DCL-16-071, Core Operating Limits Reports for Cycle 20
| ML16193A394 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/11/2016 |
| From: | Hamzehee H Pacific Gas & Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CAC MF6120, CAC MF6121, DCL-16-071 | |
| Download: ML16193A394 (34) | |
Text
Pacific Gas and Electric Company*~
Hossein G. Hamzehee Diablo Canyon Power Plant Manager Mail Code 104/5/535 Regulatory SeNices P.O. Box 56 Avila Beach , CA 93424 805 .545.4720 Internal: 691.4720 Fax: 805.545.3459 July 11, 2016 PG&E Letter DCL-16-071 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Core Operating Limits Reports for Units 1 and 2 Cycle 20
References:
- 1. DCL-15-144, "Core Operating Limits Report for Unit 1 Cycle 20," dated December 1, 2015
- 2. NRC Letter, "Diablo Canyon Power Plant, Units 1 and 2 - Issuance of Amendments re: Revision of Reactor Coolant system (RCS) Minimum Flow Specified in Technical Specification 3.4.1 ,* "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits" (CAC Nos. MF6731 and MF6732)," dated May 19, 2016
- 3. NRC Letter, "Diablo Canyon Power Plant, Unit Nos. 1 and 2- Issuance of Amendments Regarding Revision to Updated Final Safety Analysis Report for Best Estimate Analyzer for the Core Operations - Nuclear Power Distribution Monitoring System Methodology and Technical Specification 5.6.5 (CAC Nos.
MF6120 and MF6121)," dated March 9, 2016
Dear Commissioners and Staff:
In accordance with Diablo Canyon Power Plant (DCPP) Technical Specification 5.6.5.d, the following enclosures are the Cycle 20 Core Operating Limits Reports (COLR) for Units 1 and 2:
- Enclosure 1: COLR for Diablo Canyon Unit 1, Revision 10
- Enclosure 2: COLR for Diablo Canyon Unit 2, Revision 10 A member of the STARS (Strateg i c Teaming and Resource Sharing) Alliance Callaway
- Diablo Canyon
- Palo Ve rde
- Wolf Creek
Document Control Desk PG&E Letter DCL-16-071 July 11, 2016 Page 2 The Unit 1 COLR for Cycle 20 was previously submitted in Reference 1. The Unit 1 COLR has since been revised to incorporate approved License Amendment (LA) 226 (Reference 2). The Unit 2 COLR for Cycle 20 is issued to incorporate LA 228 (Reference 2), LA 226 (Reference 3), and to reflect the cycle-specific fuel parameters associated with the Unit 2 Refueling Outage 19 core reload.
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 these COLR documents, please contact Mr. John Harmon at (805) 545-4812.
H ssein G. Hamzehee Manager, Regulatory Services mem6/4539/60078189-360 Enclosure cc: Diablo Distribution cc/enc: Kriss M. Kennedy, NRC Region IV Administrator John P. Reynoso, NRC Acting Senior Resident Inspector Balwant K. Singal, NRR Senior Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek
Enclosure 1 PG&E Letter DCL-16-071 - COLR for Diablo Canyon Unit 1 (Revision 10)
EFFECTIVE DATE: May 28, 2016
- ISSUED FOR USE BY: _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ _ EXPIRES:~----***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR1 NUCLEAR POWER GENERATION REVISION 10 DUBLOCANYONPOWERPLANT PAGE 1 OF 14 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 1 1
05/28/16 EFFECTIVE DATE CLASSIFICATION: QUALITY RELATED
- 1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 20 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 keff < 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 HotChannel Factor- F lk
- 3.2.3 - Axial Flux Difference- (AFD)
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE 2 OF 14 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% ~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, the minimum refueling boron concentration of 2000 ppm (Section 2.9 .2) 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 ~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 lulrlO.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE 3 OF 14 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 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 and 2B 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 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 _:: : 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.
