DCL-10-143, Core Operating Limits Report for Cycle 17

From kanterella
Jump to navigation Jump to search
Core Operating Limits Report for Cycle 17
ML103260151
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 11/10/2010
From: Becker J
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-10-143
Download: ML103260151 (15)
v • d • e


Text

N Pacific Gas and Electric Company James R. Becker Site Vice President Diablo Canyon Power Plant Mail Code 104/5/601 R 0. Box 56 Avila Beach, CA 93424 805.545.3462 Internal: 691.3462 Fax: 805.545.6445 November 10, 2010 PG&E Letter DCL-10-143 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,. DC 20555-0001 Docket No. 50-275, OL-DPR-80 Diablo Canyon Power Plant Unit 1 Core Operatina Limits Report for Unit 1 Cycle 17

Dear Commissioners and Staff:

In accordance with Diablo Canyon Power Plant (DCPP) Technical Specification 5.6.5.d, enclosed is the Core Operating Limits Report (COLR) for Unit 1. This document was revised for DCPP Unit 1, Cycle 17.

There are no new or revised regulatory commitments in this submittal.

If there are any questions regarding the COLR, please contact Mr. Mark Mayer at (805) 545-4674.

swh/3449/60023340 Enclosure cc:

Diablo Distribution cc/enc:

Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Alan B. Wang, NRR Project Manager A©OI A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Catlaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • San Onofre
  • Wolf Creek

Enclosure PG&E Letter DCL-10-143 CORE OPERATING LIMITS REPORTS (COLR)

DIABLO CANYON POWER PLANT UNIT 1, CYCLE 17 EFFECTIVE DATE OCTOBER 23, 2010

      • ISSUED FOR USE B Y:

PACIFIC GAS AND ELECTRIC COMPANY NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT CORE OPERATING LIMITS REPORT DATE:

EXPIRES:_

NUMBER COLR1 REVISION 4

PAGE 1 OF 13 UNIT TITLE:

COLR for Diablo Canyon Unit 1 1

10/23/10 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED I

1.

CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 17 has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.5.

1.2 The Technical Specifications affected by this report are listed below:

3.1.1 -

Shutdown Margin (MODE 2 with klff < 1.0, MODES 3, 4, and 5) 3.1.3 -

Moderator Temperature Coefficient 3.1.4 -

Rod Group Alignment Limits 3.1.5 -

Shutdown Bank Insertion Limits 3.1.6 -

Control Bank Insertion Limits 3.1.8 -

PHYSICS TESTING Exceptions - MODE 2 3.2.1 -

Heat Flux Hot Channel Factor - FQ(Z) 3.2.2 -

Nuclear Enthalpy Rise Hot Channel Factor - F N AH 3.2.3 -

Axial Flux Difference - (AFD) 3.4.1 -

RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3.9.1 -

Boron Concentration I

COLR lulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER

.REVISION PAGE UNIT COLR 1 4

2 OF 13 1

2.

OPERATING LIMITS The cycle-specific parameter limits for the TS listed in Section 1 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in TS 5.6.5.

2.1 Shutdown Margin (SDM) (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8)

The SDM limit for MODE 1, MODE 2, MODE 3 and MODE 4 is:

2.1.1 The shutdown margin with Safety Injection enabled shall be greater than or equal to 1.6% Ak/k.

2.1.2 In Modes 3-or 4 the shutdown margin with Safety Injection blocked shall be greater than or equal to 1.6% Ak/k calculated at a temperature of 200'F.

The SDM limit for MODE 5 is:

2.1.3 The shutdown margin shall be greater than or equal to 1.0% Ak/k. However, an administrative value of 1.6 % Ak/k will be used to address concerns of NSAL-02-014.

2.2 Moderator Temperature Coefficient (MTC) (TS 3.1.3)

The MTC limit for MODES 1; 2, and 3 is:

2.2.1 The MTC shall be less negative than - 3.9xl04 Ak/k/°F for all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.

