DCL-13-030, Core Operating Limits Report for Unit 2 Cycle 18
| ML13086A566 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/27/2013 |
| From: | Welsch J Pacific Gas & Electric Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| DCL-13-030 | |
| Download: ML13086A566 (15) | |
Text
Pacific Gas and Electric Company Diab lo Ca nyon Power Plant James M. Welsch Station Director Mail Code 104/5/502 P. O. Box 56 Av ila Beach, CA 93424 805 .545.3242 March 27, 2013 Internal: 691.3242 Fax: 805.545 .4234 Internet: JMW1@pge.com PG&E Letter DCL-13-030 u.s. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-323, OL-DPR-82 Diablo Canyon Power Plant Unit 2 Core Operating Limits Report for Unit 2 Cycle 18
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 Unit 2. This document was revised for DCPP Unit 2, Cycle 18.
Pacific Gas and Electric (PG&E) 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. Mark Mayer at (805) 545-4674.
Sincerely, J8L3/4486 Enclosure cc: Diablo Distribution cc/enc: Elmo E. Collins, NRC Region IV Thomas R. Hipschman. NRC Senior Resident Inspector James T. Polickoski, NRR Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway . Comanche Peak . Diablo Canyon . Palo Verde . San Onofre . South Texas Project . Wolf Creek
Enclosure PG&E Letter DCL-13-030 CORE OPERATING LIMITS REPORTS (COLR)
DIABLO CANYON POWER PLANT UNIT 2, CYCLE 18 EFFECTIVE DATE March 14,2013
- ISSUED FOR USE BY: _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ _ EXPIRES: _ _ _ _ _ ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 NUCLEAR POWER GENERATION REVISION 7 DIABLO CANYON POWER PLANT PAGE 1 OF 13 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 2 2
03/14/13 EFFECTIVE DATE CLASSIFICATION: QUALITY RELATED
- 1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 2 Cycle 18 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)
- 3.9.1 - Boron Concentration COLR_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 7 PAGE 2 OF 13 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 with Safety Injection enabled 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 1.0% ~k/k. However, an administrative value of 1.6 % ~k/k will be used to address concerns of NSAL-02-014 (Reference 6.3).
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 0-4 ~k/k/oF 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/oF (all rods withdrawn, RATED THERMAL POWER condition).
2.2.3 The MTC 60 ppm surveillance limit is -3.72x10-4 ~k/k/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.
COLR_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 7 PAGE 3 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.5 Heat Flux Hot Channel Factor - FQ(Z) (TS 3.2.1)
F RTP 2.5.1 FQ(Z)<-Q-*K(Z) for P> 0.5 P
F RTP 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 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 burnup, 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 lIP (P > 0.5) or 1/0.5 (P :s 0.5), where P is the core relative power during the surveillance, to account for the increase in the 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 i{ (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_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 7 PAGE 4 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.5.3 FQ(Z) shall be evaluated to detennine if it is within its limits by verifying that F g (Z) and F "t (Z) satisfy the following:
- a. Using the moveable inc ore 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:
FRTP *K(Z)
Fe (Z) < Q for P > 0.5 Q p F RTP *K(Z)
Fe (Z) < Q for P :::; 0.5 Q 0.5 W F RTP F (Z) <-Q-*K(Z) for P > 0.5 Q P F RTP F W (Z) :::;-Q-*K(Z) for P:::; 0.5 Q 0.5 where:
F g (Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty.
F~TP is the FQ limit K(Z) is the nonnalized FQ(Z) as a function of core height P is the relative THERMAL POWER, and F ~ (Z) is the total peaking factor, F g(Z), multiplied by W(Z) which gives the maximum FQ(Z) calculated to occur in nonnal operation.
W (Z) is the cycle dependent function that accounts for power distribution transients encountered during nonnal operation.
F~TP and K(Z) are specified in 2.5.1 and W(Z) is specified in 2.5.2.
COLR_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUBLOCANYONPO~RPLANT REVISION 7 PAGE 5 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F~ (TS 3.2.2)
F~ ~ F~JP *[1 + PFm * (I-P)]
where:
THERMAL POWER P
RATED THERMAL POWER F~ = Measured values of F ~ obtained by using the moveable incore detectors to obtain a power distribution map.
