DCL-18-021, Core Operating Limits Report for Unit 2 Cycle 21

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Core Operating Limits Report for Unit 2 Cycle 21
ML18081B175
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 03/22/2018
From: Nimick J
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-18-021
Download: ML18081B175 (18)
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Text

Pacific Gas and Electric Company*

Jan A. Nimick Diablo Canyon Power Plant Senior Director Mail code 104/6/605 Nuclear Services P.O. Box 56 Avila Beach, CA 93424 805.545.6783 Internal: 691.4596 Fax: 805.545.4234 March 22, 2018 PG&E Letter DCL-18-021 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 21

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 21.

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 Connor at (805) 545-6171.

armb/4743 Enclosure cc: Diablo Distribution cc/enc: Kriss M. Kennedy, NRC Region IV Administrator Christopher W . Newport, NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager A me mber of the STARS Allianc e Call aw ay

  • Di ablo Canyon
  • Pal o Ve rd e
  • Wolf Creek

Enclosure PG&E Letter DCL-18-021 DIABLO CANYON POWER PLANT CORE OPERATING LIMITS REPORT UNIT 2 CYCLE 21 EFFECTIVE DATE March 9, 2018

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 NUCLEAR POWER GENERATION REVISION 11 DUBLOCANYONPOWERPLANT PAGE 1 OF 16 CORE OPERATING LIMITS REPORT UNIT 2

TITLE: COLR for Diablo Canyon Unit 2 03/09/18 EFFECTIVE DATE CLASSIFICATION: QUALITY RELATED

1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 2 Cycle 21 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 2u2rll.DOC 04B 0307.0654

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DliillLOCANYONPOWERPLANT REVISION 11 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% t.klk.

2.1.2 In Modes 3 or 4 the shutdown margin with Safety Injection blocked shall be greater than or equal to 1.6% b.k/k calculated at a temperature of200°F.

The SDM linlit for MODE 5 is:

2.1.3 The shutdown margin shall be greater than or equal to 1.6% Llk/k. Tills 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)

TheMTC limit for MODES 1, 2, and 3 is:

2.2.1 The MTC shall be less negative than -3.9x10- 4 t.k/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 b.klki°F (all rods withdrawn, RATED THERMAL POWER condition).

2.2.3 The MTC 60 ppm surveillance limit is -3.72x1 o* 4 b.klki°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 2u2rll.DOC 04B 0307.0654

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR2 DIABLO CANYON POWER PLANT REVISION 11 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) 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, 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 1200 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 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 burnups that are outside the range of Table 1.

COLR 2u2rll.DOC 04B 0307.0654

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 11 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 g (Z) and F i{ (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 for P :::;; 0.5 C2 0.5 W pRTP F (Z) <-Q-*K(Z) forP > 0.5 C2 p F d pRTP (Z) :::;; -Q-*K(Z) for P:::;; 0.5

0.5 where

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

F RTP is the F limit Q Q K(Z) is the normalized FQ(Z) as a function of core height P is the relative THERMAL POWER, and F ~ (Z) is the total peaking factor, F g(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 2u2rll.DOC 04B 0307.0654

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 11 PAGE 5 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.6 Nuclear Enthalpy Rise Hot Channel Factor- F~ (TS 3.2.2)

F~H : : : F~ft *[1 + PF,m * (1-P)]

where:

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

F!Ji = 1.586 (prior to including 4% unce1tainty)

PFLIH = 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 ~H, shall be calculated by the following ub.H formula: U FMI =1. 0+--

100.0 where: ULIH =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!ff = 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 _(1.0+ UQ ) *u c 1_ 100.0 where: UQ = Uncertainty for power peaking factor as defined in equation (5-19) in Reference 6.2.

Uc = 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.

Ifthe PDMS is INOPERABLE, the Heat Flux Hot Cham1el Factor, FQ(Z), shall be calculated as specified in Section 2.5 .

CO LR 2u2rll.DOC 04B 0307.0654

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 11 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 of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the more restrictive of the following lin1its:

2.9.1 A ketr of0.95 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 of2% Per 31 EFPD" 3.2 Table 2A, "Load Follow W(Z) Factors at 150 and 3000 MWD/MTU as a Function of Core Height" 3.3 Table 2B, "Load Follow W(Z) Factors at 8000 and 12000 MWD/MTU as a Function of Core Height" 3.4 Table 2C, "Load Follow W(Z) Factors at 16000 and 20000 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 ofRated Thermal Power"
5. RECORDS None
6. REFERENCES 6.1 NF-PGE-17-85, "Diablo Canyon Unit 2 Cycle 21 Final Reload Evaluation and Core Operating Limits Report," December 2017.

