DCL-21-042, Core Operating Limits Report for Unit 2 Cycle 23

From kanterella
Jump to navigation Jump to search
Core Operating Limits Report for Unit 2 Cycle 23
ML21138A940
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 05/18/2021
From: Conner S
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-21-042
Download: ML21138A940 (18)
v • d • e


Text

mPacific Gas and Electric Company*

Shannon Conner Manager, Program Engineering Diablo Canyon Power Plant Mail code 104/4/401 P.O. Box 56 Avila Beach, CA 93424 805.545.6171 Internal: 691.6171 Fax: 805.545.3808 PG&E Letter DCL-21-042 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 23

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 23.

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.

Sincerely, 05/18/21 Shannon Conner Date kjse/50943730-06 Enclosure cc: Diablo Distribution cc/enc: Donald R. Krause, NRC Senior Resident Inspector Samson S. Lee, NRR Senior Project Manager Scott A. Morris, NRC Region IV Administrator A member of the STARS Alliance Callaway

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

Enclosure PG&E Letter DCL-21-042 DIABLO CANYON POWER PLANT CORE OPERATING LIMITS REPORT UNIT 2 CYCLE 23 EFFECTIVE DATE APRIL 14, 2021

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR2 NUCLEAR POWER GENERATION REVISION 13 DIABLOCANYONPOWERPLANT PAGE 1 OF 16 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 2 2

04/14/21 EFFECTIVE DATE CLASSIFICATION: QUALITY RELATED

1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 2 Cycle 23 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 ~
  • 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 2u2rl3.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 13 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 ShutdownMargin(SDM) (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8)

The SDM limit for MODE 1, MODE 2, MODE 3 and MODE 4 is:

2.1.1 The shutdown margin shall be greater than or equal to 1.6% ~k/k.

2.1.2 In Modes 3 or 4 the shutdown margin with Safety Injection blocked shall be greater than or equal to 1.6% ~k/k calculated at a temperature of 200°F.

The SDM limit for MODE 5 is:

2.1.3 The shutdown margin shall be greater than or equal to 1.6% Lik/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 -3.9x10*4 ~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 -3.0x10*4 ~k/k/°F (all rods withdrawn, RATED THERMAL POWER condition).

2.2.3 The MTC 60 ppm surveillance limit is -3.72x10*4 ~k/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_2u2r13.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 13 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 FiTP =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 coastdown ofup to 408 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 "'tj_ (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_2u2r13.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 13 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 "'t (Z) satisfy the following:

a. Using the moveable incore detectors to obtain a power distribution map inMODE 1.
b. Increasing the measured F Q(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 Q 0.5 W pRTP F (Z) <-Q-*K(Z) for P > 0.5 Q p pRTP F~ (Z):o;_Q_*K(Z) forP:o;0.5

0.5 where

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

F~TP istheFQlimit 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 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_2u2rl3.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 13 PAGE 5 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F rH (TS 3.2.2)

FN < FRTP *[l + PF,.,H * (1-P)]

AH - AH where:

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

pRTP = 1.586 (prior to including 4% uncertainty)

AH

= 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, UF.,.H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, FrH, shall be calculated by the following UMI formula: U FMf =l .0+--

100.0 where: u~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!ti = 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 =(1.Q+~J*100.0 Ue where: UQ = Uncertainty for power peaking factor as defined in equation (5-19) in Reference 6.2. However, if the uncertainty is less than 5.0, the uncertainty should be set equal to 5.0.

Ue = 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_2u2r13.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 13 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 limits:

2.9.1 A k,ff 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 217 5 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 6000 MWD/MTU as a Function of Core Height" 3.3 Table 2B, "Load Follow W(Z) Factors at 8000 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-21-013, Revision 1 "Diablo Canyon Unit 2 Cycle 23 Final Reload Evaluation and Core Operating Limits Report," March 2021.

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_2u2r13.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 13 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 byNRC Safety Evaluation dated January 31, 1978.

7.4 WCAP-16996-P-A, Revision 1, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology)," November 2016.

7.5 Not used.

7.6 Not used.

7.7 Not used.

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.

COLR 2u2rl3.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 13 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 Cycle Burnup Max. % Decrease (MWD/MTU) inFo Margin 3214 2.00 3418 2.26 3622 2.66 3827 2.90 4031 2.98 4235 2.91 4439 2.77 4644 2.61 4848 2.47 5052 2.36 5256 2.32 5461 2.81 5665 2.84 5869 2.85 6073 2.81 6278 2.72 6482 2.58 6686 2.23 6890 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.