F ~JP = 1.586 (prior to including 4% uncertainty)
PFLlH = 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, U FLlH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F ~, shall be calculated by the following UM!
formula: U FM! =1.0+--
100.0 where: U LlH = 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~r = 1.65 for PDMS (in the above Section 2.6 equation).
If the PDMS is OPERABLE, the uncertainty, U FQ, to be applied to the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated by the following formula:
UFQ=(1.0+~J*Ue 100.0 where: U Q= 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_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 7 PAGE 6 OF 13 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 and Temperature 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.
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 4,000 MWDIMTU as a Function of Core Height" 3.3 Table 2B, "Load Follow W(Z) Factors at 12,000 and 20,000 MWDIMTU 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-13-17,"Diablo Canyon Unit 2 Cycle 18 Reload Evaluation and Core Operating Limits Report, Revision 1," March 4, 2013.
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_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUBLOCANYONPO~RPLANT REVISION 7 PAGE 7 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 6.4 Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Bumup inFQMargin (MWDIMTU) 150 2.00 312 2.01 475 2.98 637 3.75 799 4.27 961 4.48 1124 4.40 1286 4.08 1448 3.59 1611 3.02 1773 2.43 1935 2.00 5668 2.00 5830 2.57 5993 2.99 6155 2.86 6317 2.72 6480 2.62 6642 2.52 6804 2.41 6967 2.29 7129 2.17 7291 2.05 7453 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_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 7 PAGE 8 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWDIMTU as a Function of Core Height HEIGHT 150 MWDIMTU HEIGHT 4000 MWDIMTU (INCHES) W(Z) (INCHES W(Z)
- 0.0 1.5137 *0.0 1.4970
- 2.4 1.4961 *2.4 1.4781
- 4.8 1.4777 *4.8 1.4611
- 7.2 1.4590 *7.2 1.4462
- 9.7 1.4402 *9.7 1.4340 12.1 1.4187 12.1 1.4193 14.5 1.3947 14.5 1.4020 16.9 1.3704 16.9 1.3828 19.3 1.3517 19.3 1.3618 21.7 1.3321 21.7 1.3394 24.1 1.3107 24.1 1.3161 26.6 1.2902 26.6 1.2916 29.0 1.2722 29.0 1.2675 31.4 1.2551 31.4 1.2458 33.8 1.2390 33.8 1.2250 36.2 1.2261 36.2 1.2070 38.6 1.2156 38.6 1.1944 41.0 1.2074 41.0 1.1873 43.5 1.2052 43.5 1.1846 45.9 1.2023 45.9 1.1816 48.3 1.1982 48.3 1.1777 50.7 1.1930 50.7 1.1727 53.1 1.1869 53.1 1.1671 55.5 1.1800 55.5 1.1606 57.9 1.1722 57.9 1.1533 60.4 1.1638 60.4 1.1452 62.8 1.1543 62.8 1.1370 65.2 1.1449 65.2 1.1284 67.6 1.1425 67.6 1.1204 70.0 1.1524 70.0 1.1273
- Top and Bottom 8% Excluded COLR_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 7 PAGE 9 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWDIMTU as a Function of Core Height (Continued)
HEIGHT 150 MWDIMTU HEIGHT 4000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.1650 72.4 1.1390 74.9 1.1751 74.9 1.1494 77.3 1.1847 77.3 1.1592 79.7 1.1931 79.7 1.1680 82.1 1.2001 82.1 1.1757 84.5 1.2057 84.5 1.1821 86.9 1.2096 86.9 1.1870 89.3 1.2118 89.3 1.1905 91.8 1.2129 91.8 1.1931 94.2 1.2118 94.2 1.1938 96.6 1.2084 96.6 1.1923 99.0 1.2026 99.0 1.1892 101.4 1.1943 101.4 1.1833 103.8 1.1836 103.8 1.1752 106.2 1.1737 106.2 1.1760 108.7 1.1736 108.7 1.1870 111.1 1.1767 111.1 1.2017 113.5 1.1767 113.5 1.2131 115.9 1.1808 115.9 1.2230 118.3 1.1824 118.3 1.2303 120.7 1.1860 120.7 1.2383 123.1 1.1910 123.1 1.2458 125.6 1.1940 125.6 1.2511 128.0 1.1980 128.0 1.2589 130.4 1.2007 130.4 1.2758 132.8 1.1998 132.8 1.2865