COLR_ lulrlO.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 .
DUillLOCANYONPO~RPLANT REVISION 10 PAGE 4 OF 14 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 F 8(Z) and F ~ (Z) satisfy the following:
- a. Using the moveable incore detectors to obtain a power distribution map inMODE 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)
F C (Z) < Q for P > 0.5 Q p pRTP *K(Z)
F C (Z) :S; Q for P :S; 0.5 Q 0.5 W pRTP F (Z) < _Q_* K(Z) forP>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 FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty.
Q is the F Q limit FRTP 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 8(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 lulrlO.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 10 PAGE 5 OF 14 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 L'lH - L'lH
- [1 + PFllH * (1-P)]
where:
THERMAL POWER p
RATED THERMAL POWER F rH = Measured values of F ~ obtained by using the moveable incore detectors to obtain a power distribution map.
= 1.586 (prior to including 4% uncertainty)
PF m = 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, Upm, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F rH, shall be calculated by the following formula:
where: Ut:.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 ~ = 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.
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 lulrlO.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DUBLOCANYONPO~RPLANT REVISION 10 PAGE 6 OF 14 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 3,000 MWD/MTU as a Function of Core Height" 3.3 Table 2B, "Load Follow W(Z) Factors at 12,000 and 20,000 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-15-40, "Unit 1 Cycle 20 Final Reload Evaluation," August 2015 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, "Steam Line Break During Mode 3 for Westinghouse NSSS Plants," Revision 2, August 4, 2005 COLR 1u1rlO.DOC 04B 0526.1401 °
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE* 7 OF 14 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, Addendum2, 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-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988.
COLR_ lulrlO.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DUffiLOCANYONPO~RPLANT REVISION 10 PAGE 8 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 1: FQ Margin Decreases in Excess of2% Per 31 EFPD Cycle Max. % Decrease Bumup inFQ Margin (MWD/MTU) 4048 2.00 4210 2.19 4373 2.67 4535 3.13 4698 3.56 4860 3.95 5022 3.86 5185 3.72 5347 3.52 5510 3.38 5672 3.23 5834 3.08 5997 2.91 6159 2.74 6322 2.57 6484 2.38 6647 2.17 6809 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 interpolati?n is adequate for intermediate cycle bumups.
COLR_1u1rlO.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE 9 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 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 1.5037 *0.0 1.5483
- 2.4 1.4991 *2.4 1.5436
- 4.8 1.4911 *4.8 1.5351
- 7.2 1.4809 *7.2 1.5241
