DCL-14-101, Core Operating Limits Report for Unit 2 Cycle 19

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Core Operating Limits Report for Unit 2 Cycle 19
ML14314A982
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 11/10/2014
From: Welsch J
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-14-101
Download: ML14314A982 (16)
v • d • e


Text

Pacific Gas and Electric Company James M. Welsch Diablo Canyon Power Plant Station Director Mail Code 104/5/502 P. 0. Box 56 Avila Beach, CA 93424 805.545.3242 November 10, 2014 Internal: 691 .3242 Fax: 805.545.4234 Internet: JMW1@pge.com PG&E Letter DCL-14-101 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-323, OL-DPR-82 Diablo Canyon Power Plant Unit 2 Core Operating Limits Report for Unit 2 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 2. This document was revised for DCPP Unit 2, 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. John Harmon at (805) 545-4812.

J 8 L3/4486/60062143-220 Enclosure cc: Diablo Distribution cc/enc: Marc L. Dapas, NRC Region IV Thomas R. Hipschman, NRC Senior Resident Inspector Eric R. Oesterle, NRR Project Manager 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-14-101 CORE OPERATING LIMITS REPORTS (COLR)

DIABLO CANYON POWER PLANT UNIT 2, CYCLE 19 EFFECTIVE DATE October 29, 2014

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

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 NUCLEAR POWER GENERATION REVISION 9 DliffiLOCANYONPOWERPLANT PAGE 1 OF 14 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 2 2

10/29/14 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED

1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 2 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:

  • 3.1.3 - 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_2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUffiLOCANYONPOWERPLANT REVISION 9 PAGE 2 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2

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% L1klk.

2.1.2 In Modes 3 or 4 the shutdown margin with Safety Injection blocked shall be greater than or equal to 1.6% L1klk 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 (Reference 6.3).

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 L1k/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 L1klki°F (all rods withdrawn, RATED THERMAL POWER condition).

2.2.3 The MTC 60 ppm surveillance limit is -3.72x10-4 L1klki°F (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_2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUillLOCANYONPO~RPLANT REVISION 9 PAGE 3 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.5 Heat Flux Hot Channel Factor- FQ(Z) (TS 3.2.1)

FRTP 2.5.1 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 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 po1ynomial 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 1/P (P > 0.5) or 1/0.5 (P::; 0.5), where Pis the core relative power during the surveillance, to account for the increase in the F Q(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_2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUffiLOCANYONPO~RPLANT REVISION 9 PAGE 4 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.5.3 FQ(Z) shall be evaluated to determine if it is within its limits by verifying that F 8 (Z) and F "6. (Z) satisfy the following:

a. Using the moveable incore detectors to obtain a power distribution map inMODE 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:

pRTP *K(Z)

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

F (Z)< Q for P s; 0.5 Q 0.5 W pRTP F (Z)<-Q-*K(Z) forP>0.5 Q p pRTP F ~ (Z) s; _Q_* K(Z) for P s; 0.5

0.5 where

F 8 (Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty.

FRQTP 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 "6. (Z) is the total peaking factor, F 8(Z), multiplied by W(Z) which gives the maximum F Q(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_2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 9 PAGE 5 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.6 Nuclear Enthalpy Rise Hot Channel Factor- F~H (TS 3.2.2)

FN < FRTP *[1 + PFAH * (1-P)]

~H- ~H where:

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

= 1.586 (prior to including 4% uncertainty)

= 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, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F ~H, shall be calculated by the following UMI formula: U FMI =1. 0+--

100.0 where: UAH =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, UFQ, to be applied to the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated by the following formula:

UFQ=(l.O+~J*ue 100.0 where: UQ = 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_2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 9 PAGE 6 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 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 keff 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 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 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 Figure 2, "AFD Limits as a Function of Rated Thermal Power"
5. RECORDS None
6. REFERENCES 6.1 NF-PGE-14-52, Revision 2, "Unit 2 Cycle 19 Reload Evaluation and Core Operating Limits Report Revision 2," October 22, 2014 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, Revision 2, "Steam Line Break During Mode 3 for Westinghouse NSSS Plants," August 4, 2005 COLR 2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 9 PAGE 7 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2

7. ANALYTICALMETHODS 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 1A, "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-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

7.5 WCAP-10054-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 1-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.

COLR 2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 9 PAGE 8 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD CycleBumup Max. % Decrease (MWD/MTU) inF 0 Margin 312 2.00 475 2.04 637 2.32 799 2.50 962 2.58 1124 2.54 1287 2.40 1449 2.19 1611 2.00 5995 2.00 6158 2.25 6320 2.79 6482 2.73 6645 2.60 6807 2.48 6969 2.34 7132 2.19 7294 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.

