DCL-15-144, Core Operating Limits Report for Cycle 20

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Core Operating Limits Report for Cycle 20
ML15335A323
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 12/01/2015
From: Nimick J
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-15-144
Download: ML15335A323 (16)
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Pacific Gas and Electric Company December 1, 2015 PG&E Letter DCL-15-144 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 20

Dear Commissioners and Staff:

Jan A. 1\\limidl Station Director Diablo Canyon Power Plant Mail Code 104/5/502 P. 0. Box 56 Avila Beach, CA 93424 805.545.6783 Internal: 691.6783 Fax: 805.545.4234 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 20.

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.

MEM6/4539/6007 4189-360 Enclosure cc:

Diablo Distribution cc/enc: Marc L. Dapas, NRC Region IV Thomas R. Hipschman, NRC Senior Resident Inspector Siva P. Lingam, NRC Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

Enclosure PG&E Letter DCL-15-144 CORE OPERATING LIMITS REPORT DIABLO CANYON POWER PLANT UNIT 1 CYCLE 20 EFFECTIVE DATE October 21, 2015

      • ISSUED FOR USE BY: _________ DATE: _____ EXPIRES: _____ ***

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

COLR for Diablo Canyon Unit 1 CLASSIFICATION: QUALITYRELATED

1.

CORE OPERATING LIMITS REPORT NUMBER COLR 1 REVISION 9

PAGE 1 OF 14 UNIT 1

10/21/15 EFFECTIVE DATE 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 20 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 3.1.3

  • 3.1.4
  • 3.1.5 3.1.6 3.1.8 3.2.1

Moderator Temperature Coefficient Rod Group Alignment Limits Shutdown Bank Insertion Limits Control Bank Insertion Limits PHYSICS TESTING Exceptions -MODE 2 Heat Flux Hot Channel Factor-FQ(Z)

Nuclear Enthalpy Rise Hot Channel Factor - F ~

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_1u1r09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1

2.

OPERATING LIMITS NUMBER COLR 1 REVISION 9 PAGE 2 OF 14 UNIT 1

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 1.6% i1klk. This limit addresses the concerns ofNSAL-02-014 (Reference 6.3) and the boron dilution analysis for RCS filled conditions.

In order to address RCS drained conditions for the boron dilution analysis, the minimum refueling boron concentration of 2000 ppm (Section 2.9.2) shall be maintained whenever -the RCS level is at or below the reactor vessel flange elevation (114 feet).

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 L1klki°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 L1k/k/°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_1u1r09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DUillLOCANYONPO~RPLANT NUMBER COLR 1 REVISION 9 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) pRTP 2.5.1 FQ(Z)<-Q-*K(Z) for P> 0.5 p

pRTP FQ(Z)<-Q-*K(Z) for P~ 0.5

0.5 where

P F~TP = 2.58 K(Z) = 1.0 THERMAL POWER RATED THERMAL POWER 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 burnups through the end of full power reactivity plus a power coast down of up to 1000 MWD/MTU.

COLR_1ulr09.DOC 04B 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 burnup 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 burnup steps can be used. If data are listed for only 2 burnup 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 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.

1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT NUMBER COLR 1 REVISION.9 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-8 (Z) and F ~ (Z) satisfy th~ following:

COLR_lulr09.DOC 04B

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)

F C (Z) < Q for P > 0.5 Q

p pRTP *K(Z)

Fc(Z)::; Q forP:-:;0.5 Q

0.5 W

pRTP F

(Z) <-Q-*K(Z)

Q p

forP>0.5 pRTP F WQ (Z) ::;-Q-*K(Z) for P :-:; 0.5

0.5 where

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

FRTP is the F limit Q

Q 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, F 8 (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.

1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 2.6 Nuclear Enthalpy Rise Hot Channel Factor_- F ~H (TS 3.2.2)

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

~H-

~H where:

THERMAL POWER p

RATED THERMAL POWER NUMBER COLR 1 REVISION 9 PAGE 5 OF 14 UNIT 1

F ~H

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

F ~~P

= 1.586 (prior to including 4% uncertainty)

PF Llli

= 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, UFLlli, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F ~H, shall be calculated by the following formula:

utili U Ft:.H =1.0+--

100.0 where:

Ut,.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, UFQ, to be applied to the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated by the following formula:

U FQ =(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_1ulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT...