COLR_2u2rl3.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 13 PAGE 9 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 6000 MWD/MTU as a Function of Core Height HEIGHT 150MWD/MTU HEIGHT 6000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.2866 *0.0 1.4046
  • 2.4 1.2859 *2.4 1.4031
  • 4.8 1.2862 *4.8 1.4014
  • 7.2 1.2898 *7.2 1.4025
  • 9.6 1.2858 *9.6 1.3953 12.1 1.2765 12.1 1.3828 14.5 1.2660 14.5 1.3675 16.9 1.2542 16.9 1.3505 19.3 1.2415 19.3 1.3317 21.7 1.2281 21.7 1.3116 24.1 1.2139 24.1 1.2902 26.5 1.1995 26.5 1.2684 28.9 1.1852 28.9 1.2461 31.4 1.1703 31.4 1.2225 33.8 1.1559 33.8 1.2027 36.2 1.1446 36.2 1.1924 38.6 1.1401 38.6 1.1844 41.0 1.1396 41.0 1.1787 43.4 1.1411 43.4 1.1759 45.8 1.1431 45.8 1.1736 48.2 1.1444 48.2 1.1703 50.8 1.1453 50.8 1.1660 53.2 1.1453 53.2 1.1612 55.6 1.1445 55.6 1.1555 58.0 1.1430 58.0 1.1492 60.4 1.1428 60.4 1.1423 62.8 1.1522 62.8 1.1347 65.2 1.1652 65.2 1.1255 67.6 1.1777 67.6 1.1319 70.0 1.1894 70.0 1.1444
  • Top and Bottom 8% Excluded COLR_2u2r13.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 13 PAGE 10 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 6000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 150MWD/MTU HEIGHT 6000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.5 1.2057 72.5 1.1564 74.9 1.2193 74.9 1.1668 77.3 1.2318 77.3 1.1763 79.7 1.2429 79.7 1.1847 82.1 1.2526 82.1 1.1920 84.5 1.2598 84.5 1.1975 86.9 1.2651 86.9 1.2018 89.3 1.2690 89.3 1.2048 91.8 1.2706 91.8 1.2056 94.2 1.2700 94.2 1.2048 96.6 1.2660 96.6 1.2016 99.0 1.2596 99.0 1.1965 101.4 1.2507 101.4 1.1896 103.8 1.2394 103.8 1.1798 106.2 1.2248 106.2 1.1831 108.6 1.2222 108.6 1.1944 111.1 1.2340 111.1 1.2031 113.5 1.2460 113.5 1.2102 115.9 1.2566 115.9 1.2157 118.3 1.2656 118.3 1.2191 120.7 1.2738 120.7 1.2245 123.1 1.2809 123.1 1.2362 125.5 1.2892 125.5 1.2469 127.9 1.2987 127.9 1.2566 130.3 1.3078 130.3 1.2658 132.8 1.3151 132.8 1.2728

  • 135.2 1.3207 *135.2 1.2777
  • 137.6 1.3227 *137.6 1.2796
  • 140.0 1.3169 *140.0 1.2744
  • 142.4 1.3056 *142.4 1.2642
  • 144.8 1.2962 *144.8 1.2556
  • Top and Bottom 8% Excluded COLR_2u2rl3.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 13 PAGE 11 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 8000 and 10000 MWD/MTU as a Function of Core Height HEIGHT 8000 MWD/MTU HEIGHT 10000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.4252 *0.0 1.3644
  • 2.4 1.4236 *2.4 1.3638
  • 4.8 1.4214 *4.8 1.3623
  • 7.2 1.4222 *7.2 1.3643
  • 9.6 1.4146 *9.6 1.3585 12.1 1.4016 12.1 1.3480 14.5 1.3857 14.5 1.3348 16.9 1.3678 16.9 1.3202 19.3 1.3482 19.3 1.3040 21.7 1.3271 21.7 1.2869 24.1 1.3047 24.1 1.2689 26.5 1.2817 26.5 1.2503 28.9 1.2579 28.9 1.2310 31.4 1.2332 31.4 1.2101 33.8 1.2096 33.8 1.1944 36.2 1.1865 36.2 1.1909 38.6 1.1726 38.6 1.1869 41.0 1.1689 41.0 1.1822 43.4 1.1645 43.4 1.1772 45.8 1.1631 45.8 1.1743 48.2 1.1605 48.2 1.1720 50.8 1.1570 50.8 1.1683 53.2 1.1530 53.2 1.1642 55.6 1.1483 55.6 1.1591 58.0 1.1429 58.0 1.1532 60.4 1.1369 60.4 1.1467 62.8 1.1304 62.8 1.1394 65.2 1.1227 65.2 1.1304 67.6 1.1331 67.6 1.1386 70.0 1.1477 70.0 1.1530
  • Top and Bottom 8% Excluded COLR_2u2rl3.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 13 PAGE 12 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 8000 and 10000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 8000 MWD/MTU HEIGHT 10000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.5 1.1617 72.5 1.1668 74.9 1.1740 74.9 1.1790 77.3 1.1855 77.3 1.1903 79.7 1.1957 79.7 1.2002 82.1 1.2046 82.1 1.2088 84.5 1.2118 84.5 1.2156 86.9 1.2177 86.9 1.2213 89.3 1.2221 89.3 1.2255 91.8 1.2240 91.8 1.2267 94.2 1.2243 94.2 1.2264 96.6 1.2220 96.6 1.2237 99.0 1.2178 99.0 1.2191 101.4 1.2115 101.4 1.2122 103.8 1.2020 103.8 1.2029 106.2 1.1992 106.2 1.1999 108.6 1.2026 108.6 1.1990 111.1 1.2018 111.1 1.1952 113.5 1.2038 113.5 1.1992 115.9 1.2043 115.9 1.2004 118.3 1.2139 118.3 1.2051 120.7 1.2228 120.7 1.2129 123.1 1.2309 123.1 1.2197 125.5 1.2373 125.5 1.2252 127.9 1.2426 127.9 1.2298 130.3 1.2522 130.3 1.2393 132.8 1.2590 132.8 1.2464

