DCL-17-072, Core Operating Limits Report for Cycle 21

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Core Operating Limits Report for Cycle 21
ML17227A809
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 08/15/2017
From: Nimick J
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-17-072
Download: ML17227A809 (18)
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Text

Pacific Gas and Electric Companyq; Jan A. Nimick Diablo Canyon Power Plant Senior Director Mail code 104/5/507 Nuclear Services P.O. Box 56 Avila Beach, CA 93424 805.545.6783 Internal: 691.4596 Fax: 805.545.4234 August15,2017 PG&E Letter DCL-17-072 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 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 1, 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. John Harmon at (805) 545-4812.

bnsm/4540 Enclosure cc: Diablo Distribution cc/enc: Scott A. Morris, NRC Region IV Administrator (Acting)

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-17 -072 DIABLO CANYON POWER PLANT CORE OPERATING LIMITS REPORT UNIT 1 CYCLE 21 EFFECTIVE DATE May 31, 2017

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 NUCLEAR POWER GENERATION REVISION 11 DIABLO CANYON POWER PLANT PAGE 1 OF 16 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 1 1

INFO ONLY EFFECTIVE DATE CLASSIFICATION: QUALITY RELATED

1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 21 has been prepared in accordance with the requirements ofTechnical 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_l ulrll.doc 04B 0720.1505
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 2 OF 16 TITLE: COLR for Diablo Canyon Unit 1

  • UNIT 1
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% ~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% Mdk. 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 ~op 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 ~oF (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.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 3 OF 16 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 F0 (Z)<_g_*K(Z) for P > 0.5

- p pRTP F0 (Z)<_g_*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 1000 MWD/MTU.

For W(Z) data at a desired bumup not listed in the table, but less than the maximum listed bumup, values at 3 or more bumup steps should be used to interpolate the W(Z) data to the desired bumup with a 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 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.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 4 OF 16 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 g

F (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 o/o to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.
c. Satisfying the following relationship:

F g (Z) <

pRTP Q

  • K(Z)

P for P > 0.5 pRTP *K(Z)

FC(Z)< Q forP=s:;0.5

~ 0.5 W pRTP F (Z) <-Q-*K(Z) for P > 0.5 Q p pRTP F ~ (Z) =:;;-Q-*K(Z) for P =:;; 0.5

'< 0.5 where:

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

F RTP is the F limit

~ Q K(Z) is the normalized FQ(Z) as a function of core height Pis the relative THERMAL POWER, and F1{ (Z) is the total peaking factor, Fg (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.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 5 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 2.6 Nuclear Enthalpy Rise Hot Channel Factor- F ~ (TS 3.2.2)

F~ ~ F ~p *[1 + PFm * (1-P)]

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.

F~P = 1.586 (prior to including 4% uncertainty)

PF 6.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, UF6.H, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F ~, shall be calculated by the following formula:

UFM-1=1.0+--

utili 100.0 where: U6.H =Uncertainty for enthalpy rise as defmed 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:

UF0- .=(1.0+~)*ue 100.0 where: UQ = Uncertainty for power peaking factor as defmed 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 ~, 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.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 6 OF 16 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 keffof0.95 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) 2.1 0.1 Pressurizer pressure is greater than or equal to 21 75 psi g.

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 359,200 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, "Fo 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 12000MWD/MTU as a Function of Core Height" 3.4 Table 2C, "Load Follow W(Z) Factors at 16000 and 22000 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-17-3, "Diablo Canyon Unit 1 Cycle 21 Final Reload Evaluation and Core Operating Limits Report," April 2017 6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August 1994 6.3 Westinghouse Nuclear Safety Advisory Letter NSAL-02-14, Revision 2, "Steam Line Break During Mode 3 for Westinghouse NSSS Plants," August 4, 2005 COLR_lulrll.doc 04B 0720.1505
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 7 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1

7. ANALYTICALMETHODS The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

7.1 WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification," February 1994.

7.2 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

7.3 WCAP-8385, "Power Distribution Control and Load Following Procedures," September 1974. Approved by NRC Safety Evaluation dated January 31, 1978.

7.4 WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

7.5 WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection Into the Broken Loop and COSI Condensation Model," July 1997.

7.6 WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2- 5 (Revision 1), "Code Qualification Document for Best-Estimate LOCA Analysis," March 1998.

7.7 WCAP-12945-P-A, Addendum 1-A, Revision 0, "Method for Satisfying 10 CFR 50.46 Reanalysis Requirements for Best Estimate LOCA Evaluation Models," December 2004.

