DCL-20-001, Core Operating Limits Report for Unit 2 Cycle 22

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Core Operating Limits Report for Unit 2 Cycle 22
ML20006E556
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 01/06/2020
From: Gerfen P
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-20-001
Download: ML20006E556 (18)
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Text

Pacific Gas and Electric Company$

Paula Gerfen Diablo Canyon Power Plant Site Vice President Mail code 104/6/605 P.O. Box 56 Avila Beach, CA 93424 805.545.4596 Internal: 691.4596 Fax: 805.545.4234 January 6, 2020 PG&E Letter DCL-20-001 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 22

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 DCPP Unit 2, Cycle 22.

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. Shannon Conner at (805) 545-6171.

SinT6~~~

Paula Gerten 0 rntU4231 /50943730-04 Enclosure cc: Diablo Distribution cc/enc: Scott A. Morris, NRC Region IV Administrator Christopher W. Newport, NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager A member of the STARS Alliance Callaway

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

Enclosure PG&E Letter DCL-20-001 DIABLO CANYON POWER PLANT CORE OPERATING LIMITS REPORT UNIT 2 CYCLE 22 EFFECTIVE DATE October 10, 2019

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR2 NUCLEAR POWER GENERATION REVISION 12 DIABLOCANYONPOWERPLANT PAGE 1 OF 16 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 2 2

10/10/19 EFFECTIVE DATE CLASSIFICATION: QUALITYRELATED

1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 2 Cycle 22 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 - F0 (Z)
  • 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor - FrH
  • 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_2u2rl2.DOC 04B 0924.0905

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 2 OF 16 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% Lik/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% Lik/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 1.6% ~k/k. 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, a minimum boron concentration of 1800 ppm 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 -3.9xl0- 4 Lik/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 -3.0xl0-4 Lik/k/°F (all rods withdrawn, RATED THERMAL POWER condition).

2.2.3 The MTC 60 ppm surveillance limit is -3.72x10-4 Lik/k/°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.

2.4.2 The control banks shall be withdrawn and inserted in the prescribed sequence, in accordance with plant operating procedures. For example for withdrawal, the sequence is control bank A, control bank B, control bank C, and control bank D. The insertion sequence is the reverse of the withdrawal sequence.

2.4.3 A 128 step tip-to-tip relationship between each sequential control bank shall be maintained.

COLR 2u2rl2.DOC 04B 0924.0905

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 12 PAGE 3 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 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 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, 2B, and 2C 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 950 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 1/P (P > 0.5) or 1/0.5 (P :S 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 Ft (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 2u2r12.DOC 04B 0924.0905

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 4 OF 16 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 1{_ (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:

pRTP *K(Z)

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

F (Z) ~ Q forPs0.5 Q 0.5 W pRTP F (Z) <-Q-*K(Z) for P > 0.5 Q p pRTP F WQ (Z) s -Q-*K(Z) for P s 0.5

0.5 where

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

FQRTP is the F Q limit K(Z) is the normalized F Q(Z) as a function of core height P is the relative THERMAL POWER, and F 1{_ (Z) is the total peaking factor, F 8(Z), multiplied by W(Z) which gives the maximum FQ(Z) calculated to occur in nmmal 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_2u2r1 2.DOC 04B 0924.0905

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 12 PAGE 5 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.6 Nuclear Enthalpy Rise Hot Channel Factor - FrH (TS 3.2.2)

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

~H - ~H where:

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

= 1.586 (prior to including 4% uncertainty)

PFC'..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, UMH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F rH, shall be calculated by the following Uw formula: U FAfl =l. 0 + - -

100. 0 where: Uf1H = 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~ip = 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 rH, 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 2u2r12.DOC 04B 0924.0905

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 6 OF 16 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 ofthe 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, Temperature, and Flow 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.

2.10.3 RCS total flow rate is greater than or equal to 362,500 gpm.

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 of 2% Per 31 EFPD" 3.2 Table 2A, "Load Follow W(Z) Factors at 150 and 2000 MWD/MTU as a Function of Core Height" 3.3 Table 2B, "Load Follow W(Z) Factors at 6000 and 10000 MWD/MTU as a Function of Core Height" 3.4 Table 2C, "Load Follow W(Z) Factors at 14000 and 18000 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-19-063, "Diablo Canyon Unit 2 Cycle 22 Final Reload Evaluation and Core Operating Limits Report," July 2019.

6.2 WCAP-12472-P-A (Proprietary), Addendum 4, Revision 0, "BEACON Core Monitoring and Operations Support System, Addendum 4," September 2012.

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_2u2r12.DOC 04B 0924.0905

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 7 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2

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-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-16009-P-A, Revision 0, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005.