. *9.6 1.4685 *9.6 1.5106 12.1 1.4525 12.1 1.4932 14.5 1.4345 14.5 1.4736 16.9 1.4148 16.9 1.4517 19.3 1.3941 19.3 1.4279 21.7 1.3729 21.7 1.4025 24.1 1.3511 24.1 1.3759 26.5 1.3285 26.5 1.3484 28.9 1.3057 28.9 1.3204 31.4 1.2814 31.4 1.2908 33.8 1.2576 33.8 1.2616 36.2 1.2432 36.2 1.2386 38.6 1.2351 38.6 1.2235 41.0 1.2260 41.0 1.2151 43.4 1.2174 43.4 1.2130 45.8 1.2076 45.8 1.2100 48.2 1.2022 48.2 1.2055 50.8 1.1992 50.8 1.1998 53.2 1.1942 53.2 1.1934 55.6 1.1885 55.6 1.1859 58.0 1.1819 58.0 1.1776 60.4 1.1742 60.4 1.1683 62.8 1.1662 62.8 1.1587 65.2 1.1567 65.2 1.1477 67.6 1.1475 67.6 1.1358 70.1 1.1561 70.1 1.1375
- Top and Bottom 8% Excluded COLR_1u1r10.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE 10 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 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 1.1678 72.5 1.1467 74.9 1.1763 74.9 1.1566 77.3 1.1844 77.3 1.1656 79.7 1.1911 79.7 1.1734 82.1 1.1963 82.1 1.1799 84.5 1.1999 84.5 1.1849 86.9 1.2019 86.9 1.1885 89.3 1.2024 89.3 1.1906 91.8 1.2005 91.8 1.1907 94.2 1.1964 94.2 1.1886 96.6 I 1.1898 96.6 1.1842 99.0 1.1804 99.0 1.1773 101.4 1.1688 101.4 1.1680 103.8 1.1580 103.8 1.1589 106.2 1.1521 106.2 1.1574 108.6 1.1547 108.6 1.1611 111.1 1.1595 111.1 1.1753 113.5 1.1618 113.5 1.1954 115.9 1.1717 115.9 1.2165 118.3 1.1978 118.3 1.2371 120.7 1.2270 120.7 1.2525 123.1 1.2527 123.1 1.2642 125.5 1.2760 125.5 1.2776 127.9 1.2966 127.9 1.2901 130.4 1.3167 130.4 1.2868 132.8 1.3281 132.8 1.2854
- 135.2 1.3389 *135.2 1.2879
- 137.6 1.3514 *137.6 1.2839
- 140.0 1.3527 *140.0 1.2720
- 142.4 1.3467 *142.4 1.2544
- 144.8 1.3450 *144.8 1.2401
- Top and Bottom 8% Excluded COLR_1u1rlO.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR1 DUillLOCANYONPO~RPLANT REVISION 10 PAGE 11 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWD/MTU as a Function of Core Height HEIGHT 12000 MWD/MTU HEIGHT 20000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)
- 0.0 1.3131 *0.0 1.3736
- 2.4 1.3036 *2.4 1.3583
- 4.8 1.2928 *4.8 1.3422
- 7.2 1.2812 *7.2 1.3257
- 9.6 1.2688 *9.6 1.3089 12.1 1.2544 12.1 1.2896 14.5 1.2369 14.5 1.2692 16.9 1.2189 16.9 1.2502 19.3 1.2077 19.3 1.2365 21.7 1.1980 21.7 1.2227 24.1 1.1879 24.1 1.2092 26.5 1.1781 26.5 1.1964 28.9 1.1679 28.9 1.1843 31.4 1.1571 31.4 1.1737 33.8 1.1520 33.8 1.1656 36.2 1.1498 36.2 1.1562 38.6 1.1490 38.6 1.1562 41.0 1.1499 41.0 1.1709 43.4 1.1580 43.4 1.1872 45.8 1.,1662 45.8 1.2022 48.2 1.1732 48.2 1.2154 50.8 1.1795 50.8 1.2274 53.2 1.1842 53.2 1.2366 55.6 1.1876 55.6 1.2437 58.0 1.1896 58.0 1.2494 60.4 1.1906 60.4 1.2513 62.8 1.1893 62.8 1.2591 65 .2 1.1884 65.2 1.2856 67.6 1.1951 67.6 1.3081 70.1 1.2093 70.1 1.3289
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE 12 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWD/MTU as a Function of Core Height (continued)
HEIGHT 12000 MWD/MTU HEIGHT 20000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z) 72.5 1.2228 72.5 1.3463 74.9 1.2339 74.9 1.3607 \
77.3 1.2434 77.3 1.3722 79.7 1.2510 79.7 1.3805 82.1 1.2565 82.1 1.3855 84.5 1.2601 84.5 1.3873 86.9 1.2646 86.9 1.3858 89.3 1.2702 89.3 1.3805 91.8 1.2729 91.8 1.3704 94.2 1.2730 94.2 1.3566 96.6 1.2704 96.6 1.3385 99.0 1.2654 99.0 1.3161 101.4 1.2574 101.4 1.2898 103.8 1.2467 103.8 1.2649 106.2 1.2435 106.2 1.2552 108.6 1.2497 108.6 1.2522 111.1 1.2721 111.1 1.2461 113.5 1.2973 113.5 1.2478 115.9 1.3200 115.9 1.2715 118.3 1.3410 118.3 1.2947 120.7 1.3600 120.7 1.3154 123.1 1.3781 123.1 1.3357 125.5 1.3963 125.5 1.3~48 127.9 1.4111 127.9 1.3732 130.4 1.4181 130.4 1.3918 132.8 1.4195 132.8 1.4028
- 135.2 1.4201 *135.2 1.4093
- 137.6 1.4162 *137.6 1.4100
- 140.0 1.3988 *140.0 1.3950
