.80 1.2174 43 3.60 1.2210 44 3.40 1.2244 45 3.20 1.2326 46 3.00 1.2409 47 2.80 1.2569 48 2.60 1.2839 49 2.40 1.3100 50 2.20 1.3358 51 2.00 1.3612
  • 52 1.80 1.0000
  • 53 1.60 1.0000
  • 54 1.40 1.0000 0 2 4 6 8 10 12
  • 55 1.20 1.0000
  • 56 1.00 1.0000 Core Height (feet)
  • 57 0.80 1.0000
  • 58 0.60 1.0000
  • 59 0.40 1.0000
  • 60 0.20 1.0000
  • 61 1 0.00 1 1.0000
  • Top and Bottom 15% Excluded per Technical Snecification B3.2. 1.

This figure is referred to by Technical Specification B3.2. 1.

Page 11 of 15

A CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Figure 5 RAOC W(Z) at 4000 MWD/MTU Axial Elevation MOL-1 Point (feet) W(Z)

  • 1 12.00 1.0000 2 11.80 1.0000 1.60
  • 3 11.60 1.0000
  • 4 11.40 1.0000
  • 5 11.20 1.0000
  • 6 11.00 1.0000
  • 7 10.80 1.0000
  • 8 10.60 1.0000
  • 9 10.40 1.0000
  • 10 10.20 1.0000 1.50 1i 10.00 1.2512 12 9.80 1.2412 13 9.60 1.2303 14 9.40 1.2185 15 9.20 1.2058 16 9.00 1.1931 17 8.80 1.1928 18 8.60 1.2049 19 8.40 1.2139 1.40 20 8.20 1.2205 21 8.00 1.2248 22 7.80 1.2268 23 7.60 1.2266 24 7.40 1.2243 25 7.20 1.2208 26 7.00 1.2158 27 6.80 1.2093 N 1.30 28 6.60 1.2013 29 6.40 1.1921 30 6.20 1.1817 31 6.00 1.1478 A 32 5.80 1.1347 33 5.60 1.1254

.1 34 5.40 1.1276 35 5.20 1.1342 36 5.00 1.1404 1.20 A hAA 4.80 1.1458 37 38 4.60 1.1505 39 4.40 1.1544 40 4.20 1.1573 41 4.00 1.1594 42 3.80 1.1603 43 3.60 1.1610 44 3.40 1.1628 1.10 45 3.20 1.1633 1 1 46 13.00 1.1721 47 2.80 1.1881 48 2.60 1.2092 49 2.40 1.2301 50 2.20 1.2528 51 2.00 1.2742

  • 52 1.80 1.0000
  • 53 1.60 1.0000 1.00 1.40 1.0000
  • 54 0 2 4 6 8 10 12
  • 55 1.20 1.0000
  • 56 1.00 1.0000 Core Height (feet)
  • 57 0.80 1.0000
  • 58 0.60 1.0000
  • 59 0.40 1.00
  • 60 0.20 1.D000

This figure is referred to by Technical Specification B3.2.1.

Page 12 of 15

4k CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Figure 6 RAOC W(Z) at 10000 MWD/MTU Axial Elevation MOL-2 Point (feet) W(Z) 1 12.00 1.0000

  • 2 11.80 1.0000 1.60
  • 3 11.60 1.0000
  • 4 11.40 1.0000
  • 5 11.20 1.0000
  • 6 11.00 1.0000
  • 7 10.80 1.0000
  • 8 10.60 1.0000
  • 9 10.40 1.0000
  • 10 10.20 1.0000 1.50 I1 10.00 1.2482 12 9.80 1.2377 13 9.60 1.2323 14 9.40 1.2262 15 9.20 1.2196 16 9.00 1.2116 17 8.80 1.2175 18 8.60 1.2297 1.40 19 8.40 1.2444 20 8.20 1.2561 21 8.00 1.2650 22 7.80 1.2712 23 7.60 1.2747 24 7.40 1.2755 25 7.20 1.2738 26 7.00 1.2707 N