- 135.2 1.2065 *135.2 1.2949
- 137.6 1.2170 *137.6 1.2988
- 140.0 1.2160 *140.0 1.2936
- 142.5 1.2044 *142.5 1.2838
- 144.9 1.1959 *144.9 1.2754
- Top and Bottom 8% Excluded COLR_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 7 PAGE 10 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWDIMTU as a Function of Core Height HEIGHT 12000 MWDIMTU HEIGHT 20000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z)
- 0.0 1.2703 *0.0 1.3120
- 2.4 1.2689 *2.4 1.3146
- 4.8 1.2674 *4.8 1.3127
- 7.2 1.2660 *7.2 1.3080
- 9.7 1.2615 *9.7 1.3003 12.1 1.2538 12.1 1.2890 14.5 1.2446 14.5 1.2764 16.9 1.2346 16.9 1.2631 19.3 1.2240 19.3 1.2495 21.7 1.2131 21.7 1.2357 24.1 1.2019 24.1 1.2216 26.6 1.1904 26.6 1.2073 29.0 1.1787 29.0 1.1928 31.4 1.1662 31.4 1.1773 33.8 1.1558 . 33.8 1.1606 36.2 1.1529 36.2 1.1564 38.6 1.1527 38.6 1.1598 41.0 1.1536 41.0 1.1716 43.5 1.1557 43.5 1.1839 45.9 1.1570 45.9 1.1950 48.3 1.1567 48.3 1.2046 50.7 1.1573 50.7 1.2129 53.1 1.1595 53.1 1.2189 55.5 1.1604 55.5 1.2231 57.9 1.1601 57.9 1.2254 60.4 1.1595 60.4 1.2256 62.8 1.1559 62.8 1.2253 65.2 1.1549 65.2 1.2322 67.6 1.1686 67.6 1.2533 70.0 1.1868 70.0 1.2733
- Top and Bottom 8% Excluded COLR_2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUffiLOCANYONPO~RPLANT REVISION 7 PAGE 11 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWDIMTU as a Function of Core Height (Continued)
HEIGHT 12000 MWDIMTU HEIGHT 20000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.2028 72.4 1.2893 74.9 1.2175 74.9 1.3035 77.3 1.2306 77.3 1.3152 79.7 1.2421 79.7 1.3245 82.1 1.2517 82.1 1.3311 84.5 1.2592 84.5 1.3347 86.9 1.2648 86.9 1.3358 89.3 1.2688 89.3 1.3346 91.8 1.2706 91.8 1.3298 94.2 1.2696 94.2 1.3218 96.6 1.2660 96.6 1.3105 99.0 1.2598 99.0 1.2959 101.4 1.2507 101.4 1.2780 103.8 1.2388 103.8 1.2586 106.2 1.2312 106.2 1.2449 108.7 1.2295 108.7 1.2322 111.1 1.2279 111.1 1.2183 113.5 1.2233 113.5 1.2078 115.9 1.2217 115.9 1.1998 118.3 1.2252 118.3 1.1950 120.7 1.2300 120.7 1.2015 123.1 1.2334 123.1 1.2206 125.6 1.2357 125.6 1.2398 128.0 1.2399 128.0 1.2633 130.4 1.2562 130.4 1.2847 132.8 1.2667 132.8 1.2968
- 135.2 1.2720 *135.2 1.3096
- 137.6 1.2712 *137.6 1.3183
- 140.0 1.2598 *140.0 1.3124
- 142.5 1.2410 *142.5 1.2929
- 144.9 1.2244 *144.9 1.2774
- Top and Bottom 8% Excluded COLR_ 2u2r07.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 7 PAGE 12 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 225 VI (0.583,225) I 200 /
/
V 1(1.0, 188) 1/
/
175
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~
C'CS "C
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/1 (0.138,0) 1 o
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_2u2rD7.DOC 04B 0307.0729
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DUillLOCANYONPO~RPLANT REVISION 7 PAGE 13 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 120 I (-14,100) I II (+10,100)1 100 r-- j UNACCEPTABLE OPERATION I
\
IUNACCEPTABLE OPERATION r--
/ \
/ \
~
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a..
- / ACCEPTABLE I \
0 c.. / OPERATION I \,
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0 40 20 o
-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_2u2r07.DOC 04B 0307.0729