2.2.2 The MTC 300 ppm surveillance limit is -3.0x10- 4 Ak/k/°F (all rods withdrawn, RATED THERMAL POWER condition).

2.2.3 The MTC 60 ppm surveillance limit is -3.72x104 Ak/k/0F (all rods withdrawn, RATED THERMAL POWER condition).

2.3 Shutdown Bank Insertion Limits (TS 3.1.5) 2.3.i Each shutdown bank shall be withdrawn to at least 225 steps.

2.4 Control Bank Insertion Limits (TS 3.1.6) 2.4.1 The control banks shall be limited in physical insertion as shown in Figure 1.

J COLR lulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 4

PAGE 3 OF 13 TITLE:

COLR for Diablo Canyon Unit 1 UNIT 1

2.5 Heat Flux Hot Channel Factor - FQ(Z) (TS 3.2.1)

F ýrp 2.5.1 Fq(Z)<< r-*K(Z) forP>0.5 P

F RTP FQ (Z)< Q *K(Z) for P*_ 0.5 0.5 THERMAL POWER where: P =

RATED THERMAL POWER FRTP -2.58 Q

K(Z) = 1.0 NOTE: The W(Z) data is appropriate for use only if the predicted axial offset is within

+/-3% of the measured value.

2.5.2 The W(Z) data for Relaxed Axial Offset Control (RAOC) operation, provided in Tables 2A and 2B are sufficient to determine the RAOC W(Z) versus core height for Cycle 16 burnups through the end of full power reactivity plus a power coast down of up to 1000 MWD/MTU.

For W(Z) data at a desired burnup not listed in the table, but less than the maximum listed burnup, values at 3 or more burnup steps should be used to interpolate the W(Z) data to the desired bumup with a polynomial type fit that uses the W(Z) data for the nearest three burnup steps.

For W(Z) data at a desired burnup outside of the listed burnup steps, a linear extrapolation of the W(Z) data for the nearest two bumup steps can be used. If data are listed for only 2 burnup steps, a linear fit can be used for both interpolation and extrapolation.

Table. 1 shows FQ margin decreases that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase F W (Z) per SR 3.2.1.2. A 2% penalty factor shall be usedat all cycle bumups that are outside the range of Table 1.

COLR lulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 4

PAGE 4 OF 13 TITLE:

COLR for Diablo Canyon Unit 1 UNIT 1

2.5.3 FQ(Z) shall be evaluated to determine if it is within its limits by verifying that F C (Z) and F W (Z) satisfy the following:

a.

Using the moveable incore detectors to obtain a power distribution map in MODE 1.

b.

Increasing the measured FQ(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.

c.

Satisfying the following relationship:

F

)(Z) for P> 0.5 P

RTP *K(Z)

FQ (Z)*

0.

for P*_ 0.5 Q

0.5 W

FRTP F

(Z)< Q *K(Z) forP>0.5 Q

P FRTP FQ*

Fr (Z)

Q.5 *K(Z) for P

0.5 where

F C (Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty.

F RTP is the FQ limit Q

F K(Z) is the normalized FQ(Z) as a function of core height P is the relative THERMAL POWER, and F

(Z) is the total peaking factor, F C (Z), multiplied by W(Z) Which gives the maximum FQ(Z) calculated to occur in normal operation.

W(z) is the cycle dependent function that accounts for power distribution, transients encountered during normal operation.

FRTP and K(Z) are specified in 2.5.1 and W(Z) is specified in 2.5.2.

Q COLRlulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 4 PAGE 5 OF 13 TITLE:

COLR for Diablo Canyon Unit 1 UNIT 1

2.6 Nuclear Enthalpy Rise Hot Channel Factor - F N (TS 3.2.2)

F N

< RTP *[1+ PF. * (l-P)]

AH -AR HHI where:

THERMAL POWER RATED THERMAL POWER F N

= Measured values of F N obtained by using the moveable incore detectors to AR AR obtain a power distribution map.

FRTP AR

= 1.586 (prior to including 4% uncertainty)

PFH

= 0.3 = Power Factor Multiplier 2.7 Power Distribution Measurement Uncertainty (TS 3.2.1. and TS 3.2.2):

If the Power Distribution Monitoring System (PDMS) is OPERABLE, the uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F N shall be calculated by the following formula:

UFA =1.0+ UAH 100.0 where:

UAH = Uncertainty for enthalpy rise as defined in equation (5-19) in Reference 6.2 and F RTP = 1.65 for PDMS (in the above Section 2.6 AR equation).