NUMBER COLR 1 REVISION 9 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 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)

3.

TABLES 2.10.1 Pressurizer pressure is greater than or equal to 217 5 psi g.

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.

3.1 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 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-15-40, "Unit 1 Cycle 20 Final Reload Evaluation," August 2015 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_lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1

7.

ANALYTICALMETHODS NUMBER COLR 1 REVISION 9 PAGE 7 OF 14 UNIT 1

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 lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY

.DIABLO CANYON POWER PLANT.

TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 9 PAGE -

8 OF 14 UNIT 1

Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Bum up inFQ Margin (MWD/MTU) 4048 2.00 4210 2.19 4373 2.67 4535 3.13 4698 3.56 4860 3.95 5022 3.86 5185 3.72 5347 3.52 5510 3.38 5672 3.23 5834 3.08 5997 2.91 6159 2.74 6322 2.57 6484 2.38 6647 2.17 6809 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_lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 9 PAGE 9 OF 14 UNIT 1

Table 2A: Load Follow W(Z) Factors at 150 and 3000 MWD/MTU as a Function of Core Height HEIGHT 150MWD/MTU HEIGHT 3000 MWD/MTU (INCHES)

W(Z)

(INCHES)

W(Z)

  • 0.0 1.5037
  • 0.0 1.5483
  • 2.4 1.4991
  • 2.4 1.5436
  • 4.8 1.4911
  • 4.8 1.5351
  • 7.2 1.4809
  • 7.2 1.5241
  • 9.6 1.4685
  • 9.6 1.5106 12.1 1.4525 12.1 1.4932 14.5 1.4345 14.5 1.4736 16.9 1.4148 16.9 1.4517 19.3 1.3941 19.3 1.4279 21.7 1.3729 21.7 1.4025 24.1 1.3511 24.1 1.3759 26.5 1.3285 26.5 1.3484 28.9 1.3057 28.9 1.3204 31.4 1.2814 31.4 1.2908 33.8 1.2576 33.8 1.2616 36.2 1.2432 36.2 1.2386 38.6 1.2351 38.6 1.2235 41.0 1.2260 41.0 1.2151 43.4 1.2174 43.4 1.2130 45.8 1.2076 45.8 1.2100 48.2 1.2022 48.2 1.2055 50.8 1.1992 50.8 1.1998 53.2 1.1942 53.2 1.1934 55.6 1.1885 55.6 1.1859 58.0 1.1819 58.0 1.1776 60.4 1.1742 60.4 1.1683 62.8 1.1662 62.8 1.1587 65.2 1.1567 65.2 1.1477 67.6 1.1475 67.6 1.1358 70.1 1.1561 70.1 1.1375
  • Top and Bottom 8% Excluded COLR_lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY

  • DUBLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 9 PAGE 10 OF 14 UNIT 1

Table 2A: Load Follow W(Z) Factors at 150 and 3000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 150MWD/MTU HEIGHT 3000 MWD/MTU (INCHES)

W(Z)

(INCHES)

W(Z) 72.5 1.1678 72.5 1.1467 74.9 1.1763 74.9 1.1566 77.3 1.1844 77.3 1.1656 79.7 1.1911 79.7 1.1734 82.1 1.1963 82.1 1.1799 84.5 1.1999 84.5 1.1849 86.9 1.2019 86.9 1.1885 89.3 1.2024 89.3 1.1906 91.8 1.2005 91.8 1.1907 94.2 1.1964 94.2 1.1886 96.6 1.1898 96.6 1.1842 99.0 1.1804 99.0 1.1773 101.4 1.1688 101.4 1.1680 103.8 1.1580 103.8 1.1589 106.2 1.1521 106.2 1.1574 108.6 1.1547 108.6 1.1611 111.1 1.1595 111.1 1.1753 113.5 1.1618 113.5 1.1954 115.9 1.1717 115.9 1.2165 118.3 1.1978 118.3 1.2371 120.7 1.2270 120.7 1.2525 123.1 1.2527 123.1 1.2642 125.5 1.2760 125.5 1.2776 127.9 1.2966 127.9 1.2901 130.4 1.3167 130.4 1.2868 132.8 1.3281 132.8 1.2854

