DCL-19-037, Submittal of Core Operating Limits Report for Unit 1 Cycle 22
| ML19112A211 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/22/2019 |
| From: | Harbor C Pacific Gas & Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| DCL-19-037 | |
| Download: ML19112A211 (18) | |
Text
Pacific Gas and Electric Company"'
Cary . Harbor Diablo Canyon Power Plant Interim Senior Director Mail code 104/6/601 Engineering, Technical and P.O. Box 56 Emergency Services Avila Beach, CA 93424 805.545.4102 Internal: 691.4102 April 22, 2019 PG&E Letter DCL-19-037 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 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 1, 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.
Sincerely,
/2=d~
Cary D. Harbor rntt/4231 Enclosure cc: Diablo Distribution cc/enc: Scott A. Morris, NRG Region IV Administrator Christopher W. Newport, NRG Senior Resident Inspector Balwant K. Singal, NRR Senior Project Manager A member of the STARS Alliance Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek
Enclosure PG&E Letter DCL-19-037 DIABLO CANYON POWER PLANT CORE OPERATING LIMITS REPORT UNIT 1 CYCLE 22 EFFECTIVE DATE March 14, 2019
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 NUCLEAR POWER GENERATION REVISION 12 DIABLOCANYONPOWERPLANT PAGE 1 OF 16 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 1 1
03/14/19 EFFECTIVE DATE CLASSIFICATION: QUALITY RELATED
- 1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for the Diablo Canyon Unit 1 Cycle 22 redesign 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 - Shutdown Margin (MODE 2 with k,,ff< 1.0, MODES 3, 4, and 5)
- 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 rH
- 3.2.3 - Axial Flux Difference - (AFD)
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 12 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% L'1k/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% L'1k/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% t-.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 .9xl 0-4 L'1k/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 L'1k/k/°F (all rods withdrawn, RATED THERMAL POWER condition).
2.2.3 The MTC 60 ppm surveillance limit is -3.72x10-4 L'1k/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.
COLR lulrl2.DOC 04B 0307.1522
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 3 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 2.5 Heat Flux Hot Channel Factor -F 0 (Z) (TS 3.2.1)
FRTP 2.5.1 FQ(Z)<-Q-*K(Z) for P> 0.5 p
pRTP FQ(Z)<-Q-*K(Z) for Ps 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 burnups 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 burnup 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 F 0(Z) limit at reduced power levels.
Table 1 shows F0 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.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT . REVISION 12 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 Fi (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:
g F (Z) <
pRTP Q
- K(Z) p for P > 0.5 pRTP *K(Z)
FQC(Z):C:: Q forP:c::0.5 0.5 W pRTP F (Z) < _Q_* K(Z) for P > 0.5 Q p pRTP FWQ(Z):C::-Q-*K(Z) forP:c::0.5
0.5 where
g F (Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty.
FRTP Q
is the FQ limit K(Z) is the normalized FQ(Z) as a function of core height P is the relative THERMAL POWER, and Ft (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.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 5 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F rH (TS 3.2.2)
FN < FRTP *[1 + PF,,,H * (1-P)]
flH - flH where:
p THERMAL POWER RATED THERMAL POWER F rH = Measured values of F rH obtained by using the moveable incore detectors to obtain a power distribution map.
= 1.586 (prior to including 4% uncertainty)
= 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, UFMI, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F rH, shall be calculated by the following formula:
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 !Jl = 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+~]*ue 100.0 where: Uq = Uncertainty for power peaking factor as defined in equation (5-19) in Reference 6.2.