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

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

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

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 8 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Bumup in FQ Margin (MWD/MTU) 0 2.00 24240 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.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 9 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 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 1.2269 *0.0 1.3275
  • 2.4 1.2234 *2.4 1.3235 4.8 1.2197 *4.8 1.3191 7.2 1.2151 *7.2 1.3135 9.7 1.2074 *9.7 1.3038 12.1 1.1971 12.1 1.2904 14.5 1.1868 14.5 1.2762 16.9 1.1760 16.9 1.2606 19.3 1.1650 19.3 1.2439 21.7 1.1540 21.7 1.2269 24.1 1.1429 24.1 1.2122 26.6 1.1318 26.6 1.1971 29.0 1.1233 29.0 1.1818 31.4 1.1204 31.4 1.1661 33.8 1.1166 33.8 1.1509 36.2 1.1145 36.2 1.1367 38.6 1.1164 38.6 1.1295 41.0 1.1177 41.0 1.1288 43.5 1.1211 43.5 1.1288 45.9 1.1266 45 .9 1.1314 48.3 1.1309 48.3 1.1332 50.7 1.1346 50.7 1.1341 53.1 1.1371 53.1 1.1344 55.5 1.1385 55.5 1.1340 57.9 1.1392 57.9 1.1333 60.4 1.1384 60.4 1.1307 62 .8 1.1387 62.8 1.1314 65.2 1.1441 65.2 1.1406 67.6 1.1555 67.6 1.1513 70.0 1.1701 70.0 1.1624
  • Top and Bottom 8% Excluded (note that a reduced exclusion zone at the bottom of the core will be implemented in the begim1ing of Cycle 21 until the peak FQ is shown to occur outside of the typical 8% exclusion zone).

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 10 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 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) 72.4 1.1854 72.4 1.1176 74.8 1.1988 74.8 1.1906 77.3 1.2112 77.3 1.2028 79.7 1.2227 79.7 1.2137 82.1 1.2334 82.1 1.2234 84.5 1.2421 84.5 1.2310 86.9 1.2497 86.9 1.2377 89.3 1.2556 89.3 1.2423 91.7 1.2587 91.7 1.2436 94.2 1.2598 94.2 1.2430 96.6 1.2573 96.6 1.2390 99.0 1.2524 99.0 1.2325 101.4 1.2452 101.4 1.2235 103.8 1.2335 103.8 1.2094 106.2 1.2303 106.2 1.2086 108.6 1.2330 108.6 1.2152 111.1 1.2429 111.1 1.2238 113.5 1.2584 113.5 1.2455 115.9 1.2672 115.9 1.2566 118.3 1.2779 118.3 1.2530 120.7 1.2819 120.7 1.2675 123.1 1.2848 123.1 1.3024 125.5 1.3007 125.5 1.3117 128.0 1.3130 128.0 1.3209 130.4 1.3248 130.4 1.3382 132.8 1.3360 132.8 1.3473

  • 135.2 1.3306 *135.2 1.3527
  • 137.6 1.3182 *137.6 1.3574
  • 140.0 1.3242 *140.0 1.3604
  • 142.4 1.3417 *142.4 1.3653
  • 144.9 1.3549 *144.9 1.3707 1
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 11 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 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 1.3241 *0.0 1.3113
  • 2.4 1.3204 *2.4 1.3087
  • 4.8 1.3161 *4.8 1.3046
  • 7.2 1.3108 *7.2 1.3001
  • 9.7 1.3015 *9.7 1.2918 12.1 1.2886 12.1 1.2800 14.5 1.2748 14.5 1.2675 16.9 1.2598 16.9 1.2540 19.3 1.2436 19.3 1.2395 21.7 1.2269 21.7 1.2246 24.1 1.2096 24.1 1.2094 26.6 1.1921 26.6 1.1937 29.0 1.1738 29.0 1.1772 31.4 1.1571 31.4 1.1604 33.8 1.1484 33.8 1.1437 36.2 1.1401 36.2 1.1312 38.6 1.1357 38.6 1.1302 41.0 1.1335 41.0 1.1299 43 .5 1.1298 43.5 1.1287 45.9 1.1275 45.9 1.1281 48.3 1.1285 48.3 1.1296 50.7 1.1321 50.7 1.1338 53.1 1.1342 53.1 1.1375 55.5 1.1358 55.5 1.1405 57.9 1.1367 57.9 1.1428 60.4 1.1368 60.4 1.1440 62.8 1.1371 62.8 1.1454 65.2 1.1418 65.2 1.1500 67.6 1.1523 67.6 1.1613 70.0 1.1623 70.0 1.1769
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 12 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 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) 72.4 1.1734 72.4 1.1927 74.8 1.1829 74.8 1.2069 77.3 1.1914 77.3 1.2201 79.7 1.1988 79.7 1.2316 82.1 1.2049 82.1 1.2416 84.5 1.2093 84.5 1.2497 86.9 1.2148 86.9 1.2569 89.3 1.2212 89.3 1.2616 91.7 1.2244 91.7 1.2623 94.2 1.2262 94.2 1.2611 96.6 1.2254 96.6 1.2566 99.0 1.2227 99.0 1.2495 101.4 1.2177 101.4 1.2393 103.8 1.2108 103.8 1.2250 106.2 1.2042 106.2 1.2193 108.6 1.1956 108.6 1.2213 111.1 1.1955 111.1 1.2254 113.5 1.2022 113.5 1.2512 115.9 1.2298 115.9 1.2764 118.3 1.2436 118.3 1.2933 120.7 1.2759 120.7 1.3184 123.1 1.3337 123.1 1.3557 125.5 1.3533 125.5 1.3758 128.0 1.3697 128.0 1.3960 130.4 1.3851 130.4 1.4184 132.8 1.3974 132.8 1.4257

