DCL-14-024, Core Operating Limits Report for Cycle 19

Core Operating Limits Report for Cycle 19

ML14085A483
Person / Time
Site:	Diablo Canyon
Issue date:	03/27/2014
From:	Welsch J Pacific Gas & Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PG&E Letter DCL-14-024
Download: ML14085A483 (16)

Text

Pacific Gas and Electric Company Diablo Canyon Power Plant James M. Welsch Station Director Mail Code 104/5/502 P. O. Box 56 Avila Beach, CA 93424 805 .545 .3242 March 27, 2014 Internal: 691.3242 Fax: 805.545.4234 Internet: JMW1@pge.com PG&E Letter DCL-14-024 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 Operating Limits Report for Unit 1 Cycle 19

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 19.

Pacific Gas and Electric Company makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.

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

Sjncerely,

,JJ. . ,4vU.J..L,_J_

J~ WelsCh J8L3/4486/60052827 -360 Enclosure cc: Diablo Distribution cc/enc: Peter J. Bamford, NRC Project Manager Marc L. Dapas, NRC Region IV Thomas R. Hipschman, NRC Senior Resident Inspector A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway. Comanche Peak. Diablo Canyon. Palo Verde. Wolf Creek

Enclosure PG&E Letter DCL-14-024 CORE OPERATING LIMITS REPORTS (COLR)

DIABLO CANYON POWER PLANT UNIT 1, CYCLE 19 EFFECTIVE DATE March 9, 2014

• • • ISSUED FOR USE BY: _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ _ EXPIRES: _ _ _ _ _ ***

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 NUCLEAR POWER GENERATION REVISION 8 DIABLO CANYON POWER PLANT PAGE 1 OF 14 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 1 1

03/09/14 EFFECTIVE DATE CLASSIFICATION: QUALITY RELATED

1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 19 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 keff < 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 ~H

• 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 COLR_lulr08.DOC 04B 0307.1045

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 2 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 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 shall be greater than or equal to 1.6% ~k/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% ~k/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% ~k/k. However, an administrative value of 1.6 % ~k/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 -3.9x10-4 ~k/k/oF 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 ~k/k/oF (all rods withdrawn, RATED THERMAL POWER condition).

2.2.3 The MTC 60 ppm surveillance limit is -3.72x10-4 ~k/k/oF (all rods withdrawn, RATED THERMAL POWER condition).

2.3 Shutdown Bank Insertion Limits (TS 3.1.5) 2.3.1 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.

COLR_lulr08.DOC 04B 0307.1045

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 3 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 2.5 Heat Flux Hot Channel Factor - FQ(Z) (TS 3.2.1)

F RTP 2.5.1 FQ(Z)<-Q-*K(Z) for P> 0.5 P

F RTP FQ(Z)<-Q-*K(Z) forP~0.5 0.5 THERMAL POWER where: P RATED THERMAL POWER F~TP = 2.58 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 bumups 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 bumup not listed in the table, but less than the maximum listed bumup, values at 3 or more bumup 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 bumup steps.

For W (Z) data at a desired bumup outside of the listed bumup 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 bumup steps, a linear fit can be used for both interpolation and extrapolation.

The W (Z) values are generated assuming that they will be used for full power surveillance. When using a flux map instead of the Power Distribution Monitoring System (PDMS) for part power surveillance, the W(Z) values must be increased by the factor lIP (P > 0.5) or 1/0.5 (P .:s 0.5), where P is the core relative power during the surveillance, to account for the increase in the FQ(Z) limit at reduced power levels.

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 ~ (Z) per SR 3.2.1.2. A 2% penalty factor shall be used at all cycle bumups that are outside the range of Table 1.

COLR_lulr08.DOC 04B 0307.1045

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 4 OF 14 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 g (Z) and F ~ (Z) satisfy the following:

a. Using the moveable inc ore 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 RTP *K(Z)

FC(Z)< Q forP> 0.5 Q p FRTP *K(Z)

FC(Z)< Q forP~0.5 Q 0.5 W pRTP F (Z) <-Q-*K(Z) for P > 0.5 Q P FRTP F W (Z) ~-Q-*K(Z) for P ~ 0.5 Q 0.5 where:

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

F ~TP is the FQ limit K(Z) is the normalized F Q(Z) as a function of core height P is the relative THERMAL POWER, and F ~ (Z) is the total peaking factor, Fg (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.

F~TP and K(Z) are specified in 2.5.1 and W(Z) is specified in 2.5.2.

COLR_lulrOS.DOC 04B 0307.1045

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 5 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F ~H (TS 3.2.2) where:

THERMAL POWER p

RATED THERMAL POWER F ~H = Measured values of F ~ obtained by using the moveable inc ore detectors to obtain a power distribution map.

F~~P = 1.586 (prior to including 4% uncertainty)

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

If the PDMS is OPERABLE, the uncertainty, UFL'l.H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F ~ , shall be calculated by the following formula:

where: UL'l.H = Uncertainty for enthalpy rise as defined in equation (5-19) in Reference 6.2. However, if the uncertainty is less than 4.0, the uncertainty should be set equal to 4.0. F ~P = 1.65 for PDMS (in the above Section 2.6 equation).