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

7.9 WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004.

7.10 WCAP-16045-P-A, Addendum 1-A, "Qualification of the NEXUS Nuclear Data Methodology," August 2007.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 8 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 1: FQ Margin Decreases in Excess of2% Per 31 EFPD CycleBumup Max. % Decrease (MWD/MTU) in F 0 Margin 5467 2.00 5671 2.45 5876 3.02 6080 3.16 6285 3.01 6489 2.58 6693 2.43 6898 2.27 7102 2.12 7307 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_2u2rl2.DOC 04B 0924.0905

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 9 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 2000 MWD/MTU as a Function of Core Height HEIGHT 150MWD/MTU HEIGHT 2000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.5877 *0.0 1.6279
  • 2.4 1.5802 *2.4 1.6203
  • 4.8 1.5720 *4.8 1.6119
  • 7.2 1.5614 *7.2 1.6011
  • 9.6 1.5458 *9.6 1.5847 12.1 1.5252 12.1 1.5629 14.5 1.5031 14.5 1.5393 16.9 1.4787 16.9 1.5132 19.3 1.4524 19.3 1.4849 21.7 1.4245 21.7 1.4547 24.1 1.3948 24.1 1.4228 26 .5 1.3646 26.5 1.3903 28.9 1.3341 28.9 1.3573 31.4 1.3018 31.4 1.3234 33.8 1.2734 33.8 1.2900 36.2 1.2584 36.2 1.2644 38.6 1.2497 38.6 1.2550 41.0 1.2397 41.0 1.2472 43.4 1.2315 43.4 1.2399 45 .8 1.2244 45.8 1.2313 48.2 1.2162 48.2 1.2218 50.8 1.2068 50.8 1.2109 53.2 1.1969 53.2 1.1998 55.6 1.1860 55.6 1.1876 58 .0 1.1743 58.0 1.1746 60.4 1.1622 60.4 1.1619 62.8 1.1497 62.8 1.1468 65.2 1.1438 65.2 1.1334 67.6
  • 1.1567 67.6 1.1382 70.0 1.1679 70.0 1.1453
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 10 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 2000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 150 MWD/MTU HEIGHT 2000MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.5 1.1787 72.5 1.1525 74.9 1.1876 74.9 1.1584 77.3 1.1954 77.3 1.1633 79.7 1.2020 79.7 1.1673 82.1 1.2076 82.1 1.1705 84.5 1.2111 84.5 1.1720 86.9 1.2131 86.9 1.1723 89.3 1.2132 89.3 1.1715 91.8 1.2105 91.8 1.1686 94.2 1.2063 94.2 1.1646 96.6 1.1991 96.6 1.1583 99.0 1.1897 99.0 1.1502 101.4 1.1781 101.4 1.1403 103.8 1.1661 103.8 1.1319 106.2 1.1518 106.2 1.1341 108.6 1.1462 108.6 1.1398 111.1 1.1442 111.1 1.1413 113.5 1.1448 113.5 1.1441 115.9 1.1421 115.9 1.1438 118.3 1.1359 118.3 1.1409 120.7 1.1317 120.7 1.1353 123.1 1.1376 123.1 1.1368 125.5 1.1434 125 .5 1.1397 127.9 1.1488 127.9 1.1415 130.3 1.1542 130.3 1.1467 132.8 1.1583 132.8 1.1503

  • 135.2 1.1611 *135.2 1.1533
  • 137.6 1.1621 *137.6 1.1507
  • 140.0 1.1592 *140.0 1.1395
  • 142.4 1.1534 *142.4 1.1294
  • 144.8 1.1485 *144.8 1.1190
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR2 DIABLO CANYON POWER PLANT REVISION 12 PAGE 11 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 6000 and 10000 MWD/MTU as a Function of Core Height HEIGHT 6000 MWD/MTU HEIGHT 10000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.4579 *0.0 1.3226
  • 2.4 1.4533 *2.4 1.3206
  • 4.8 1.4475 *4.8 1.3167
  • 7.2 1.4409 *7.2 1.3136
  • 9.6 1.4295 *9.6 1.3063 12.1 1.4133 12.1 1.2951 14.5 1.3959 14.5 1.2835 16.9 1.3766 16.9 1.2710 19.3 1.3558 19.3 1.2578 21.7 1.3339 21.7 1.2444 24.1 1.3109 24.1 1.2308 26.5 1.2874 26.5 1.2168 28.9 1.2631 28.9 1.2015 31.4 1.2377 31.4 1.1857 33 .8 1.2155 33.8 1.1704 36.2 1.2032 36.2 1.1561 38.6 1.1967 38.6 1.1512 41.0 1.1909 41.0 1.1536 43.4 1.1852 43.4 1.1588 45.8 1.1797 45.8 1.1638 48.2 1.1728 48 .2 1.1674 50.8 1.1647 50.8 1.1691 53.2 1.1578 53.2 1.1698 55.6 1.1519 55.6 1.1694 58.0 1.1454 58.0 1.1678 60.4 1.1388 60.4 1.1658 62.8 1.1301 62.8 1.1614 65.2 1.1244 65.2 1.1608 67.6 1.1388 67.6 1.1813 70.0 1.1513 70.0 1.1988
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 12 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 6000 and 10000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 6000 MWD/MTU HEIGHT 10000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.5 1.1635 72.5 1.2156 74.9 1.1742 74.9 1.2304 77.3 1.1841 77.3 1.2439 79.7 1.1928 79.7 1.2554 82.1 1.2002 82.1 1.2650 84.5 1.2060 84.5 1.2725 86.9 1.2107 86.9 1.2786 89.3 1.2140 89.3 1.2825 91 .8 1.2143 91.8 1.2824 94.2 1.2132 94.2 1.2805 96 .6 1.2097 96.6 1.2757 99.0 1.2041 99.0 1.2686 101.4 1.1963 101.4 1.2586 103.8 1.1865 103.8 1.2455 106.2 1.1874 106.2 1.2367 108.6 1.1935 108.6 1.2295 111.1 1.1947 111.1 1.2289 113.5 1.1955 113.5 1.2308 115.9 1.1937 115.9 1.2314 118.3 1.1900 118.3 1.2302 120.7 1.1922 120.7 1.2290 123.1 1.1978 123.1 1.2358 125.5 1.2020 125.5 1.2428 127.9 1.2052 127.9 1.2498 130.3 1.2102 130.3 1.2562 132.8 1.2125 132.8 1.2606