6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Suppmi 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.

rnrH ?n?rll .DOC 04B 0307.0654

PACilnC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 11 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 IA, "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 (Revision2) 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 ofUncertainty Method (ASTRUM)," January 2005.

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

7.9 WCAP-16045-P-A, "Qualification ofthe 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.

r nr 11 7l!?r ll .nor. 048 0307.0654

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUillLOCANYONPO~RPLANT REVISION 11 PAGE 8 OF 16 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) inFo Margin 0 4.19 150 4.19 355 3.93 559 3.64 764 3.31 969 2.94 1174 2.50 1378 2.02 1583 2.00 7930 2.00 8135 2.11 8340 2.22 8544 2.33 8749 2.18 8954 2.00 NOTE: All cycle bumups outside the range of this table shall use a 2% decrease in FQ margin for compliance with SR 3.2.1.2. Linear interpolation is adequate for intermediate cycle burnups.

ll'Hl7 !ll> <;d

PACIFIC GAS AND ELECTIUC COMPANY NUMBER COLR2 DUffiLOCANYONPO~RPLANT REVISION 11 PAGE 9 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 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 1.5304 *0.0 1.6187
  • 2.4 1.5232 *2.4 1.6107
  • 4.8 1.5154 *4.8 1.6022
  • 7.2 1.5053 *7.2 1.5909
  • 9.6 1.4907 *9.6 1.5741 12.1 1.4717 12.1 1.5520 14.5 1.4515 14.5 1.5279 16.9 1.4294 16.9 1.5012 19.3 1.4057 19.3 1.4721 21.7 1.3807 21.7 1.4412 24.1 1.3542 24.1 1.4085 26.5 1.3272 26.5 1.3754 28.9 1.3002 28.9 1.3421 31.4 1.2724 31.4 1.3081 33.8 1.2444 33.8 1.2792 36.2 1.2216 36.2 1.2619 38.6 1.2122 38.6 1.2535 41.0 1.2019 41.0 1.2429 43.4 1.1927 43.4 1.2317 45.8 1.1857 45.8 1.2190 48.2 1.1799 48.2 1.2079 50.8 1.1731 50.8 1.1980 53.2 1.1660 53.2 1.1875 55.6 1.1579 55.6 1.1761 58.0 1.1494 58.0 1.1641 60.4 1.1393 60.4 1.1519 62.8 1.1336 62.8 1.1385 65.2 1.1351 65.2 1.1255 67.6 1.1467 67.6 1.1231 70.0 1.1567 70.0 1.1307
  • Top and Bottom 8% Excluded r-AT u '1 .. '1.*11 nnr f).dQ

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUffiLOCANYONPO~RPLANT REVISION 11 PAGE 10 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 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 1.1664 72.5 1.1392 74.9 1.1745 74.9 1.1466 77.3 1.1815 77.3 1.1530 79.7 1.1877 79.7 1.1587 82.1 1.1930 82.1 1.1636 84.5 1.1964 84.5 1.1669 86.9 1.1986 86.9 1.1691 89.3 1.2000 89.3 1.1703 91.8 1.1990 91.8 1.1696 94.2 1.1966 94.2 1.1677 96.6 1.1915 96.6 1.1636 99.0 1.1846 99.0 1.1579 101.4 1.1755 101.4 1.1500 103.8 1.1680 103.8 1.1445 106.2 1.1671 106.2 1.1443 108.6 1.1675 108.6 1.1490 111.1 1.1641 111.1 1.1521 113.5 1.1600 113.5 1.1592 115.9 1.1606 115.9 1.1626 118.3 1.1596 118.3 1.1644 120.7 1.1568 120.7 1.1661 123.1 1.1616 123.1 1.1625 125.5 1.1668 125 .5 1.1702 127.9 1.1716 127.9 1.1776 130.3 1.1764 130.3 1.1850 132.8 1.1803 132.8 1.1908

