DCL-08-029, Core Operating Limits Report for Unit 2 Cycle 15
ML081050030 | |
Person / Time | |
---|---|
Site: | Diablo Canyon ![]() |
Issue date: | 03/26/2008 |
From: | Becker J Pacific Gas & Electric Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
DCL-08-029 | |
Download: ML081050030 (14) | |
Text
PacificGas and ElectricCompany" James R. Becker Diablo Canyon Power Plant Site Vice President and Mail Code 104/5/502 Station Director P.0. Box 56 Avila Beach, CA 93424 March 26, 2008 805.545.3462 Internal: 691.3462 Fax: 805.545.4234 PG&E Letter DCL-08-029 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-323, OL-DPR-82 Diablo Canyon Unit 2 Core ODeratina Limits Reoort for Unit 2
Dear Commissioners and Staff:
In accordance with Diablo Canyon Power Plant Technical Specification 5.6.5.d, enclosed is the Core Operating Limits Report (COLR) for Unit 2. The COLR has been revised for Unit 2 Cycle 15, consistent with the NRC approved License Amendment Number 196.
There are no new or revised regulatory commitments in this report.
If there are any questions regarding the COLR, please contact Mr. Steve Hamilton at (805) 545-3449.
ddm/2254/A0710976 Enclosure cc: Diablp Distribution cc/enc: Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Alan B. Wang, NRR Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance 40ý I
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Enclosure PG&E Letter DCL-08-029 CORE OPERATING LIMITS REPORT (COLR)
DIABLO CANYON POWER PLANT UNIT 2 CYCLE 15 EFFECTIVE DATE MARCH 22, 2008
- ISSUED FOR USE BY:__ DATE: EXPIRES:____
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 NUCLEAR POWER GENERATION REVISION 1 DIABLO CANYON POWER PLANT PAGE 1 OF 12 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 2 Cycle i5 2 03/22/08 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 2 Cycle 15 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
- 3.2.1 - Heat Flux Hot Channel Factor - FQ(Z)
- 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor - FN AH
- 3.2.3 - Axial Flux Difference - (AFD)
- 3.9.1 - Boron Concentration
- 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)
The SDM limit for MODE 2 with ker< 1.0, MODES 3 and 4 is:
2.1.1 The shutdown margin with Safety Injection enabled shall be greater than or equal to 1.6% Ak/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% Ak/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 1.0% Ak/k. However, an administrative value of 1.6 % Ak/k will be used to address concerns of NSAL-02-014.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 2 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 2.2 Shutdown Margin (SDM) (TS 3.1.4, 3.1.5, 3.1.6)
The SDM for MODE 1 and MODE 2 with keff> 1.0 is:
2.2.1 The shutdown margin shall be greater than or equal to 1.6% Ak/k.
2.3 Moderator Temperature Coefficient (MTC) (TS 3.1.3)
The MTC limit for MODES 1, 2, and 3 is:
2.3.1 The MTC shall be less negative than -3.9x1 0-4 Ak/k/°F for all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.
2.3.2 The MTC 300 ppm surveillance limit is -3.0x10- 4 Ak/k/°F (all rods withdrawn, RATED THERMAL POWER condition).
2.3.3 The MTC 60 ppm surveillance limit is -3.72x] 0- 4 Ak/k/°F (all rods withdrawn, RATED THERMAL POWER condition).
2.4 Shutdown Bank Insertion Limits (TS 3.1.5) 2.4.1 Each shutdown bank shall be withdrawn to at least 225 steps.
2.5 Control Bank Insertion Limits (TS 3.1.6) 2.5.1 The control banks shall be limited in physical insertion as shown in Figure 1.
2.6 Heat Flux Hot Channel Factor - FQ(Z) (TS 3.2. 1) 2.6.1 F.)(Z)<o *K(Z) for P > 0.5 P
FRJ1' F. (Z)<! L*K(Z) for P_< 0.5
0.5 where
P = THERMAL POWER RATED THERMAL POWER F RTP = 2.58 Q
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.
2.6.2 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 Cycle 15 burnups through the end of full power reactivity plus a power coast down of up to 1000 MWD/MTU.
Table I shows FQ margin decreases that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase F (Z) per SR 3.2.1.2. A 2% penalty factor shall be used at all cycle burnups that are outside the range of Table 1.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 3 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 2.6.3 FQ(Z) shall be evaluated to determine if it is within its limits by verifying that F C (Z) and F W (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:
RFTP *K(Z)
F C(Z) < Qfor P > 0.5 P
(FTP *K(Z)
F C(Z)_<ý F6for P* 0.5 0.5 W FRTP F (Z) < Q-*K(Z) for P > 0.5 Q P FQ(Z)*
Qg Q *K(Z) forP<0.5
0.5 where
F C (Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty.
F RTP is the FQ limit K(Z) is the normalized FQ(Z) as a function of core height P is the relative THERMAL POWER, and F W(Z) is the total peaking factor, F C (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.
FRTP and K(Z) are specified in 2.6.1 and W(Z) is specified in 2.6.2.