  • 135.2 1.4056
  • 135.2 1.4311
  • 137.6 1.4056 *137.6 1.4364
  • 140.0 1.4045 *140.0 1.4376
  • 142.4 1.4141 *142.4 1.4447
  • 144.9 1.4196 *144.9 1.4496
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 13 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2C: Load Follow W(Z) Factors at 16000 and 22000 MWD/MTU as a Function of Core Height HEIGHT 16000 MWD/MTU HEIGHT 22000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)

  • 0.0 1.2334 *0.0 1.2674
  • 2.4 1.2326 *2.4 1.2663
  • 4.8 1.2291 *4.8 1.2604
  • 7.2 1.2260 *7.2 1.2552
  • 9.7 1.2198 *9.7 1.2467 12.1 1.2106 12.1 1.2349 14.5 1.2012 14.5 1.2232 16.9 1.1913 16.9 1.2112 19.3 1.1810 19.3 1.1990 21.7 1.1709 21.7 1.1873 24.1 1.1611 24.1 1.1761 26.6 1.1510 26.6 1.1644 29.0 1.1394 29.0 1.1509 31.4 1.1309 31.4 1.1371 33.8 1.1304 33.8 1.1237 36.2 1.1305 36.2 1.1183 38.6 1.1337 38.6 1.1296 41.0 1.1374 41.0 1.1443 43.5 1.1423 43.5 1.1606 45.9 1.1510 45.9 1.1764 48.3 1.1583 48.3 1.1900 50.7 1.1637 50.7 1.2009 53.1 1.1679 53.1 1.2096 55.5 1.1712 55.5 1.2170 57.9 1.1732 57.9 1.2232 60.4 1.1749 60.4 1.2255 62.8 1.1745 62.8 1.2325 65.2 1.1741 65.2 1.2532 67.6 1.1930 67.6 1.2764 70.0 1.2092 70.0 1.2941
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 14 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2C: Load Follow W(Z) Factors at 16000 and 22000 MWD/MTU as a Function of Core Height (continued)

HEIGHT 16000 MWD/MTU HEIGHT 22000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.2249 72.4 1.3105 74.8 1.2386 74.8 1.3243 77.3 1.2511 77.3 1.3359 79.7 1.2615 79.7 1.3442 82.1 1.2699 82.1 1.3496 84.5 1.2764 84.5 1.3521 86.9 1.2817 86.9 1.3521 89.3 1.2840 89.3 1.3479 91.7 1.2815 91.7 1.3373 94.2 1.2771 94.2 1.3248 96.6 1.2694 96.6 1.3083 99.0 1.2587 99.0 1.2882 101.4 1.2446 101.4 1.2647 103.8 1.2274 103.8 1.2386 106.2 1.2212 106.2 1.2201 108.6 1.2209 108.6 1.2035 111.1 1.2223 111.1 1.1914 113.5 1.2287 113.5 1.2000 115.9 1.2279 115.9 1.2127 118.3 1.2402 118.3 1.2234 120.7 1.2557 120.7 1.2344 123.1 1.2740 123.1 1.2378 125.5 1.2917 125.5 1.2594 128.0 1.3077 128.0 1.2761 130.4 1.3229 130.4 1.2906 132.8 1.3334 132.8 1.2986

  • 135.2 1.3408 *135.2 1.3060
  • 137.6 1.3490 *137.6 1.3164
  • 140.0 1.3528 *140.0 1.3225
  • 142.4 1.3560 *142.4 1.3290
  • 144.9 1.3550 *144.9 1.3322
  • Top and Bottom 8% Excluded COLR_lulrll.doc 04B 0720.1505
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 15 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 225

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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_lulrll.doc 04B 0720.1505

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 11 PAGE 16 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1

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Figure 2: AFD Limits as a Function of Rated Thermal Power COLR_lulrll.doc 04B 0720.1505

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