- 142.4 1.3724 *142.4 1.3695
- 144.8 1.3512 *144.8 1.3502
- Top and Bottom 8% Excluded COLR 1u1r10.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR1 DUBLOCANYONPO~RPLANT REVISION 10 PAGE 13 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 225
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n:s =_ ---~-- --~------~--
_ _ __J _ _ _ ---1--- -- --
co _)_
---r-- --1------r--
1
---~---f---
I
~--
_ _ __j _ _ _ _ _ _j_ _ _ _ _ _j_ _ _ __ J __ _
---~-- --~------L-- ---1--- -- --
I I I I I 50 --+--
1
---1--- ---1--- --+--
I
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1
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-- I
-~---
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--+--
1 I
-~---
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1
---+---
I 1% --,-- --,---
I I I I I
---~--- -- -~--- ---~---
25 I
--~-- ---~-- --~------~ - - - -:--- c-- Valid for Fully Withdrawn Rod
---+-- ---r--- ----1------ -- -----j---f--
--~--
I 1 I
---:--- r- Positions: ~225 Steps And .::s_231 Steps
---+-- ==~ I(0.29,0):
I I===- ==I~ == -----1---f---~----~------~------~----~------JJ 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 1u1rlO.DOC 04B 0526.1401
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE 14 OF 14 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 120
- (-14,100) I 1 (+10,100)1 100 -
~UNACCEPTABLE~ I IUNACCEPTABLE
- OPERATION I
\ I OPERATION I \
.I I \
80 \
L..
Q) 3:
I ACCEPTABLE I \
0 a.. I OPERATION I \
I E '
L..
Q)
.s:::: 60 I 1\
I-
"C Q)
I \
v C'IS 0:::
0 I (-3o,5o) I 1(+25,50)1
~
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 Thermal Power COLR lulrlO.DOC 04B 0526.1401
Enclosure 2 PG&E Letter DCL-16-071 - COLR for Diablo Canyon Unit 2 (Revision 10)
EFFECTIVE DATE: May 28, 2016
- ISSUED FOR USE BY: _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ _ EXPIRES: _ _ _ _ _ ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR2 NUCLEAR POWER GENERATION REVISION 10 DUffiLOCANYONPOWERPLANT PAGE . 1 OF 16 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 2 2
05/28/16 EFFECTIVE DATE CLASSIFICATION: QUALITY RELATED
- 1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 2 Cycle 20 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 keff< 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 ~
- 3.2.3 - Axial Flux Difference- (AFD)
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUffiLOCANYONPO~RPLANT REVISION 10 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% L'lk!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'lklk 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 .9x1 o-4 L'lk/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 L'lk!k!°F (all rods withdrawn, RATED THERMAL POWER condition).
2.2.3 The MTC 60 ppm surveillance limit is -3.72x10-4 L'lklki°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 2u2r10.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUffiLOCANYONPO~RPLANT REVISION 10 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)
FRTP 2.5.1 FQ(Z)<-Q-*K(Z) for P> 0.5 p
FRTP 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 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 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 ~ 0.5), where Pis the core relative power during the surveillance, to account for the increase in the F Q(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.