Q D7K1COO0.DOC 04B 0322.0932
PACIFIC *,AS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 4 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 Nuclear Enthalpy Rise Hot Channel Factor - F N 3.2.2) 2.7 AH (TS FN < RAP * [1 + PF, * (1-P)]
where:
THERMAL POWER RATED THERMAL POWER FAN AH = Measured values of F N AH obtained by using the moveable incore detectors to obtain a power distribution map.
F RTP = 1.59 (includes the 4% measurement uncertainty)
AH PFAH = 0.3 = Power Factor Multiplier 2.8 Power Distribution Measurement Uncertainty (TS 3.2.1. and TS 3.2.2):
If the Power Distribution Monitoring System (PDMS) is OPERABLE, the uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F AH, shall be calculated by the following formula:
UF* =1.0 100.0 +/-0 UH where: UAH = Uncertainty for enthalpy rise as defined in equation (5-19) in Reference 6.2 and F RTP AH
= 1.65 for PDMS (in the above Section 2.7 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 F-Q 1.0'+ U.O *U" U,2 Q .0100.0 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, FNAH, shall be calculated as specified in Section 2.7.
If the PDMS is inoperable, the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated as specified in Section 2.6.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 5 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 2.9 Axial Flux Difference (TS 3.2.3) 2.9.1 The Axial Flux Difference (AFD) Limits are provided in Figure 2.
2.10 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:
2.10.1 A keff of 0.95 or less, with the most reactive control rod assembly completely withdrawn, or 2.10.2 A boron concentration of greater than or equal to 2000 ppm.
2.11 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limit (TS 3.4.1) 2.11.1 Pressurizer pressure is greater than or equal to 2175 psig.
2.11.2 RCS average temperature is less than or equal to 581.7°F.
NOTE: The DNBR RCS TAVG limit is based on the slightly lower and bounding value associated with Unit I 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 of 2% Per 31 EFPD" 3.2 Table 2A, "Load Follow W(Z) Factors at 150 and 4,000 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 z, "r13 Lilits as a runction o0 Kated I nermal rower
- 5. RECORDS NONE
- 6. REFERENCES 6.1 NF-PGE-08-26, "Diablo Canyon Unit 2 Cycle 15 Reload Evaluation and COLR, Revision 1," March, 2008 6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August, 1994 D7KICOO.DOC 04B 0322.0932
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 6 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Burnup in FQ Margin (MWD/MTU) 150 2.00 313 2.40 475 2.90 638 3.29 800 3.56 963 3.70 1125 3.71 1288 3.60 1450 3.39 1613 3.10 1775 2.77 1938 2.42 2100 2.10 2263 2.00 5675 2.00 5838 2.25 6000 2.90 6163 3.48 6325 3.29 6488 3.09 6650 2.88 6813 2.66 6975 2.43 7138 2.13 7300 2.00 NOTE: All cycle burnups 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.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 7 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 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 (FEET) W(Z) (FEET) W(Z)
- 0.0000 1.5321
- 0.0000 1.5088
- 0.2000 1.5270
- 0.2000 1.5046
- 0.4000 1.5183
- 0.4000 1.4966
- 0.6000 1.5074
- 0.6000 1.4861
- 0.8000 1.4943
- 0.8000 1.4731 1.0000 1.4784 1.0000 1.4571 1.2000 1.4599 1.2000 1.4383 1.4000 1.4395 1.4000 1.4172 1.6000 1.4176 1.6000 1.3943 1.8000 1.3945 1.8000 1.3698 2.0000 1.3703 2.0000 1.3441 2.2000 1.3454 2.2000 1.3177 2.4000 1.3197 2.4000 1.2906 2.6000 1.2936 2.6000 1.2631 2.8000 1.2680 2.8000 1.2404 3.0000 1.2390 3.0000 1.2238 3.2000 1.2187 3.2000 1.2121 3.4000 1.2169 3.4000 1.2029 3.6000 1.2149 3.6000 1.1938 3.8000 1.2119 3.8000 1.1889 4.0000 1.2084 4.0000 1.1859 4.2000 1.2036 4.2000 1.1818 4.4000 1.1978 4.4000 1.1769 4.6000 1.1910 4.6000 1.1709 4.8000 1.1833 4.8000 1.1642 5.0000 1.1749 5.0000 1.1565 5.2000 1.1654 5.2000 1.1485 5.4000 1.1556 5.4000 1.1395 5.6000 1.1533 5.6000 1.1279 5.8000 1.1610 5.8000 1.1329