  • 135.2 1.3389
  • 135.2 1.2879
  • 137.6 1.3514
  • 137.6 1.2839
  • 140.0 1.3527
  • 140.0 1.2720
  • 142.4 1.3467
  • 142.4 1.2544
  • 144.8 1.3450
  • 144.8 1.2401
  • Top and Bottom 8% Excluded COLR_1u1r09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION PAGE 11 OF 14

  • UNIT 1

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 1.3131
  • 0.0 1.3736
  • 2.4 1.3036
  • 2.4 1.3583
  • 4.8 1.2928
  • 4.8 1.3422
  • 7.2 1.2812
  • 7.2 1.3257
  • 9.6 1.2688
  • 9.6 1.3089 12.1 1.2544 12.1 1.2896 14.5 1.2369 14.5 1.2692 16.9 1.2189 16.9 1.2502 19.3 1.2077 19.3 1.2365 21.7 1.1980 21.7 1.2227 24.1 1.1879 24.1 1.2092 26.5 1.1781 26.5 1.1964 28.9 1.1679 28.9 1.1843 31.4 1.1571 31.4 1.1737 33.8 1.1520 33.8 1.1656 36.2 1.1498 36.2 1.1562 38.6 1.1490 38.6 1.1562 41.0 1.1499 41.0 1.1709 43.4 1.1580 43.4 1.1872 45.8 1.1662 45.8 1.2022 48.2 1.1732 48.2 1.2154 50.8 1.1795 50.8 1.2274 53.2 1.1842 53.2 1.2366 55.6 1.1876 55.6 1.2437 58.0 1.1896 58.0 1.2494 60.4 1.1906 60.4 1.2513 62.8 1.1893 62.8 1.2591 65.2 1.1884 65.2 1.2856 67.6 1.1951 67.6 1.3081 70.1 1.2093 70.1 1.3289
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PACIFIC GAS AND ELECTRIC COMPANY DUffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 9 PAGE 12 OF 14 UNIT 1

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) 72.5 1.2228 72.5 1.3463 74.9 1.2339 74.9 1.3607 77.3 1.2434 77.3 1.3722 79.7 1.2510 79.7 1.3805 82.1 1.2565 82.1 1.3855 84.5 1.2601 84.5 1.3873 86.9 1.2646 86.9 1.3858 89.3 1.2702 89.3 1.3805 91.8 1.2729 91.8 1.3704 94.2 1.2730 94.2 1.3566 96.6 1.2704 96.6 1.3385 99.0 1.2654 99.0 1.3161 101.4 1.2574 101.4 1.2898 103.8 1.2467 103.8 1.2649 106.2 1.2435 106.2 1.2552 108.6 1.2497 108.6 1.2522 111.1 1.2721 111.1 1.2461 113.5 1.2973 113.5 1.2478 115.9 1.3200 115.9 1.2715 118.3 1.3410 118.3 1.2947 120.7 1.3600 120.7 1.3154 123.1 1.3781 123.1 1.3357 125.5 1.3963 125.5 1.3548 127.9 1.4111 127.9 1.3732 130.4 1.4181 130.4 1.3918 132.8 1.4195 132.8 1.4028

  • 135.2 1.4201
  • 135.2 1.4093
  • 137.6 1.4162
  • 137.6 1.4100
  • 140.0 1.3988
  • 140.0 1.3950
  • 142.4 1.3724
  • 142.4 1.3695
  • 144.8 1.3512
  • 144.8 1.3502
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PACIFIC GAS AND ELECTRIC COMPANY DlirnLOCANYONPO~RPLANT NUMBER REVISION PAGE COLR1 9

13 OF 14 TITLE:

  • COLR for Diablo Canyon Unit 1 UNIT 1

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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 lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DUillLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Pnit 1 120 I (-14, 100) 1

(+1o, 1oo) I NUMBER COLR 1 REVISION 9 PAGE 14 OF 14 UNIT 1

~UNACCEPTABLE I I UNACCEPTABLE

~

\\

OPERATION OPERATION 100 I

\\

I I

\\

80 I..

Q) s:

0

0.

(U E

I..