  • 135.2 1.1830 *135.2 1.1950
  • 137.6 1.1844 *137.6 1.1973
  • 140.0 1.1827 *140.0 1.1962
  • 142.4 1.1786 *142.4 1.1927
  • 144.8 1.1754 *144.8 1.1900
  • Top and Bottom 8% Excluded rY"\T D ").,'),.1 1 n()r' nan ln07()h'i4

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 11 PAGE 11 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 8000 and 12000 MWD/MTU as a Function of Core Height HEIGHT 8000 MWD/MTU HEIGHT 12000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.3685 *0.0 1.2652
  • 2.4 1.3652 *2.4 1.2645
  • 4.8 1.3610 *4.8 1.2620
  • 7.2 1.3567 *7.2 1.2610
  • 9.6 1.3478 *9.6 1.2560 12.1 1.3345 12.1 1.2473 14.5 1.3201 14.5 1.2383 16.9 1.3041 16.9 1.2285 19.3 1.2867 19.3 1.2182 21.7 1.2684 21.7 1.2079 24.1 1.2493 24.1 1.1976 26.5 1.2296 26.5 1.1870 28.9 1.2099 28.9 1.1754 31.4 1.1946 31.4 1.1635 33.8 1.1820 33.8 1.1516 36.2 1.1701 36.2 1.1441 38.6 1.1641 38.6 1.1448 41.0 1.1619 41.0 1.1485 43.4 1.1586 43.4 1.1533 45.8 1.1547 45.8 1.1595 48 .2 1.1511 48.2 1.1641 50.8 1.1479 50.8 1.1673 53.2 1.1440 53.2 1.1694 55.6 1.1396 55.6 1.1705 58.0 1.1344 58.0 1.1705 60.4 1.1300 60.4 1.1699 62.8 1.1291 62.8 1.1669 65.2 1.1320 65 .2 1.1656 67.6 1.1455 67.6 1.1810 70.0 1.1584 70 .0 1.1984
  • Top and Bottom 8% Excluded

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 11 PAGE 12 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 8000 and 12000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 8000 MWD/MTU HEIGHT 12000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.5 1.1711 72.5 1.2154 74.9 1.1822 74.9 1.2304 77.3 1.1924 77.3 1.2441 79.7 1.2013 79.7 1.2557 82.1 1.2089 82.1 1.2655 84.5 1.2147 84.5 1.2730 86.9 1.2194 86.9 1.2792 89.3 1.2228 89.3 1.2837 91.8 1.2232 91.8 1.2839 94.2 1.2220 94.2 1.2823 96.6 1.2183 96.6 1.2779 99.0 1.2126 99.0 1.2710 101.4 1.2040 101.4 1.2606 103.8 1.2007 103.8 1.2525 106.2 1.2039 106.2 1.2515 108.6 1.2092 108.6 1.2507 111.1 1.2113 111.1 1.2445 113.5 1.2119 113.5 1.2359 115.9 1.2111 115.9 1.2339 118.3 1.2103 118.3 1.2301 120.7 1.2174 120.7 1.2240 123.1 1.2233 123.1 1.2255 125.5 1.2276 125 .5 1.2270 127.9 1.2312 127.9 1.2335 130.3 1.2410 130.3 1.2401 132.8 1.2466 132.8 1.2485

  • 135.2 1.2541 *135.2 1.2563
  • 137.6 1.2556 *137.6 1.2588
  • 140 .0 1.2486 *140.0 1.2539
  • 142.4 1.2435 *142.4 1.2426
  • 144.8 1.2379 *144.8 1.2335
  • Top and Bottom 8% Excluded