If the PDMS is OPERABLE, the uncertainty, U FQ, to be applied to the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated by the following formula:

UFQ=(1.0+~J*Ue 100.0 where: U Q= Uncertainty for power peaking factor as defined in equation (5-19) in Reference 6.2.

U e = Engineering uncertainty factor

= 1.03 If the PDMS is inoperable, the Nuclear Enthalpy Rise Hot Channel Factor, F ~H ' 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_1u1rOS.DOC 04B 0307.1045

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 6 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 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 keffofO.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 DNB 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 of2% Per 31 EFPD" 3.2 Table 2A, "Load Follow W(Z) Factors at 150 and 3,000 MWDIMTU as a Function of Core Height" 3.3 Table 2B, "Load Follow W(Z) Factors at 12,000 and 20,000 MWDIMTU as a Function of Core Height"

4. FIGURES 4.1 Figure 1, "Control Bank Insertion Limits Versus Rated Thermal Power" 4.2 Figure 2, "AFD Limits as a Function of Rated Thermal Power"

5. RECORDS None

6. REFERENCES 6.1 NF-PGE-13-87, "Diablo Canyon Unit 1 Cycle 19 Reload Evaluation and Core Operating Limits Report," November 2013 6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August 1994 6.3 Westinghouse Nuclear Safety Advisory Letter NSAL-02-14, "Steam Line Break During Mode 3 for Westinghouse NSSS Plants," Revision 2, August 4, 2005 COLR_lulrOS.DOC 04B 0307.1045

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 7 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1

7. ANALYTICAL METHODS The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

7.1 WCAP-10216-P-A, Revision lA, "Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification," February 1994.

7.2 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

7.3 WCAP-8385, "Power Distribution Control and Load Following Procedures," September 1974. Approved by NRC Safety Evaluation dated January 31,1978.

7.4 WCAP-I0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

7.5 WCAP-I0054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection Into the Broken Loop and COSI Condensation Model," July 1997.

7.6 WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2 - 5 (Revision 1), "Code Qualification Document for Best-Estimate LOCA Analysis," March 1998.

7.7 WCAP-12945-P-A, Addendum I-A, Revision 0, "Method for Satisfying 10 CFR 50.46 Reanalysis Requirements for Best Estimate LOCA Evaluation Models," December 2004.

7.8 WCAP-8567-P-A, "Improved Thermal Design Procedure," February 1989.

7.9 WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DUffiLOCANYONPOWERPLANT REVISION 8 PAGE 8 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 1: FQ Margin Decreases in Excess of2% Per 31 EFPD Cycle Max. % Decrease Bumup in FQ Margin (MWDIMTU) 313 2.00 475 2.09 638 2.56 800 2.82 963 2.84 1126 2.63 1288 2.25 1451 2.00 5028 2.00 5191 2.03 5353 2.37 5516 2.70 5678 3.03 5841 3.21 6004 3.02 6166 2.84 6329 2.67 6491 2.49 6654 2.33 6817 2.18 6979 2.03 7142 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 bumups.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 9 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2A: Load Follow W(Z) Factors at 150 and 3000 MWDIMTU as a Function of Core Height HEIGHT 150 MWDIMTU HEIGHT 3000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z)

• 0.0 1.5121 *0.0 1.5315

• 2.4 1.5086 *2.4 1.5275

• 4.8 1.5016 *4.8 1.5197

• 7.2 1.4924 *7.2 1.5094

• 9.7 1.4809 *9.7 1.4966 12.1 1.4660 12.1 1.4799 14.5 1.4492 14.5 1.4612 16.9 1.4305 16.9 1.4402 19.3 1.4105 19.3 1.4173 21.7 1.3892 21.7 1.3929 24.1 1.3670 24.1 1.3675 26.6 1.3440 26.6 1.3411 29.0 1.3204 29.0 1.3143 31.4 1.2952 31.4 1.2860 33.8 1.2699 33.8 1.2579 36.2 1.2505 36.2 1.2375 38.6 1.2382 38.6 1.2250 41.0 1.2286 41.0 1.2168 43.5 1.2185 43.5 1.2133 45.9 1.2106 45.9 1.2094 48.3 1.2053 48.3 1.2042 50.7 1.2003 50.7 1.1978 53.1 1.1940 53.1 1.1906 55.5 1.1869 55.5 1.1825 58.0 1.1790 58.0 1.1735 60.4 1.1701 60.4 1.1638 62.8 1.1611 62.8 1.1533 65.2 1.1505 65.2 1.1423 67.6 1.1394 67.6 1.1324 70.0 1.1454 70.0 1.1291

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 10 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2A: Load Follow W(Z) Factors at 150 and 3000 MWDIMTU as a Function of Core Height (Continued)