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 lulrl2.DOC 048 0307.1522
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLOCANYONPOWERPLANT REVISION 12 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 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 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, "FQ Margin Decreases in Excess of2% Per 31 EFPD" 3.2 Table 2A, "Load Follow W(Z) Factors at 150 and 4000 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 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 of Rated Thermal Power"
- 5. RECORDS None
- 6. REFERENCES 6.1 NF-PGE-19-028, "Diablo Canyon Unit 1 Cycle 22 Redesign Reload Evaluation and Core Operating Limits Report," March 2019 6.2 WCAP-12472-P-A, Addendum 4, "BEACON Core Monitoring and Operation 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 lulrl2.DOC 04B 0307.1522
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 12 PAGE 7 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1
- 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 F0 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 CPR 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 of the NEXUS Nuclear Data Methodology," August 2007.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLOCANYONPOWERPLANT REVISION 12 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 Burnup in FQ Margin (MWD/MTU) 0 2.97 150 2.97 354 3.91 558 4.34 762 4.33 967 4.08 1171 3.61 1375 3.02 1579 2.43 1783 2.00 7499 2.00 7704 2.20 7908 2.41 8112 2.60 8316 2.33 8520 2.00 NOTE: All cycle burnups outside the range ofthis 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.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 9 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height HEIGHT 150MWD/MTU HEIGHT 4000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)
- 0.0 1.5415 *0.0 1.5598
- 2.4 1.5334 *2.4 1.5523
- 4.8 1.5255 *4.8 1.5450
- 7.2 1.5148 *7.2 1.5352
- 9.6 1.5002 *9.6 1.5208 12.1 1.4818 12.1 1.5019 14.5 1.4621 14.5 1.4812 16.9 1.4406 16.9 1.4583 19.3 1.4175 19.3 1.4333 21.7 1.3932 21.7 1.4067 24.1 1.3674 24.1 1.3784 26.5 1.3412 26.5 1.3497 28.9 1.3149 28.9 1.3212 31.4 1.2877 31.4 1.2990 33 .8 1.2606 33.8 1.2832 36.2 1.2364 36.2 1.2659 38.6 1.2243 38.6 1.2500 41.0 1.2185 41.0 1.2374 43.4 1.2111 43.4 1.2266 45.8 1.2027 45.8 1.2179 48.2 1.1935 48.2 1.2077 50.8 1.1837 50.8 1.1965 53.2 1.1752 53.2 1.1864 55.6 1.1668 55.6 1.1773 58.0 1.1579 58.0 1.1675 60.4 1.1481 60.4 1.1571 62.8 1.1388 62.8 1.1464 65.2 1.1348 65.2 1.1347 67.6 1.1418 67.6 1.1237 70.0 1.1502 70.0 1.1288
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 10 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height (continued)
HEIGHT 150MWD/MTU HEIGHT 4000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.5 1.1595 72.5 1.1374 74.9 1.1671 74.9 1.1466 77.3 1.1738 77.3 1.1556 79.7 1.1796 79.7 1.1636 82.1 1.1845 82.1 1.1707 84.5 1.1877 84.5 1.1761 86.9 1.1898 86.9 1.1803 89.3 1.1902 89.3 1.1828 91.8 1.1881 91.8 1.1824 94.2 1.1845 94.2 1.1807 96.6 1.1780 96.6 1.1761 99.0 1.1695 99.0 1.1696 101.4 1.1630 101.4 1.1609 103.8 1.1559 103.8 1.1490 106.2 1.1510 106.2 1.1472 108.6 1.1500 108.6 1.1467 111.1 1.1545 111.1 1.1503 113.5 1.1640 113.5 1.1665 115.9 1.1690 115.9 1.1805 118.3 1.1706 118.3 1.1908 120.7 1.1718 120.7 1.2007 123.1 1.1687 123.1 1.2012 125.5 1.1690 125.5 1.2123 127.9 1.1665 127.9 1.2042 130.3 1.1775 130.3 1.2040 132.8 1.1812 132.8 1.2174
- 135.2 1.1996 *135.2 1.2235
- 137.6 1.2168 *137.6 1.2261
- 140.0 1.2271 *140.0 1.2272
- 142.4 1.2269 *142.4 1.2275
- 144.8 1.2346 *144.8 1.2284
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLOCANYONPOWERPLANT REVISION 12 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 1.3804 *0.0 1.2711
- 2.4 1.3764 *2.4 1.2698
- 4.8 1.3717 *4.8 1.2666
- 7.2 1.3664 *7.2 1.2639