,.......,-n n 1") . . ' ) *

  • 1 1 nn f""' f\AO f\ 'H17 n,;~d

PACIFIC GAS AND ELECTIUC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 11 PAGE 13 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2C: Load Follow W(Z) Factors at 16000 and 20000 MWD/MTU as a Function of Core Height HEIGHT 16000 MWD/MTU HEIGHT 20000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.3134 *0.0 1.3474
  • 2.4 1.3125 *2.4 1.3460
  • 4.8 1.3085 *4.8 1.3398
  • 7.2 1.3064 *7.2 1.3360
  • 9.6 1.2998 *9.6 1.3271 12.1 1.2888 12.1 1.3135 14.5 1.2778 14.5 1.3000 16.9 1.2659 16.9 1.2858 19.3 1.2534 19.3 1.2710 21.7 1.2409 21.7 1.2563 24.1 1.2285 24.1 1.2419 26.5 1.2154 26.5 1.2266 28.9 1.2008 28.9 1.2093 31.4 1.1855 31.4 1.1914 33.8 1.1704 33.8 1.1732 36.2 1.1575 36.2 1.1633 38.6 1.1556 38.6 1.1670 41.0 1.1607 41.0 1.1756 43.4 1.1690 43.4 1.1859 45 .8 1.1789 45.8 1.1970 48.2 1.1871 48.2 1.2087 50.8 1.1932 50.8 1.2172 53.2 1.1978 53.2 1.2237 55 .6 1.2011 55.6 1.2287 58.0 1.2033 58.0 1.2319 60.4 1.2033 60.4 1.2337 62.8 1.2045 62.8 1.2338 65.2 1.2159 65.2 1.2348 67.6 1.2356 67.6 1.2514 70.0 1.2510 70.0 1.2636
  • Top and Bottom 8% Excluded

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR2 DIABLO CANYON POWER PLANT REVISION 11 PAGE 14 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2C: Load Follow W(Z) Factors at 16000 and 20000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 16000 MWD/MTU HEIGHT 20000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.5 1.2654 72.5 1.2746 74.9 1.2773 74.9 1.2835 77.3 1.2872 77.3 1.2906 79.7 1.2946 79.7 1.2950 82.1 1.2996 82.1 1.2971 84.5 1.3020 84.5 1.2970 86.9 1.3028 86.9 1.2957 89.3 1.3013 89.3 1.2914 91.8 1.2946 91.8 1.2818 94.2 1.2865 94.2 1.2708 96.6 1.2754 96.6 1.2570 99.0 1.2616 99.0 1.2404 101.4 1.2438 101.4 1.2241 103.8 1.2372 103.8 1.2187 106.2 1.2363 106.2 1.2154 108.6 1.2334 108.6 1.2105 111.1 1.2249 111 .1 1.2005 113.5 1.2135 113.5 1.1964 115.9 1.2077 115.9 1.1985 118.3 1.1980 118.3 1.2011 120.7 1.1904 120.7 1.2086 123.1 1.1932 123.1 1.2155 125.5 1.2070 125.5 1.2227 127.9 1.2186 127.9 1.2308 130.3 1.2305 130.3 1.2382 132.8 1.2469 132.8 1.2433

  • 135.2 1.2546 *135.2 1.2477
  • 137.6 1.2611 *137.6 1.2503
  • 140.0 1.2580 *140.0 1.2483
  • 142.4 1.2484 *142.4 1.2434
  • 144.8 1.2410 *144.8 1.2394
  • Top and Bottom 8% Excluded rnr R ? n?.-1 1 nnr 04R 0307.0654

PACD'IC GAS AND ELECTRIC COMPANY NUMBER COLR2 DVillLOCANYONPO~RPLANT REVISION 11 PAGE 15 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 225

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/ I BANKC I v

/

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§ C/)

a.

125 v

/ /

/

/

Q)

..... V 'BANKD/

(/)

v r:: 100

e 0

1co.o. 98) 1 C/)

0 a.. L

~ 75 co r::

(13 50 /

/

/

25 /

/

v Valid for Fully Withdrawn Rod Positions: ::: 225 Steps and _s 231 Steps

/I co.138, o) 1 I I I 0

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power Figme 1: Control Bank Insertion Limits Versus Rated Thermal Power r n1 "  ? ..? .* ! 1 n nr 04 fl 0307.0654

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 11 PAGE 16 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 120 r

100 I--

I--

t1 UNACCEPTABLE OPERATION 1 (-14,1oo)

IJ

(+10,100) 1\

IUNACCEPTABLE OPERATION I \

I 1/

\

80 Cl)

I ACCEPTABLE I 1\

0

n. II I OPERATION \

Cij

...EC1l J

..c: 60 1-1:1 I \

1/

.l!l fi.

0 _I (-30,50) 1(+25,50)

~

0 40 20 0

-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 Flux Difference (DELTA I) %

Figure 2: AFD Limits as a Function of Rated Thennal Power rr\T D 0u1 o* l 1 nnr (M.P. fn07.0!i S4

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