HEIGHT 150 MWDIMTU HEIGHT 3000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.1571 72.4 1.1340 74.9 1.1672 74.9 1.1457 77.3 1.1766 77.3 1.1553 79.7 1.1847 79.7 1.1642 82.1 1.1915 82.1 1.1719 84.5 1.1967 84.5 1.1781 86.9 1.2003 86.9 1.1830 89.3 1.2019 89.3 1.1866 91.8 1.2014 91.8 1.1884 94.2 1.1985 94.2 1.1881 96.6 1.1931 96.6 1.1856 99.0 1.1855 99.0 1.1804 101.4 1.1744 101.4 1.1735 103.8 1.1606 103.8 1.1672 106.2 1.1580 106.2 1.1647 108.7 1.1604 108.7 1.1719 111.1 1.1705 111.1 1.1946 113.5 1.1828 113.5 1.2186 115.9 1.1953 115.9 1.2433 118.3 1.2218 118.3 1.2665 120.7 1.2523 120.7 1.2858 123.1 1.2780 123.1 1.2967 125.6 1.3000 125.6 1.3008 128.0 1.3218 128.0 1.3050 130.4 1.3431 130.4 1.3053 132.8 1.3557 132.8 1.3021

• 135.2 1.3601 *135.2 1.2883

• 137.6 1.3493 *137.6 1.2749

• 140.0 1.3078 *140.0 1.2906

• 142.5 1.2456 *142.5 1.3062

• 144.9 1.1955 *144.9 1.3219

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 11 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWDIMTU as a Function of Core Height HEIGHT 12000 MWDIMTU HEIGHT 20000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z)

• 0.0 1.3047 *0.0 1.3314

• 2.4 1.2967 *2.4 1.3332

• 4.8 1.2869 *4.8 1.3309

• 7.2 1.2763 *7.2 1.3257

• 9.7 1.2648 *9.7 1.3176 12.1 1.2505 12.1 1.3061 14.5 1.2357 14.5 1.2932 16.9 1.2233 16.9 1.2795 19.3 1.2147 19.3 1.2655 21.7 1.2059 21.7 1.2512 24.1 1.1967 24.1 1.2367 26.6 1.1876 26.6 1.2218 29.0 1.1783 29.0 1.2067 31.4 1.1684 31.4 1.1904 33.8 1.1591 33.8 1.1742 36.2 1.1479 36.2 1.1602 38.6 1.1435 38.6 1.1614 41.0 1.1456 41.0 1.1779 43.5 1.1502 43.5 1.1909 45.9 1.1540 45.9 1.2027 48.3 1.1569 48.3 1.2133 50.7 1.1591 50.7 1.2224 53.1 1.1616 53.1 1.2292 55.5 1.1652 55.5 1.2340 58.0 1.1676 58.0 1.2375 60.4 1.1694 60.4 1.2376 62.8 1.1691 62.8 1.2433 65.2 1.1693 65.2 1.2669 67.6 1.1841 67.6 1.2870 70.0 1.2037 70.0 1.3055

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DUffiLOCANYONPOWERPLANT REVISION 8 PAGE 12 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWDIMTU as a Function of Core Height (continued)

HEIGHT 12000 MWDIMTU HEIGHT 20000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.2211 72.4 1.3209 74.9 1.2368 74.9 1.3335 77.3 1.2509 77.3 1.3434 79.7 1.2629 79.7 1.3504 82.1 1.2727 82.1 1.3543 84.5 1.2805 84.5 1.3554 86.9 1.2861 86.9 1.3535 89.3 1.2893 89.3 1.3480 91.8 1.2894 91.8 1.3382 94.2 1.2864 94.2 1.3250 96.6 1.2801 96.6 1.3078 99.0 1.2710 99.0 1.2871 101.4 1.2580 101.4 1.2621 103.8 1.2416 103.8 1.2371 106.2 1.2347 106.2 1.2354 108.7 1.2369 108.7 1.2345 111.1 1.2473 111.1 1.2319 113.5 1.2672 113.5 1.2321 115.9 1.2954 115.9 1.2364 118.3 1.3211 118.3 1.2569 120.7 1.3417 120.7 1.2818 123.1 1.3613 123.1 1.3035 125.6 1.3823 125.6 1.3258 128.0 1.3996 128.0 1.3470 130.4 1.4022 130.4 1.3618 132.8 1.4007 132.8 1.3702

• 135.2 1.3983 *135.2 1.3755

• 137.6 1.3814 *137.6 1.3654

• 140.0 1.3345 *140.0 1.3176

• 142.5 1.2676 *142.5 1.2447

• 144.9 1.2124 *144.9 1.1864

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR1 DurnLOCANYONPO~RPLANT REVISION 8 PAGE 13 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 225 __ .i __

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o 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 of Rated Thermal Power Figure 1: Control Bank Insertion Limits Versus Rated Thermal Power COLR_lulr08.DOC 04B 0307.1045

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 8 PAGE 14 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 120 I(-14, 100) I (+10,100) I 100  :-- tjUNACCEPTABLE IUNACCEPTABLE

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Figure 2: AFD Limits as a Function of Rated Thermal Power COLR_lulr08.DOC 04B 0307.1045