- 9.6 1.3571 *9.6 1.2578 12.1 1.3441 12.1 1.2484 14.5 1.3300 14.5 1.2386 16.9 1.3145 16.9 1.2281 19.3 1.2977 19.3 1.2169 21.7 1.2802 21.7 1.2057 24.1 1.2619 24.1 1.1945 26.5 1.2433 26.5 1.1829 28.9 1.2239 28.9 1.1699 31.4 1.2040 31.4 1.1587 33.8 1.1846 33.8 1.1546 36.2 1.1673 36.2 1.1492 38 .6 1.1600 38.6 1.1472 41.0 1.1591 41.0 1.1507 43.4 1.1572 43.4 1.1559 45 .8 1.1550 45.8 1.1637 48.2 1.1516 48.2 1.1697 50.8 1.1474 50.8 1.1741 53.2 1.1444 53.2 1.1773 55.6 1.1420 55.6 1.1794 58.0 1.1393 58.0 1.1806 60.4 1.1347 60.4 1.1798 62.8 1.1332 62.8 1.1804 65.2 1.1398 65 .2 1.1892 67.6 1.1505 67.6 1.2085 70.0 1.1646 70.0 1.2262
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLOCANYONPOWERPLANT REVISION 12 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) 72.5 1.1791 72.5 1.2433 74.9 1.1921 74.9 1.2580 77.3 1.2040 77.3 1.2710 79.7 1.2145 79.7 1.2817 82.1 1.2236 82.1 1.2902 84.5 1.2307 84.5 1.2963 86.9 1.2370 86.9 1.3009 89.3 1.2409 89.3 1.3023 91.8 1.2411 91.8 1.2989 94.2 1.2394 94.2 1.2935 96.6 1.2346 96.6 1.2846 99.0 1.2272 99.0 1.2727 101.4 1.2172 101.4 1.2573 103.8 1.2025 103.8 1.2413 106.2 1.1999 106.2 1.2434 108.6 1.2258 108.6 1.2502 111.1 1.2527 111.1 1.2553 113 .5 1.2758 113.5 1.2761 115 .9 1.2992 115.9 1.2988 118.3 1.3195 118.3 1.3193 120.7 1.3403 120.7 1.3413 123.1 1.3567 123.1 1.3568 125.5 1.3795 125.5 1.3783 127.9 1.3900 127.9 1.3876 130.3 1.4031 130.3 1.3989 132.8 1.4125 132.8 1.4093
- 135 .2 1.4182 *135.2 1.4093
- 137.6 1.4220 *137.6 1.4186
- 140.0 1.4222 *140.0 1.4186
- 142.4 1.4204 *142.4 1.4183
- 144.8 1.4195 *144.8 1.4182
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLOCANYONPOWERPLANT REVISION 12 PAGE 13 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 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 1.3091 *0.0 1.3386
- 2.4 1.3078 *2.4 1.3368
- 4.8 1.3030 *4.8 1.3299
- 7.2 1.2992 *7.2 1.3242
- 9.6 1.2918 *9.6 1.3143 12.1 1.2808 12.1 1.3005 14.5 1.2697 14.5 1.2869 16.9 1.2581 16.9 1.2727 19.3 1.2460 19.3 1.2581 21.7 1.2342 21.7 1.2438 24.1 1.2227 24.1 1.2299 26.5 1.2105 26.5 1.2152 28.9 1.1969 28 .9 1.1985 31.4 1.1828 31.4 1.1810 33.8 1.1689 33 .8 1.1664 36.2 1.1573 36.2 1.1605 38.6 1.1575 38.6 1.1648 41.0 1.1644 41.0 1.1814 43.4 1.1732 43.4 1.1957 45 .8 1.1852 45.8 1.2099 48 .2 1.1948 48.2 1.2216 50.8 1.2024 50.8 1.2304 53.2 1.2082 53 .2 1.2370 55.6 1.2125 55.6 1.2419 58.0 1.2161 58 .0 1.2454 60.4 1.2166 60.4 1.2471 62.8 1.2210 62.8 1.2540 65.2 1.2440 65 .2 1.2825 67.6 1.2643 67.6 1.3067 70 .0 1.2795 70 .0 1.3247
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 12 PAGE 14 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 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 1.2936 72.5 1.3413 74.9 1.3050 74.9 1.3550 77.3 1.3141 77.3 1.3662 79.7 1.3203 79.7 1.3737 82.1 1.3238 82.1 1.3780 84.5 1.3248 84.5 1.3793 86.9 1.3237 86.9 1.3785 89.3 1.3190 89.3 1.3732 91.8 1.3087 91.8 1.3612 94.2 1.2966 94.2 1.3471 96.6 1.2810 96.6 1.3289 99.0 1.2621 99.0 1.3069 101.4 1.2388 101.4 1.2816 103.8 1.2229 103.8 1.2538 106.2 1.2236 106.2 1.2330 108.6 1.2239 108.6 1.2168 111.1 1.2231 111.1 1.2032 113.5 1.2267 113.5 1.1989 115.9 1.2273 115.9 1.1998 118.3 1.2316 118.3 1.2101 120.7 1.2443 120.7 1.2245 123.1 1.2549 123.1 1.2417 125.5 1.2720 125.5 1.2548 127.9 1.2828 127.9 1.2665 130.3 1.2944 130.3 1.2782 132.8 1.3019 132.8 1.2874
- 135.2 1.3083 *135.2 1.2972
- 137.6 1.3180 *137.6 1.3039
- 140.0 1.3215 *140.0 1.3100
- 142.4 1.3203 *142.4 1.3148
- 144.8 1.3230 *144.8 1.3182
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLRl DIABLOCANYONPOWERPLANT REVISION 12 PAGE 15 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 225 __ __ __.:l
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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 lu l rl 2.DOC 048 0307. 1522
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 12 PAGE 16 OF 16 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 .
120 r I 1(-14,100) 1 (+10,100) 100 ~
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Figure 2: AFD Limits as a Function of Rated Thermal Power COLR lulrl 2.DOC 04B 0307. 1522