COLR_2u2rlO.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUBLOCANYONPO~RPLANT REVISION 10 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 if (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)
F C (Z) < Q for P > 0.5 Q p C pRTP *K(Z)
F (Z):s; Q forP~0.5 Q 0.5 W pRTP F (Z) <-Q-*K(Z) for P > 0.5 Q p pRTP F WQ (Z) ~-Q-*K(Z) for P ~ 0.5
0.5 where
F 8 (Z) is the measured F Q(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 if (Z) is the total peaking factor, 8 F (Z), multiplied by W(Z) which gives the maximum F Q(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_2u2rlO.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE 5 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.6 Nuclear Enthalpy Rise Hot Channel Factor- F ~H (TS 3.2.2) 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 ~~P = 1.586 (prior to including 4% uncertainty)
PFm = 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, UFLlli, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F ~H, shall be calculated by the following utili formula: U Ftili = 1. 0+--
100.0 where: Ut:.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:
UFQ=(l.O+~]*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 ~,
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 2u2rlO.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DliffiLOCANYONPO~RPLANT REVISION 10 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 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 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 12000 MWD/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-16-22, "Diablo Canyon Unit 2 Cycle 20 Reload Evaluation and Core Operating Limits Report," April2016.
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_2u2rlO.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR2 DUillLOCANYONPO~RPLANT REVISION 10 PAGE 7 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2
- 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-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, Addenduml-A, "Qualification of the NEXUS Nuclear Data Methodology," August 2007.
COLR_2u2r10.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUffiLOCANYONPO~RPLANT REVISION 10 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) inF 0 Margin 0 6.26 150 6.26 355 6.33 559 6.23 764 5.97 968 5.56 1173 5.02 1378 4.44 1582 3.87 1787 3.37 1992 2.95 2196 2.62
- 2401 2.34 2605 2.06 2810 2.00 9153 - 2.00 9358 2.01 9562 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 2u2r10.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUillLOCANYONPO~RPLANT REVISION 10 PAGE 9 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height HEIGHT 150 MWD/MTU HEIGHT 4000 MWD/MTU (INCHES) W(Z) (INCHES) W(Z)
- 0.0 1.4475 *0.0 1.6178
- 2.4 1.4455 *2.4 1.6153
- 4.8 1.4410 *4.8 1.6097
- 7.2 1.4339 *7.2 1.6005