Q)

.c 60 1-

"'C

~

\\

I

\\

ACCEPTABLE I

I OPERATION I \\

I l

I 1\\

I

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+J cu

~

I 0

I ( -3o,5o) 1(+25,50)1

~

0 40 20 0

-60

-50

-40

-30

-20

-10 0

1 0 20 30 40 50 60 Flux Difference (DELTA I)%

Figure 2: AFD Limits as a Function of Rated Thermal Power COLR_1ulr09.DOC 04B 1016.0502

Pacific Gas and Electric Company December 1, 2015 PG&E Letter DCL-15-144 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 20

Dear Commissioners and Staff:

Jan A. 1\\limidl Station Director Diablo Canyon Power Plant Mail Code 104/5/502 P. 0. Box 56 Avila Beach, CA 93424 805.545.6783 Internal: 691.6783 Fax: 805.545.4234 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 20.

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.

MEM6/4539/6007 4189-360 Enclosure cc:

Diablo Distribution cc/enc: Marc L. Dapas, NRC Region IV Thomas R. Hipschman, NRC Senior Resident Inspector Siva P. Lingam, NRC Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

Enclosure PG&E Letter DCL-15-144 CORE OPERATING LIMITS REPORT DIABLO CANYON POWER PLANT UNIT 1 CYCLE 20 EFFECTIVE DATE October 21, 2015

      • ISSUED FOR USE BY: _________ DATE: _____ EXPIRES: _____ ***

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

COLR for Diablo Canyon Unit 1 CLASSIFICATION: QUALITYRELATED

1.

CORE OPERATING LIMITS REPORT NUMBER COLR 1 REVISION 9

PAGE 1 OF 14 UNIT 1

10/21/15 EFFECTIVE DATE 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 20 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 3.1.3

  • 3.1.4
  • 3.1.5 3.1.6 3.1.8 3.2.1

Moderator Temperature Coefficient Rod Group Alignment Limits Shutdown Bank Insertion Limits Control Bank Insertion Limits PHYSICS TESTING Exceptions -MODE 2 Heat Flux Hot Channel Factor-FQ(Z)

Nuclear Enthalpy Rise Hot Channel Factor - F ~

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_1u1r09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1

2.

OPERATING LIMITS NUMBER COLR 1 REVISION 9 PAGE 2 OF 14 UNIT 1

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 1.6% i1klk. This limit addresses the concerns ofNSAL-02-014 (Reference 6.3) and the boron dilution analysis for RCS filled conditions.

In order to address RCS drained conditions for the boron dilution analysis, the minimum refueling boron concentration of 2000 ppm (Section 2.9.2) shall be maintained whenever -the RCS level is at or below the reactor vessel flange elevation (114 feet).

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 L1klki°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 L1k/k/°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_1u1r09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DUillLOCANYONPO~RPLANT NUMBER COLR 1 REVISION 9 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) pRTP 2.5.1 FQ(Z)<-Q-*K(Z) for P> 0.5 p

pRTP FQ(Z)<-Q-*K(Z) for P~ 0.5

0.5 where

P F~TP = 2.58 K(Z) = 1.0 THERMAL POWER RATED THERMAL POWER 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 burnups through the end of full power reactivity plus a power coast down of up to 1000 MWD/MTU.

COLR_1ulr09.DOC 04B 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 burnup 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 burnup steps can be used. If data are listed for only 2 burnup 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 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.

1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT NUMBER COLR 1 REVISION.9 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-8 (Z) and F ~ (Z) satisfy th~ following:

COLR_lulr09.DOC 04B

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)

F C (Z) < Q for P > 0.5 Q

p pRTP *K(Z)

Fc(Z)::; Q forP:-:;0.5 Q

0.5 W

pRTP F

(Z) <-Q-*K(Z)

Q p

forP>0.5 pRTP F WQ (Z) ::;-Q-*K(Z) for P :-:; 0.5

0.5 where

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

FRTP is the F limit Q

Q 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, F 8 (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.

1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 2.6 Nuclear Enthalpy Rise Hot Channel Factor_- F ~H (TS 3.2.2)

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

~H-

~H where:

THERMAL POWER p

RATED THERMAL POWER NUMBER COLR 1 REVISION 9 PAGE 5 OF 14 UNIT 1

F ~H

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

F ~~P

= 1.586 (prior to including 4% uncertainty)

PF Llli

= 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, UFLlli, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F ~H, shall be calculated by the following formula:

utili U Ft:.H =1.0+--

100.0 where:

Ut,.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, UFQ, to be applied to the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated by the following formula:

U FQ =(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_1ulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT...

NUMBER COLR 1 REVISION 9 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 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)

3.