If the PDMS is OPERABLE, the uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor, FQ(z), ýhall be calculated by the following formula:

=( +UQ UFOQ 0 1-00.0,J*Ue where:

UQ = Uncertainty for power peaking factor as defined in equation (5-19) in Reference 6.2.

Ue Engineering uncertainty factor

=1.03 If the PDMS is inoperable, the Nuclear Enthalpy Rise Hot Channel Factor, F N, shall be calculated as specified in Section 2.6.

If the PDMS is inoperable, the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated as specified in Section 2.5.

COLR 1ulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER REVISION PAGE UNIT COLR 1 4

6 OF 13 1

2.8 Axial Flux Difference (TS 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Limits are provided in Figure 2.

2.9 Boron Concentration (TS 3.9.1)

The refueling boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the more restrictive of the following limits:

2.9.1 A kIff of 0.95 or less, With the most reactive control rod assembly completely withdrawn, or 2.9.2 A boron concentration of greater than or equal to 2000 ppm.

2.10 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limit (TS 3.4.1) 2.10.1 Pressurizer pressure is greater than or equal to 2175 psig.

2.10.2 RCS average temperature is less than or equal to 581.7'F.

NOTE: The DNBR RCS TAVG limit is based on the slightly lower and bounding value associated with Unit 1 in order to have the same surveillance limits for both Unit 1 and Unit 2.

3.

TABLES 3.1 Table 1, "FQ Margin Decreases in Excess of 2% Per 31 EFPD" 3.2 Table 2A, "Load Follow W(Z) Factors at 150 and 4,000 MWD/MTU as a Function of Core Height" 3.3 Table 2B, "Load Follow W(Z) Factors at 12,000 and 20,000 MWD/MTU as a Function of Core Height"

4.

FIGURES 4.1 Figure 1, "Control Bank Insertion Limits Versus Rated Thermal Power" 4.2 r igure Z, A*ArJ LiI1lmlS as a r unction of R~ateu I nermal rower

5.

RECORDS None

6.

REFERENCES 6.1 "Diablo Canyon Unit I Cycle 17 Final Reload Evaluation Revision 1," October, 2010 6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August, 1994 I

COLRIulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER REVISION PAGE UNIT COLR 1 4

7 OF 13 Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Burnup in FQ Margin (MWD/MTU) 313 2.00 475 2.71 638 3.53 800 4.07 963 4.28 1126 4.17 1288 3.79 1451 3.25 1613 2.62 1776 2.00 5353 2.00 5516 2.31 5678 2.96 5841 3.21 6004 3.18 6166 3.14 6329 3.08 6491 2.97 6654 2.81 6817 2.65 6979 2.52 7142 2.38 7304 2.23 7467 2.07 7630 2.00 NOTE: All cycle bumups outside the range of this table shall use a 2% decrease in FQ margin for compliance with SR 3.2.1.2. Linear interpolation is adequate for intermediate cycle burnups.

COLR_lulr04.DOC 04B '

1020.0724

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 4

PAGE 8 OF 13 UNIT 1

Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height HEIGHT (FEET)

  • 0.0000
  • 0.2000
  • 0.4000
  • 0.6000
  • 0.8000 1.0000 1.2000 1.4000 1.6000 1.8000 2.0000 2.2000 2.4000 2.6000 2.8000 3.0000 3.2000 3.4000 3.6000 3.8000 4.0000 4.2000 4.4000 4.6000 4.8000 5.0000 5.2000 5.4000 5.6000 5.8000 150 MWD/MTU W(Z) 1.4777 1.4732 1.4653 1.4554 1.4433 1.4285 1.4114 1.3925 1.3723 1.3511 1.3290 1.3064 1.2831 1.2593 1.2393 1.2226 1.2085 1.1988 1.1953 1.1938 1.1917 1.1883 1.1840 1.1788 1.1726 1.1656 1.1581 1.1497 1.1416 1.1484 HEIGHT (FEET)
  • 0.0000
  • 0.2000
  • 0.4000
  • 0.6000
  • 0.8000 1.0000 1.2000 1.4000 1.6000 1.8000 2.0000 2.2000 2.4000 2.6000 2.8000 3.0000 3.2000 3.4000 3.6000 3.8000 4.0000 4.2000 4.4000 4.6000 4.8000 5.0000 5.2000 5.4000 5.6000 5.8000 4000 MWD/MTU W(Z) 1.4873 1.4834 1.4758 1.4658 1.4532 1.4378 1.4196 1.3992 1.3771 1.3535 1.3289 1.3035 1.2776 1.2516 1.2253 1.2034 1.1914 1.1889 1.1879 1.1860 1.1831 1.1792 1.1744 1.1686 1.1620 1.1545 1.1465 1.1377 1.1268 1.1280
  • Top and Bottom 8% Excluded COLRIulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 4 PAGE 9 OF 13 UNIT 1

Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT (FEET) 6.0000 6.2000 6.4000 6.6000 6.8000 7.0000 7.2000 7.4000 7.6000 7.8000 8.0000 8.2000 8.4000 8.6000 8.8000 9.0000 9.2000 9.4000 9.6000 9.8000 10.0000 10.2000 10.4000 10.6000 10.8000 11.0000 "11.2000 "11.4000 "11.6000 "11.8000

  • 12.0000 150 MWD/MTU W(Z) 1.1617 1.1715 1.1809 1.1890 1.1958 1.2011 1.2048 1.2071 1.2073 1.2052 1.2006 1.1936 1.1839 1.1721 1.1649 1.1652 1.1724 1.2064 1.2441 1.2777 1.3083 1.3360 1.3589 1.3780 1.3975 1.4133 1.4216 1.4291 1.4241 1.4050 1.3893 HEIGHT (FEET) 6.0000 6.2000 6.4000 6.6000 6.8000 7.0000 7.2000 7.4000 7.6000 7.8000 8.0000 8.2000 8.4000 8.6000 8.8000 9.0000 9.2000, 9.4000 9.6000 9.8000 10.0000 10.2000 10.4000 10.6000' 10.8000 11.0000
  • 11.2000 "11.4000 "11.6000
  • 11.8000
  • 12.0000 4000 MWD/MTU W(Z) 1"1387 1.1504 1.1613 1.1712 1.1799 1.1871 1.1929 1.1975 1.2001 1.2006 1.1989 1.1947 1.1880 1.1796 1.1762 1.1780 1.1919 1.2134 1.2366 1.2596 1.2772 1.2870 1.2959 1.3033 1.3127 1.3269 1.3393 1.3362 1.3216.

1.2976 1.2757

  • Top and Bottom 8% Excluded COLR_lulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWERPLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 4

PAGE 10 OF 13 UNIT 1

Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWD/MTU as a Function of Core Height HEIGHT (FEET)

  • 0.0000
  • 0.2000
  • 0.4000
  • 0.6000
  • 0.8000 1.0000 1.2000 1.4000 1.6000 1.8000 2.0000 2.2000 2.4000 2.6000 2.8000 3.0000 3.2000.

3.4000 3.6000 3.8000 4.0000 4.2000 4.4000 4.6000 4.8000 5.0000 5.2000 5.4000 5.6000 5.8000 12000 MWD/MTU W(Z) 1.3197 1.3099 1.2991 1.2876 1.2751 1.2626 1.2515 1.2418 1.2314 1.2207 1.2098 1.1988 1.1876 1.1762 1.1653 1.1515 1.1445 1.1523 1.1594 1.1655 1.1711 1.1754 1.1787 1.1807 1.1814 1.1813 1.1799 1.1804 1.2011 1.2237 HEIGHT (FEET)

  • 0.0000
  • 0.2000
  • 0.4000
  • 0.6000
  • 0.8000 1.0000 1.2000 1.4000 1.6000 1.8000 2.0000 2.2000 2.4000 2.6000 2.8000 3.0000 3.2000 3.4000 3.6000 3.8000 4.0000 4.2000 4.4000 4.6000 4.8000 5.0000 5.2000 5.4000 5.6000 5.8000 20000 MWD/MTU W(Z) 1.3571 1.3478 1.3379 1.3282 1.3189 1.3075 1.2938 1.2796 1.2651 1.2504 1.2355 1.2204 1.2050 1.1893 1.1734 1.1570 1.1546 1.1737 1.1897 1.2039 1.2172 1.2284 1.2376 1.2446 1.2503 1.2523 1.2563 1.2770 1.2999 1.3204
  • -Top and Bottom 8% Excluded COLR_1u1r04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 4 PAGE 11 OF 13 UNIT 1

Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWDiMTU as a Function of Core Height (continued)

HEIGHT (FEET) 6.0000 6.2000 6.4000 6.6000 6.8000 7.0000 7.2000 7.4000 7.6000 7.8000 8.0000 8.2000 8.4000 8.6000 8.8000 9.0000 9.2000 9.4000 9.6000 9.8000 10.0000 10.2000 10.4000 10.6000 10.8000 11.0000 "11.2000 "11.4000 "11.6000 "11.8000

'12.0000 12000 MWD/MTU W(Z) 1.2424 1.2601 1.2756 1.2889 1.2997 1.3080

.- 1.3133 1.3157 1.3148 1.3106 1.3027 1.2916 1.2770 1.2565 1.2493 1.2488 1.2582 1.2858 1.3159 1.3436 1.3675 1.3882 1.4100 1.4291 1.4400 1.4477 1.4543 1.4454 1.4252 1.3960 1.3687 HEIGHT (FEET) 6.0000 6.2000 6.4000 6.6000 6.8000 7.0000 7.2000 7.4000 7.6000 7.8000 8.0000 8.2000 8.4000 8.6000 8.8000 9.0000 9.2000 9.4000 9.6000 9.8000 10.0000 10.2000 10.4000 10.6000 10.8000 11.0000

  • 11.2000
  • 11.4000
  • 11.6000
  • 11.8000
  • 12.0000 20000 MWD/MTU W(Z) 1.3382 1.3532 1.3653 1.3743 1.3800 1.3825 1.3818 1.3774 1.3690 1.3565 1.3398 1.3190 1.2941 1.2679 1.2511 1.2406 1.2323 1.2353 1.2539 1.2773 1.2973 1.3167 1.3349 1.3522 1.3688 1.3860 1.4010 1.4035 1.3929 1.3703 1.3505
  • Top and Bottom 8% Excluded COLRIulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 4 PAGE 12 OF 13 UNIT 1

CL I-a.

a)

Co 0

0 a-m 225 200 175 150 125 100 75

_I0 1

I (0.17,225) 068,.-

-i-_- _-

___L r-

I...

.L..

1-

~ ~~

~

-4 4-

- ( 1 0 1

7 IIII I

I I

I I

2 IIiI I

- - -(

1.

1 7 7 ) -

(0.0,183)- -

I-i--

S-II I

I III

-1 i- -

4 -- - -

IIII t

I I

H I------------

4 I

I I

I I

I I

- - E I

IIIII I

I I

I

L --.---..------..--

i.

I I

_I.

_ J III I

I I

I I

I* I I

w~

£ -

~

-~

/-TI w

III I

I I

I i

i I

t~~~~~

~~~

I.

"---'4 II I

I I

I I

I I

T L

IIIIIII I

i I

I Il I

i IIIII BIK I

F -

. T-r- -- -

IIII I

I I

I 2

I---4.------4 I

I I

I II-m r

H--

H r----

FIIIIII I

I I

I I

I II I

4

-I---

4-------

4 I---

I--- -

I-I I/:i Valid for Fully Withdrawn Rod Positions: >225 Steps And <231 Steps 11---

---. (0.29,0)11 i

I I

I I

I 50 25 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 Figure 1: Control Bank Insertion Limits Versus Rated Thermal Power COLR lulr04.DOC 04B 1020.0724

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 4

PAGE 13 OF 13 UNIT 1

120 100 80 0

C0

?5 60 40 20 0

-60

-50

-40

-30

-20

-10 0

10 20 30 40 50 60 Flux Difference (DELTA I) %

Figure 2: AFD Limits as a Function of Rated Thermal Power COLR lulr04.DOC 04B 1020.0724

Retrieved from "https://kanterella.com/w/index.php?title=DCL-10-143,_Core_Operating_Limits_Report_for_Cycle_17&oldid=5288698"