- 9.6 1.4219 *9.6 1.5845 12.1 1.4063 12.1 1.5633 14.5 1.3895 14.5 1.5398 16.9 1.3710 16.9 1.5134 19.3 1.3515 19.3 1.4848 21.7 1.3306 21.7 1.4540 24.1 1.3083 24.1 1.4211 26.5 1.2857 26.5 1.3881 28.9 1.2630 28.9 1.3553 31.4 1.2393 31.4 1.3218 33.8 1.2170 33.8 1.2889 36.2 1.2015 36.2 1.2600 38.6 1.1943 38.6 1.2429 41.0 1.1894 41.0 1.2319 43.4 1.1829 43.4 1.2243 45.8 1.1764 45.8 1.2152 48.2 1.1711 48.2 1.2056 50.8 1.1654 50.8 1.1949 53.2 1.1593 53.2 1.1842 55.6 1.1522 55.6 1.1726 58.0 1.1438 58.0 1.1605 60.4 1.1405 60.4 1.1477 62.8 1.1409 62.8 1.1357 65.2 1.1461 65.2 1.1248 67.6 1.1534 67.6 1.1136 70.0 1.1637 70.0 1.1202
- Top and Bottom 8% Excluded COLR 2u2r10.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE 10 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 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 1.1741 72.5 1.1301 74.9 1.1828 74.9 1.1392 77.3 1.1902 77.3 1.1474 79.7 1.1968 79.7 1.1549 82.1 1.2026 82.1 1.1617 84.5 1.2063 84.5 1.1668 86.9 1.2087 86.9 1.1708 89.3 1.2103 89.3 1.1737 91.8 1.2096 91.8 1.1750 94.2 1.2073 94.2 1.1750 96.6 1.2022 96.6 1.1727 99.0 1.1951 99.0 1.1688 101.4 1.1856 101.4 1.1632 103.8 1.1795 103.8 1.1556 106.2 1.1789 106.2 1.1477 108.6 1.1807 108.6 1.1481 111.1 1.1808 111.1 1.1544 113.5 1.1782 113.5 1.1591
. 115.9 1.1813 115.9 1.1673 118.3 1.1859 118.3 1.1709 120.7 1.1899 120.7 1.1743 123.1 1.1933 123.1 1.1728 125.5 1.1948 125.5 1.1690 127.9 1.1945 127.9 1.1787 130.3 1.1946 130.3 1.1942 132.8 1.1958 132.8 1.2040
- 135.2 1.1994 *135.2 1.2140
- 137.6 1.2004 *137.6 1.2158
- 140.0 1.1997 *140.0 1.2156
- 142.4 1.1979 *142.4 1.2155
- 144.8 1.1966 *144.8 1.2154
- Top and Bottom 8% Excluded COLR_2u2r10.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DliffiLOCANYONPO~RPLANT REVISION 10 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 1.4365 *0.0 1.2784
- 2.4 1.4357 *2.4 1.2784
- 4.8 1.4330 *4.8 1.2775
- 7.2 1.4288 *7.2 1.2768
- 9.6 1.4198 *9.6 1.2730 12.1 1.4062 12.1 1.2651 14.5 1.3908 14.5 1.2561 16.9 1.3737 16.9 1.2466 19.3 1.3552 19.3 1.2366 21.7 1.3352 21.7 1.2261 24.1 1.3141 24.1 1.2155 26.5 1.2925 26.5 1.2044 28.9 1.2702 28.9 1.1924 31.4 1.2473 31.4 1.1798 33.8 1.2251 33.8 1.1678 36.2 1.2034 36.2 1.1557 38.6 1.1888 38.6 1.1491 41.0 1.1838 41.0 1.1487 43.4 1.1786 43.4 1.1478 45.8 1.1725 45.8 1.1498 48.2 1.1672 48 .2 1.1536 50.8 1.1628 50.8 1.1558 53.2 1.1576 53.2 1.1572 55.6 1.1518 55.6 1.1577 58.0 1.1453 58.0 1.1574 60.4 1.1389 60.4 1.1563 62.8 1.1303 62.8 1.1547 65.2 1.1231 65.2 1.1542 67.6 1.1329 67.6 1.1653 70.0 1.1460 70.0 1.1795
- Top and Bottom 8% Excluded COLR 2u2rlO.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUillLOCANYONPO~RPLANT REVISION 10 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 1.1589 72.5 1.1934 74.9 1.1704 74.9 1.2054 77.3 1.1809 77.3 1.2163 79.7 1.1903 79.7 1.2254 82.1 1.1985 82.1 1.2330 84.5 1.2050 84.5 1.2384 86.9 1.2101 86.9 1.2427 89.3 1.2138 89.3 1.2456 91.8 1.2151 91.8 1.2447 94.2 1.2149 94.2 1.2424 96.6 1.2120 96.6 1.2373 99.0 1.2072 99.0 1.2302 101.4 1.2004 101.4 1.2217 103.8 1.1900 103.8 1.2169 106.2 1.1894 106.2 1.2191 108.6 1.1969 108.6 1.2231 111.1 1.2013 111.1 1.2235 113.5 1.2027 113.5 1.2223 115.9 1.2116 115.9 1.2196 118.3 1.2150 118.3 1.2149 120.7 1.2196 120.7 1.2128 123.1 1.2197 123.1 1.2159 125.5 1.2217 125.5 1.2179 127.9 1.2303 127.9 1.2277 130.3 1.2381 130.3 1.2370 132.8 1.2440 132.8 1.2422