TABLES 2.10.1 Pressurizer pressure is greater than or equal to 217 5 psi g.

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.

3.1 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 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-15-40, "Unit 1 Cycle 20 Final Reload Evaluation," August 2015 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_lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1

7.

ANALYTICALMETHODS NUMBER COLR 1 REVISION 9 PAGE 7 OF 14 UNIT 1

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 lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY

.DIABLO CANYON POWER PLANT.

TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 9 PAGE -

8 OF 14 UNIT 1

Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Bum up inFQ Margin (MWD/MTU) 4048 2.00 4210 2.19 4373 2.67 4535 3.13 4698 3.56 4860 3.95 5022 3.86 5185 3.72 5347 3.52 5510 3.38 5672 3.23 5834 3.08 5997 2.91 6159 2.74 6322 2.57 6484 2.38 6647 2.17 6809 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_lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 9 PAGE 9 OF 14 UNIT 1

Table 2A: Load Follow W(Z) Factors at 150 and 3000 MWD/MTU as a Function of Core Height HEIGHT 150MWD/MTU HEIGHT 3000 MWD/MTU (INCHES)

W(Z)

(INCHES)

W(Z)

  • 0.0 1.5037
  • 0.0 1.5483
  • 2.4 1.4991
  • 2.4 1.5436
  • 4.8 1.4911
  • 4.8 1.5351
  • 7.2 1.4809
  • 7.2 1.5241
  • 9.6 1.4685
  • 9.6 1.5106 12.1 1.4525 12.1 1.4932 14.5 1.4345 14.5 1.4736 16.9 1.4148 16.9 1.4517 19.3 1.3941 19.3 1.4279 21.7 1.3729 21.7 1.4025 24.1 1.3511 24.1 1.3759 26.5 1.3285 26.5 1.3484 28.9 1.3057 28.9 1.3204 31.4 1.2814 31.4 1.2908 33.8 1.2576 33.8 1.2616 36.2 1.2432 36.2 1.2386 38.6 1.2351 38.6 1.2235 41.0 1.2260 41.0 1.2151 43.4 1.2174 43.4 1.2130 45.8 1.2076 45.8 1.2100 48.2 1.2022 48.2 1.2055 50.8 1.1992 50.8 1.1998 53.2 1.1942 53.2 1.1934 55.6 1.1885 55.6 1.1859 58.0 1.1819 58.0 1.1776 60.4 1.1742 60.4 1.1683 62.8 1.1662 62.8 1.1587 65.2 1.1567 65.2 1.1477 67.6 1.1475 67.6 1.1358 70.1 1.1561 70.1 1.1375
  • Top and Bottom 8% Excluded COLR_lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY

  • DUBLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 9 PAGE 10 OF 14 UNIT 1

Table 2A: Load Follow W(Z) Factors at 150 and 3000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 150MWD/MTU HEIGHT 3000 MWD/MTU (INCHES)

W(Z)

(INCHES)

W(Z) 72.5 1.1678 72.5 1.1467 74.9 1.1763 74.9 1.1566 77.3 1.1844 77.3 1.1656 79.7 1.1911 79.7 1.1734 82.1 1.1963 82.1 1.1799 84.5 1.1999 84.5 1.1849 86.9 1.2019 86.9 1.1885 89.3 1.2024 89.3 1.1906 91.8 1.2005 91.8 1.1907 94.2 1.1964 94.2 1.1886 96.6 1.1898 96.6 1.1842 99.0 1.1804 99.0 1.1773 101.4 1.1688 101.4 1.1680 103.8 1.1580 103.8 1.1589 106.2 1.1521 106.2 1.1574 108.6 1.1547 108.6 1.1611 111.1 1.1595 111.1 1.1753 113.5 1.1618 113.5 1.1954 115.9 1.1717 115.9 1.2165 118.3 1.1978 118.3 1.2371 120.7 1.2270 120.7 1.2525 123.1 1.2527 123.1 1.2642 125.5 1.2760 125.5 1.2776 127.9 1.2966 127.9 1.2901 130.4 1.3167 130.4 1.2868 132.8 1.3281 132.8 1.2854