N 27 6.80 1.2659 1.30 +-4-4-I-I-4-4-4.-4.-+-4 28 6.60 1.2590 29 6.40 1.2502 30 6.20 1.2397 31 6.00 1.2039 32 5.80 1.1898 33 5.60 1.1772 34 5.40 1.1737 AA 35 5.20 1.1730 1.20 36 5.00 1.1714' 37 4.80 1.1684 38 4.60 1.1642 39 4.40 1.1589 40 4.20 1.1523 41 4.00 1.1456 42 3.80 1.1401 43 3.60 1.1368 44 3.40 1.1332 1.10 45 3.20 1.1291 46 3.00 1.1274 47 2.80 1.1332 48 2.60 1.1379 49 2.40 1.1451 50 2.20 1.1546 51 2.00 1.1643

  • 52 1.80 1.0000 1.00
  • 53 1.60 1.0000
  • 54 1.40 1.0000 0 2 4 6 8 10 12
  • 55 1.20 1.0000
  • 56 1.00 1.0000 Core Height (feet)
  • 57 0.80 1.0000
  • 58 0.60 1.0000
  • 59 0.40 1.0000
  • 60 0.20 1.0000

This figure is referred to by Technical Specification B3.2.1.

Page 13 of 15

4A CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Figure 7 RAOC W(Z) at 18000 MWD/MTU Axial Elevation EOL Point (feet) W(Z)

  • 1 12.00 1.0000 1.60
  • 2 11.80 1.0000
  • 3 11.60 1.0000
  • 4 11.40 1.0000
  • 5 11.20 1.0000
  • 6 11.00 1.0000
  • 7 10.80 1.0000
  • 8 10.60 1.0000
  • 9 10.40 1.0000
  • 10 10.20 1.0000 1.50 11 10.00 1.2352 12 9.80 1.2287 13 9.60 1.2245 14 9.40 1.2216 15 9.20 1.2294 16 9.00 1.2499 17 8.80 1.2717 18 8.60 1.2897 1.40 19 8.40 1.3097 20 8.20 1.3289 21 8.00 1.3447 22 7.80 1.3564 23 7.60 1.3645 A 24 7.40 1.3688 25 7.20 1.3696 A 26 7.00 1.3670 "N1.30 27 6.80 1.3614 A 28 6.60 1.3528 29 6.40 1.3417 30 6.20 1.3280 31 6.00 1.2868 32 5.80 1.2685 33 5.60 1.2504 34 5.40 1.2437 A A, 35 5.20 1.2414 1.20 36 5.00 1.2374 A 37 4.80 1.2313 38 4.60 1.2235 39 4.40 1.2144

'40 4.20 1.2033 41 4.00 1.1905 42 3.80 1.1756 43 3.60 1.1618 44 3.40 1.1524 1.10 45 3.20 1.1404 46 3.00 1.1400 47 2.80 1.1529 48 2.60 1.1696 49 2.40 1.1854 50 2.20 1.2008 51 2.00 1.2162

  • 52 1.80 1.0000 1.00
  • 53 1.60 1.0000
  • 54 1.40 1.0000 0 2 4 6 8 10 12
  • 55 1.20 1.0000
  • 56 1.00 1.0000 Core Height (feet)
  • 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

.. *J IU DJLWIU i~7 coE--L..IUl4 _J_

Tpcicalu mei.-/oo Bx3..I.uddpe Technical SSpecification 133.2. 1.

This figure is referred to by Technical Specification B3.2. 1.

Page 14 of 15

4 CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18, REV. 2 DECEMBER 2001 Figure 8 Reactor Core Safety Limits 680 UNACCEPTABLE OPERATION 660 X%

640

-- *--2425 psig u ACEPABJ 2235 psig 620

-- 1985 psig "B~

OPRAIO -X- 1825 psig 600 580 560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of Rated Thermal Power)

Page 15 of 15

Retrieved from "https://kanterella.com/w/index.php?title=ML020580392&oldid=2711862"