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 8 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 TABLE 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height (Continued)
HEIGHT 150 MWD/MTU HEIGHT 4000 MWD/MTU (FEET) W(Z) (FEET) W(Z) 6.0000 1.1754 6.0000 1.1470 6.2000 1.1867 6.2000 1.1584 6.4000 1.1974 6.4000 1.1693 6.6000 1.2067 6.6000 1.1791 6.8000 1.2147 6.8000 1.1876 7.0000 1.2210 7.0000 1.1948 7.2000 1.2256 7.2000 1.2004 7.4000 1.2282 7.4000 1.2044 7.6000 1.2286 7.6000 1.2072 7.8000 1.2266 7.8000 1.2083 8.0000 1.2222 8.0000 1.2073 8.2000 1.2152 8.2000 1.2041 8.4000 1.2054 8.4000 1.1987 8.6000 1.1927 8.6000 1.1900 8.8000 1.1785 8.8000 1.1866 9.0000 1.1615 9.0000 1.1887 9.2000 1.1462 9.2000 1.1976 9.4000 1.1432 9.4000 1.2027 9.6000 1.1426 9.6000 1.2100 9.8000 1.1416 9.8000 1.2158 10.0000 1.1420 10.0000 1.2183 10.2000 1.1449 10.2000 1.2188 10.4000 1.1502 10.4000 1.2184 10.6000 1.1563 10.6000 1.2231 10.8000 1.1621 10.8000 1.2299 11.0000 1.1668 11.0000 1.2379
- 11.2000 1.1729
- 11.2000 1.2481
- 11.4000 1.1824
- 11.4000 1.2524
- 11.6000 1.1834
- 11.6000 1.2504
- 11.8000 1.1771
- 11.8000 1.2438
- 12.0000 1.1709
- 12.0000 1.2372
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PACIFIC 'AS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 9 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 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 (FEET) W(Z) (FEET) W(Z)
- 0.0000 1.2489
- 0.0000 1.3031
- 0.2000 1.2516
- 0.2000 1.3036
- 0.4000 1.2510
- 0.4000 1.3002
- 0.6000 1.2481
- 0.6000 1.2943
- 0.8000 1.2429
- 0.8000 1.2857 1.0000 1.2355 1.0000 1.2744 1.2000 1.2264 1.2000 1.2614 1.4000 1.2167 1.4000 1.2477 1.6000 1.2066 1.6000 1.2338 1.8000 1.1962 1.8000 1.2199 2.0000 1.1857 2.0000 1.2058 2.2000 1.1752 2.2000 1.1918 2.4000 1.1643 2.4000 1.1773 2.6000 1.1530 2.6000 1.1621 2.8000 1.1477 2.8000 1. 1558 3.0000 1.1452 3.0000 1.1568 3.2000 1.1439 3.2000 1. 1620 3.4000 1.1445 3.4000 1.1700 3.6000 1.1480 3.6000 1.1775 3.8000 1.1510 3.8000 1.1863 4.0000 1.1524 4.0000 1.1968 4.2000 1.1539 4.2000 1.2069 4.4000 1.1573 4.4000 1.2148 4.6000 1.1599 4.6000 1.2209 4.8000 1.1612 4.8000 1.2250 5.0000 1.1619 5.0000 1.2275 5.2000 1.1606 5.2000 1.2276 5.4000 1.1593 5.4000 1.2266 5.6000 1.1690 5.6000 1.2316 5.8000 1.1867 5.8000 1.2423
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 10 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 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 (FEET) W(Z) (FEET) W(Z) 6.0000 1.2052 6.0000 1.2533 6.2000 1.2216 6.2000 1.2618 6.4000 1.2366 6.4000 1.2686 6.6000 1.2500 6.6000 1.2734 6.8000 1.2614 6.8000 1.2761 7.0000 1.2708 7.0000 1.2764 7.2000 1.2780 7.2000 1.2756 7.4000 1.2835 7.4000 1.2766 7.6000 1.2868 7.6000 1.2767 7.8000 1.2876 7.8000 1.2746 8.0000 1.2854 8.0000 1.2698 8.2000 1.2805 8.2000 1.2625 8.4000 1.2728 8.4000 1.2527 8.6000 1.2616 8.6000 1.2406 8.8000 1.2515 8.8000 1.2262 9.0000 1.2429 9.0000 1.2108 9.2000 1.2357 9.2000 1.2023 9.4000 1.2334 9.4000 1.2064 9.6000 1.2298 9.6000 1.2094 9.8000 1.2257 9.8000 1.2126 10.0000 1.2271 10.0000 1.2190 10.2000 1.2354 10.2000 1.2265 10.4000 1.2471 10.4000 1.2328 10.6000 1.2685 10.6000 1.2463 10.8000 1.2881 10.8000 1.2658 11.0000 1.3011 11.0000 1.2864
- 11.2000 1.3102
- 11.2000 1.3045
- 11.4000 1.3123
- 11.4000 1.3162
- 11.6000 1.3066
- 11.6000 1.3160
- 11.8000 1.2867
- 11.8000 1.3016
- 12.0000 1.2667
- 12.0000 1.2872
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PACIFIC 3AS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO ,CANYON POWER PLANT REVISION 1 PAGE 11 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 225 200 175 150 CL 4.0- 125 0,
r-0 100 0
0.
75 50 25 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 D7KICOO1.DOC 04B 0322.0932
- 6 PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 1 PAGE 12 OF 12 TITLE: COLR for Diablo Canyon Unit 2 Cycle 15 UNIT 2 120 100 80 0I-.
aC I-
'R 60 4-,
.4-0 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 D7K1COO1.DOC 04B 0322.0932