  • 135.2 1.3389
  • 135.2 1.2879
  • 137.6 1.3514
  • 137.6 1.2839
  • 140.0 1.3527
  • 140.0 1.2720
  • 142.4 1.3467
  • 142.4 1.2544
  • 144.8 1.3450
  • 144.8 1.2401
  • Top and Bottom 8% Excluded COLR_1u1r09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DliffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION PAGE 11 OF 14

  • UNIT 1

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 1.3131
  • 0.0 1.3736
  • 2.4 1.3036
  • 2.4 1.3583
  • 4.8 1.2928
  • 4.8 1.3422
  • 7.2 1.2812
  • 7.2 1.3257
  • 9.6 1.2688
  • 9.6 1.3089 12.1 1.2544 12.1 1.2896 14.5 1.2369 14.5 1.2692 16.9 1.2189 16.9 1.2502 19.3 1.2077 19.3 1.2365 21.7 1.1980 21.7 1.2227 24.1 1.1879 24.1 1.2092 26.5 1.1781 26.5 1.1964 28.9 1.1679 28.9 1.1843 31.4 1.1571 31.4 1.1737 33.8 1.1520 33.8 1.1656 36.2 1.1498 36.2 1.1562 38.6 1.1490 38.6 1.1562 41.0 1.1499 41.0 1.1709 43.4 1.1580 43.4 1.1872 45.8 1.1662 45.8 1.2022 48.2 1.1732 48.2 1.2154 50.8 1.1795 50.8 1.2274 53.2 1.1842 53.2 1.2366 55.6 1.1876 55.6 1.2437 58.0 1.1896 58.0 1.2494 60.4 1.1906 60.4 1.2513 62.8 1.1893 62.8 1.2591 65.2 1.1884 65.2 1.2856 67.6 1.1951 67.6 1.3081 70.1 1.2093 70.1 1.3289
  • Top and Bottom 8% Excluded COLR 1ulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DUffiLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Unit 1 NUMBER COLR 1 REVISION 9 PAGE 12 OF 14 UNIT 1

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) 72.5 1.2228 72.5 1.3463 74.9 1.2339 74.9 1.3607 77.3 1.2434 77.3 1.3722 79.7 1.2510 79.7 1.3805 82.1 1.2565 82.1 1.3855 84.5 1.2601 84.5 1.3873 86.9 1.2646 86.9 1.3858 89.3 1.2702 89.3 1.3805 91.8 1.2729 91.8 1.3704 94.2 1.2730 94.2 1.3566 96.6 1.2704 96.6 1.3385 99.0 1.2654 99.0 1.3161 101.4 1.2574 101.4 1.2898 103.8 1.2467 103.8 1.2649 106.2 1.2435 106.2 1.2552 108.6 1.2497 108.6 1.2522 111.1 1.2721 111.1 1.2461 113.5 1.2973 113.5 1.2478 115.9 1.3200 115.9 1.2715 118.3 1.3410 118.3 1.2947 120.7 1.3600 120.7 1.3154 123.1 1.3781 123.1 1.3357 125.5 1.3963 125.5 1.3548 127.9 1.4111 127.9 1.3732 130.4 1.4181 130.4 1.3918 132.8 1.4195 132.8 1.4028

  • 135.2 1.4201
  • 135.2 1.4093
  • 137.6 1.4162
  • 137.6 1.4100
  • 140.0 1.3988
  • 140.0 1.3950
  • 142.4 1.3724
  • 142.4 1.3695
  • 144.8 1.3512
  • 144.8 1.3502
  • Top and Bottom 8% Excluded COLR 1ulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DlirnLOCANYONPO~RPLANT NUMBER REVISION PAGE COLR1 9

13 OF 14 TITLE:

  • COLR for Diablo Canyon Unit 1 UNIT 1

225 200 175 g 100 E

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cu al 50 25 0

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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 lulr09.DOC 04B 1016.0502

PACIFIC GAS AND ELECTRIC COMPANY DUillLOCANYONPO~RPLANT TITLE:

COLR for Diablo Canyon Pnit 1 120 I (-14, 100) 1

(+1o, 1oo) I NUMBER COLR 1 REVISION 9 PAGE 14 OF 14 UNIT 1

~UNACCEPTABLE I I UNACCEPTABLE

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OPERATION OPERATION 100 I

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1 0 20 30 40 50 60 Flux Difference (DELTA I)%

Figure 2: AFD Limits as a Function of Rated Thermal Power COLR_1ulr09.DOC 04B 1016.0502

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