  • 135.2 1.2149 *135.2 1.2637
  • 137.6 1.2100 *137.6 1.2648
  • 140.0 1.1973 *140.0 1.2610
  • 142.4 1.1922 *142.4 1.2538
  • 144.8 1.1846 *144.8 1.2478
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 13 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2C: Load Follow W(Z) Factors at 14000 and 18000 MWD/MTU as a Function of Core Height HEIGHT 14000 MWD/MTU HEIGHT 18000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.2854 *0.0 1.3195
  • 2.4 1.2842 *2.4 1.3178
  • 4.8 1.2797 *4.8 1.3110
  • 7.2 1.2768 *7.2 1.3061
  • 9.6 1.2698 *9.6 1.2965 12.1 1.2588 12.1 1.2827 14.5 1.2480 14.5 1.2693 16.9 1.2367 16.9 1.2553 19.3 1.2250 19.3 1.2411 21.7 1.2137 21.7 1.2274 24.1 1.2027 24.1 1.2142 26.5 1.1912 26.5 1.2004 28.9 1.1782 28.9 1.1867 31.4 1.1642 31.4 1.1748 33.8 1.1554 33.8 1.1641 36.2 1.1560 36.2 1.1528 38.6 1.1622 38.6 1.1505 41.0 1.1672 41.0 1.1649 43.4 1.1715 43.4 1.1794 45.8 1.1759 45.8 1.1935 48.2 1.1824 48.2 1.2051 50.8 1.1891 50.8 1.2137 53.2 1.1937 53.2 1.2201 55.6 1.1970 55.6 1.2250 58.0 1.1990 58.0 1.2281 60.4 1.1989 60.4 1.2295 62.8 1.1996 62.8 1.2301 65.2 1.2084 65.2 1.2325 67.6 1.2290 67.6 1.2500 70.0 1.2453 70.0 1.2630
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 14 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2C: Load Follow W(Z) Factors at 14000 and 18000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 14000 MWD/MTU HEIGHT 18000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.5 1.2606 72.5 1.2747 74.9 1.2735 74.9 1.2845 77.3 1.2847 77.3 1.2925 79.7 1.2932 79.7 1.2978 82.1 1.2994 82.1 1.3007 84.5 1.3032 84.5 1.3015 86.9 1.3053 86.9 1.3009 89.3 1.3049 89.3 1.2974 91.8 1.2994 91.8 1.2883 94.2 1.2923 94.2 1.2779 96.6 1.2823 96.6 1.2647 99.0 1.2697 99.0 1.2487 101.4 1.2547 101.4 1.2308 103.8 1.2420 103.8 1.2264 106.2 1.2361 106.2 1.2259 108.6 1.2315 108.6 1.2229 111.1 1.2201 111.1 1.2137 113.5 1.2134 113.5 1.2067 115.9 1.2098 115.9 1.1977 118.3 1.2055 118.3 1.1899 120.7 1.2080 120.7 1.1847 123.1 1.2136 123.1 1.1906 125.5 1.2193 125.5 1.1975 127.9 1.2255 127.9 1.2108 130.3 1.2313 130.3 1.2294 132.8 1.2351 132.8 1.2443

  • 135.2 1.2381 *135.2 1.2493
  • 137.6 1.2392 *137.6 1.2541
  • 140.0 1.2355 *140.0 1.2478
  • 142.4 1.2283 *142.4 1.2407
  • 144.8 1.2223 *144.8 1.2339
  • Top and Bottom 8% Excluded COLR 2u2rl2.DOC 04B 0924.0905

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 12 PAGE 15 OF 16 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_2u2r12. DOC 04 B 0924.0905

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 12 PAGE 16 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 120 I (-14,100) I I (+ 1o, 1oo) I 100 -

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Figure 2: AFD Limits as a Function of Rated Thermal Power COLR 2u2rl2.DOC 04B 0924.0905

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