COLR 2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 9 PAGE 9 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height HEIGHT 150MWD/MTU HEIGHT 4000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.5536 *0.0 1.5245
  • 2.4 1.5305 *2.4 1.5046
  • 4.8 1.5098 *4.8 1.4856
  • 7.2 1.4905 *7.2 1.4666
  • 9.7 1.4728 *9.7 1.4474 12.1 1.4560 12.1 1.4298 14.5 1.4393 14.5 1.4130 16.9 1.4202 16.9 1.3932 19.3 1.3998 19.3 1.3718 21.7 1.3782 21.7 1.3489 24.1 1.3556 24.1 1.3249 26.6 1.3323 26.6 1.2999 29.0 1.3085 29.0 1.2749 31.4 1.2832 31.4 1.2514 33.8 1.2581 33.8 1.2304 36.2 1.2376 36.2 1.2145 38.6 1.2241 38.6 1.2037 41.0 1.2171 41.0 1.1947 43.5 1.2147 43.5 1.1869 45.9 1.2119 45.9 1.1839 48.3 1.2079 48.3 1.1813 50.7 1.2026 50.7 1.1769 53.1 1.1965 53.1 1.1721 55.5 1.1895 55.5 1.1663 57.9 1.1815 57.9 1.1597 60.4 1.1726 60.4 1.1522 62.8 1.1634 62.8 1.1446 65.2 1.1527 65.2 1.1353 67.6 1.1412 67.6 1.1253 70.0 1.1461 70.0 1.1331
  • Top and Bottom 8% Excluded COLR 2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DliffiLOCANYONPO~RPLANT REVISION 9 PAGE 10 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 150MWD/MTU HEIGHT 4000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.1575 72.4 1.1465 74.9 1.1680 74.9 1.1582 77.3 1.1776 77.3 1.1693 79.7 1.1861 79.7 1.1792 82.1 1.1933 82.1 1.1879 84.5 1.1991 84.5 1.1952 86.9 1.2031 86.9 1.2008 89.3 1.2056 89.3 1.2049 91.8 1.2070 91.8 1.2080 94.2 1.2063 94.2 1.2090 96.6 1.2033 96.6 1.2079 99.0 1.1982 99.0 1.2046 101.4 1.1904 101.4 1.1988 103.8 1.1802 103.8 1.1906 106.2 1.1725 106.2 1.1874 108.7 1.1692 108.7 1.1910 111.1 1.1676 111.1 1.1999 113.5 1.1662 113.5 1.2049 115.9 1.1671 115.9 1.2103 118.3 1.1681 118.3 1.2120 120.7 1.1695 120.7 1.2152 123.1 1.1738 123.1 1.2211 125.6 1.1813 125.6 1.2284 128.0 1.1881 128.0 1.2383 130.4 1.1943 130.4 1.2498 132.8 1.1981 132.8 1.2602

  • 135.2 1.2064 *135.2 1.2628
  • 137.6 1.2142 *137.6 1.2586
  • 140.0 1.2133 *140.0 1.2545
  • 142.5 1.2062 *142.5 1.2453
  • 144.9 1.2008 *144.9 1.2376
  • Top and Bottom 8% Excluded COLR_2u2r09 .DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DliffiLOCANYONPO~RPLANT REVISION 9 PAGE 11 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWD/MTU as a Function of Core Height HEIGHT 12000 MWD/MTU HEIGHT 20000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.2630 *0.0 1.2846
  • 2.4 1.2613 *2.4 1.2868
  • 4.8 1.2597 *4.8 1.2852
  • 7.2 1.2581 *7.2 1.2810
  • 9.7 1.2535 *9.7 1.2740 12.1 1.2460 12.1 1.2641 14.5 1.2372 14.5 1.2532 16.9 1.2278 16.9 1.2421 19.3 1.2180 19.3 1.2311 21.7 1.2080 21.7 1.2204 24.1 1.1978 24.1 1.2099 26.6 1.1876 26.6 1.1996 29.0 1.1773 29.0 1.1894 31.4 1.1664 31.4 1.1785 33.8 1.1556 33.8 1.1680 36.2 1.1523 36.2 1.1578 38.6 1.1517 38.6 1.1576 41.0 1.1515 41.0 1.1693 43.5 1.1516 43.5 1.1795 45.9 1.1504 45.9 1.1882 48.3 1.1503 48.3 1.1970 50.7 1.1534 50.7 1.2067 53.1 1.1578 53.1 1.2152 55.5 1.1608 55.5 1.2217 57.9 1.1626 57.9 1.2262 60.4 1.1636 60.4 1.2292 62.8 1.1638 62.8 1.2295 65.2 1.1655 65.2 1.2295 67.6 1.1769 67.6 1.2359 70.0 1.1911 70.0 1.2480
  • Top and Bottom 8% Excluded COLR 2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 9 PAGE 12 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 12000 MWD/MTU HEIGHT 20000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.2073 72.4 1.2589 74.9 1.2244 74.9 1.2673 77.3 1.2392 77.3 1.2741 79.7 1.2525 79.7 1.2787 82.1 1.2639 82.1 1.2810 84.5 1.2731 84.5 1.2813 86.9 1.2802 86.9 1.2796 89.3 1.2857 89.3 1.2756 91.8 1.2889 91.8 1.2685 94.2 1.2892 94.2 1.2586 96.6 1.2867 96.6 1.2461 99.0 1.2812 99.0 1.2300 101.4 1.2729 101.4 1.2123 103.8 1.2618 103.8 1.2005 106.2 1.2465 106.2 1.2014 108.7 1.2371 108.7 1.2033 111.1 1.2348 111.1 1.2034 113.5 1.2339 113.5 1.2059 115.9 1.2341 115.9 1.2148 118.3 1.2384 118.3 1.2234 120.7 1.2461 120.7 1.2292 123.1 1.2542 123.1 1.2410 125.6 1.2614 125.6 1.2629 128.0 1.2679 128.0 1.2850 130.4 1.2735 130.4 1.3067 132.8 1.2774 132.8 1.3258

  • 135.2 1.2794 *135.2 1.3207
  • 137.6 1.2783 *137.6 1.3097
  • 140.0 1.2713 *140.0 1.3067
  • 142.5 1.2586 *142.5 1.3071
  • 144.9 1.2475 *144.9 1.3074
  • Top and Bottom 8% Excluded COLR_2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 9 PAGE 13 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 225

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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 2u2r09.DOC 04B 1027.0930

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 9 PAGE 14 OF 14 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 120 I (-14, 100) I I (+ 1o, 1oo) I 100 - j UNACCEPTABLE IJ IUNACCEPTABLE OPERATION ~ OPERATION I \

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Figure 2: AFD Limits as a Function of Rated Thermal Power COLR_2u2r09.DOC 04B 1027.0930

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