- 135.2 1.2484 *135.2 1.2464
- 137.6 1.2498 *137.6 1.2467
- 140.0 1.2472 *140.0 1.2421
- 142.4 1.2419 *142.4 1.2344
- 144.8 1.2378 *144.8 1.2281
- Top and Bottom 8% Excluded COLR 2u2r10.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUWLOCANYONPO~RPLANT REVISION 10 PAGE 13 OF -16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 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 1.2571 *0.0 1.3540
- 2.4 1.2569 *2.4 1.3532
- 4.8 1.2550 *4.8 1.3479
- 7.2 1.2541 *7.2 1.3439
- 9.6 1.2499 *9.6 1.3358 12.1 1.2415 12.1 1.3226 14.5 1.2321 14.5 1.3085 16.9 1.2225 16.9 1.2943 19.3 1.2127 19.3 1.2797 21.7 1.2027 21.7 1.2652 24.1 1.1929 24.1 1.2508 26.5 1.1825 26.5 1.2355 28.9 1.1709 28.9 1.2180 31.4 1.1580 31.4 1.1999 33.8 1.1509 33.8 1.1816 36.2 1.1537 36.2 1.1671 38.6 1.1572 38 .6 1.1679 41.0 1.1605 41.0 1.1770 43.4 1.1659 43.4 1.1870 45.8 1.1744 45.8 1.1980 48.2 1.1810 48.2 1.2098 50.8 1.1859 50.8 1.2192 53.2 1.1894 53.2 1.2264 55.6 1.1917 55.6 1.2320 58.0 1.1926 58.0 1.2359 60.4 1.1932 60.4 1.2382 62.8 1.1932 62.8 1.2385 65.2 1.1936 65.2 1.2386 67.6 1.2061 67.6 1.2499 70.0 1.2201 70.0 1.2625
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DliffiLOCANYONPOWERPLANT REVISION 10 PAGE 14 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 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) 72.5 1.2332 72.5 1.2737 74.9 1.2442 74.9 1.2829 77.3 1.2536 77.3 1.2905 79.7 1.2608 79.7 1.2955 82.1 1.2659 82.1 1.2981 84.5 1.2687 84.5 1.2984 86.9 1.2703 86.9 1.2975 89.3 1.2698 89.3 1.2937 91.8 1.2648 91.8 1.2845 94.2 1.2584 94.2 1.2740 96.6 1.2493 96.6 1.2606 99.0 1.2379 99.0 1.2445 101.4 1.2249 101.4 1.2266 103.8 1.2202 103 .8 1.2192 106.2 1.2189 106.2 1.2161 108.6 1.2161 108.6 1.2107 111.1 1.2097 111.1 1.2008 113.5 1.2015 113.5 1.1913 115.9 1.2045 115.9 1.1928 118.3 1.2077 118.3 1.1986 120.7 1.2102 120.7 1.2059 123.1 1.2115 123.1 1.2125 125.5 1.2307 125.5 1.2194 127.9 1.2564 127.9 1.2290 130.3 1.2822 130.3 1.2514 132.8 1.2985 132.8 1.2674
- 135.2 1.3099 *135.2 1.2828
- 137.6 1.3143 *137.6 1.2919
- 140.0 1.3140 *140.0 1.2924
- 142.4 1.3110 *142.4 1.2877
- 144.8 1.3093 *144.8 1.2853
- Top and Bottom 8% Excluded COLR 2u2r10.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUBLOCANYONPO~RPLANT REVISION 10 PAGE 15 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 225
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VI (0.138, 0) I 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 2u2rlO.DOC 04B 0526.1413
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DliffiLOCANYONPO~RPLANT REVISION 10 PAGE 16 OF 16 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 120 I (-14,100) I II (+1o, 1oo) r 100 1---- tj UNACCEPTABLE OPERATION IJ
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Figure 2: AFD Limits as a Function of Rated Thermal Power COLR 2u2rlO.DOC 04B 0526.1413