  • 135.2 1.2597 *135.2 1.2482
  • 137.6 1.2438 *137.6 1.2322
  • 140.0 1.2356 *140.0 1.2138
  • 142.4 1.2313 *142.4 1.2149
  • 144.8 1.2270 *144.8 1.2032
  • Top and Bottom 8% Excluded COLR 2u2rl3.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 13 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 1.3395 *0.0 1.3463
  • 2.4 1.3394 *2.4 1.3460
  • 4.8 1.3381 *4.8 1.3428
  • 7.2 1.3402 *7.2 1.3442
  • 9.6 1.3351 *9.6 1.3380 12.1 1.3257 12.1 1.3276 14.5 1.3138 14.5 1.3149 16.9 1.3007 16.9 1.3013 19.3 1.2866 19.3 1.2870 21.7 1.2718 21.7 1.2724 24.1 1.2566 24.1 1.2577 26.5 1.2407 26.5 1.2423 28.9 1.2233 28.9 1.2251 31.4 1.2053 31.4 1.2072 33.8 1.1878 33.8 1.1902 36.2 1.1714 36.2 1.1737 38.6 1.1653 38.6 1.1679 41.0 1.1655 41.0 1.1746 43.4 1.1668 43.4 1.1802 45.8 1.1716 45.8 1.1860 48.2 1.1741 48.2 1.1892 50.8 1.1753 50.8 1.1903 53.2 1.1756 53.2 1.1923 55.6 1.1747 55.6 1.1956 58.0 1.1727 58.0 1.1974 60.4 1.1698 60.4 1.1978 62.8 1.1657 62.8 1.1969 65.2 1.1596 65.2 1.2021 67.6 1.1683 67.6 1.2257 70.0 1.1826 70.0 1.2428
  • Top and Bottom 8% Excluded COLR 2u2rl3.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 13 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 1.1960 72.5 1.2586 74.9 1.2078 74.9 1.2723 77.3 1.2184 77.3 1.2841 79.7 1.2271 79.7 1.2931 82.1 1.2340 82.1 1.2996 84.5 1.2391 84.5 1.3037 86.9 1.2430 86.9 1.3060 89.3 1.2451 89.3 1.3048 91.8 1.2434 91.8 1.2983 94.2 1.2402 94.2 1.2903 96.6 1.2347 96.6 1.2794 99.0 1.2271 99.0 1.2658 101.4 1.2164 101.4 1.2493 103.8 1.2090 103.8 1.2298 106.2 1.2067 106.2 1.2147 108.6 1.2039 108.6 1.2125 111.1 1.1972 111.1 1.2075 113.5 1.1983 113.5 1.2048 115.9 1.1967 115.9 1.2002 118.3 1.1986 118.3 1.1967 120.7 1.2040 120.7 1.1942 123.1 1.2172 123.1 1.1910 125.5 1.2326 125.5 1.2147 127.9 1.2291 127.9 1.2286 130.3 1.2342 130.3 1.2463 132.8 1.2568 132.8 1.2695

  • 135.2 1.2489 *135.2 1.2692
  • 137.6 1.2376 *137.6 1.2655
  • 140.0 1.2322 *140.0 1.2514
  • 142.4 1.2383 *142.4 1.2460
  • 144.8 1.2444 *144.8 1.2405
  • Top and Bottom 8% Excluded COLR_2u2rl3.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 13 PAGE 15 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 225 V/ (0.583, 225) j .

200 /

/

V I <1.0, 188) I/

/

175

/I BANKC I /

-C:

~

cu 150 / V V

L.

V "C

.c:

~

125 / /

C. V -. / .

/

Cl)

VIBANKDI U)

C:

100 0 I (o.o, 98) I

E

~

0 a.

75

/

V co C:

cu 50 /

V V

25 /

/

V Valid for Fully Withdrawn Rod Positions: ~ 225 Steps and .:::. 231 Steps

/I (0.138, o) 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 Figure 1 : Control Bank Insertion Limits Versus Rated Thermal Power COLR_2u2r13.DOC 04B 0413.1449

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLOCANYONPOWERPLANT REVISION 13 PAGE 16 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 120

(-14,100) I I (+10, 100) 100 - j UNACCEPTABLE OPERATION \

IUNACCEPTABLE OPERATION

- I I \

80 I

I I

I

'\

0 I ACCEPTABLE OPERATION I \,

C.

iij I

E Q) I

.c: 60 I-

"C I \

~

0 j

....0 i/

I (-30,50) '

(+25,50) 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 Thermal Power COLR_2u2rl3.DOC 04B 0413.1449

Retrieved from "https://kanterella.com/w/index.php?title=DCL-21-042,_Core_Operating_Limits_Report_for_Unit_2_Cycle_23&oldid=3410270"