DCL-07-060, Core Operating Limits Report, Cycle 15
| ML071710449 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/11/2007 |
| From: | Becker J Pacific Gas & Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| DCL-07-060 | |
| Download: ML071710449 (26) | |
Text
PacificGas and A!! ElectricCompany James R. Becker Diablo Canyon Power Plant Vice President P. 0. Box 56 Diablo Canyon Operations and Avila Beach, CA 93424 Station Director 805.545.3462 June 11,2007 Fax: 805.545.4234 PG&E Letter DCL-07-060 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Diablo Canyon Unit 1 Core ODeratina Limits Report Unit 1. Cycle 15
Dear Commissioners and Staff:
In accordance with Diablo Canyon Power Plant Technical Specification 5.6.5.d, enclosed are the Core Operating Limits Report (COLR) for Unit 1, Cycle 15, Revision 0 and Revision 1. Note, Revision 1 was effective prior to the start of Unit 1, Cycle 15.
There are no new or revised regulatory commitments in this report.
If there are any questions regarding the COLR for Unit 1, Cycle 15, please contact Mr. Larry Parker at (805) 545-3386.
ddm/2254/A0679170 Enclosures cc/enc: Edgar Bailey, DHS Terry W. Jackson, NRC Senior Resident Inspector Bruce S. Mallett, NRC Region IV Alan B. Wang, NRR Project Manager cc: Diablo Distribution A member of the STARS (Strategic Teaming and Resource Sharing) AlLiance Cattaway
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Enclosure 1 PG&E Letter DCL-07-060 CORE OPERATING LIMITS REPORT (COLR)
DIABLO CANYON POWER PLANT UNIT 1, CYCLE 15, REVISION 0 (12 Pages)
EFFECTIVE DATE MAY 15, 2007
- ISSUED FOR USE BY: DATE: EXPIRES: :_***
PACIFIC GAS AND ELECTRIC COMIPANY NUMBER COLR 1-15 NUCLEAR POWER GENERATION REVISION 0 DIABLO CANYON POWER PLANT PAGE 1 OF 12 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 1 EPFECTEIVE IQR PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 15 has been prepared in accordance with the requirements of Technical Specification (TS)'5.6.5.
The Technical Specifications affected by this report are listed below:
3.1.1 - Shutdown Margin (MODE 2 with kff < 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 - F N 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 kfr < 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.
2.2 Shutdown Margin (SDM) (TS 3.1.4, 3.1.5, 3.1.6)
The SDM for MODE I and MODE 2 with k,ff> 1.0 is:
2.2.1 The shutdown margin shall be greater than or equal to 1.6% Ak/k.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 2 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1.
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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 .9 xl04 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 .OX104 AWk/F (all rods withdrawn, RATED THERMAL POWER condition).
2.3.3 The MTC 60 ppm surveillance limit is -3.72x1004 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 FQ(Z)<* *K(Z) for P > 0.5 P
F RTP FQ(Z)<-Q *K(Z) forP< 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 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 W (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.
F1OUUCOO.doa 04B 0509.0824
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 3 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 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:
FC (Z) < *K(Z) for P > 0.5 P
- K(Z)
R*FTP' F (Z)<
Q 0.5 (Z for P__ 0.5 FWQ (Z)5 <--*-*K(Z)
P for P:5 0.5 Q 0.5 ,K(Z) forP_<.5 where:
F ( (Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty.
F RTT is the FQ limit Q
K(Z) is the normalized FQ(Z) as a function of core height P is the relative THERMAL POWER, and F Q (Z) is the total peaking factor, F Q (Z), multiplied by W(Z) which gives the maximum FQ(Z) calculated to occur in normal operation.
W(z) is the cycle dependefit function that accounts for power distribution transients encountered during normal operation.
F RTP and K(Z) are specified in 2.6.1 and W(Z) is specified in 2.6.2.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 4 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1(
2.7 Nuclear Enthalpy Rise Hot Channel Factor - Fa (TS 3.2.2)
FN <FRTP *,[+ PFH * (l-P)]
AllI ALT L i
where:
- THERMAL POWER RATED THERMAL POWER F All N Measured values of F N All obtained by using the moveable incore detectors to obtain a power distribution map.
F RTP = 1.59 (includes the 4% measurement uncertainty)
AH PFm = 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, UFm, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F N shall be calculated by the following formula:
UFA =1.0+ UAH 100.0 where: UH = Uncertainty for enthalpy rise as defined in equation (5-19) in Reference 6.2 2.7 equation).
andFRTP = 1.65 for PDMS (in the above Section 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:
UFQ1.0+UQ *'l UFQ .0100.0)J*
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 N 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.
F1OUUCOO.doa 04B 0509.0824
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 5 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 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 kr 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.
- 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 5,000 MWD/MTU as a Function of Core Height."
3.3 Table 2B, "Load Follow W(Z) Factors at 12,000 and 22,000 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 "Diablo Canyon Unit 1 Cycle 15 Final Reload Evaluation,"
April, 2007.
6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August, 1994.
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PACIFIC GAS AND ELECTRIC COMPANY NUMIBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 6 OF 12 UNIT 1 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15
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TABLE 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Burnup in FQ Margin (MWD/MTU) 150 2.05 313 2.32 475 2.56 638 2.76 801 2.88 963 2.93 1126 2.88 1289 2.75 1451 2.54 1614 2.26 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.
(
FIOUUCOO.doa 04B 0509.0824
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 7 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 TABLE 2A: Load Follow W(Z) Factors at 150 and 5000 MWD/MTU as a Function of Core Height HEIGHT 150 MWD/MTU HEIGHT 5000 MWD/MTU (FEET) W(Z) (FEET) W(Z)
- 0.0000 1.4014 *0.0000 1.4209
- 0.2000 1.3937 *0.2000 1.4182
- 0.4000 1.3843 *0.4000 1.4120
- 0.6000 1.3740 *0.6000 1.4037
- 0.8000 1.3628 *0.8000 1.3930 1.0000 1.3496 1.0000 1.3797 1.2000 1.3340 1.2000 1.3637 1.4000 1.3168 1.4000 1.3456 1.6000 1.2986 1.6000 1.3259 1.8000 1.2795 1.8000 1.3048 2.0000 1.2597 2.0000 1.2829 2.2000 1.2396 2.2000 1.2602 2.4000 1.2190 2.4000 1.2373 2.6000 1.1983 2.6000 1.2145 2.8000 1.1827 2.8000 1.1908 3.0000 1.1747 3.0000 1.1739 3.2000 1.1713 3.2000 1.1643 3.4000 1.1672 3.4000 1.1582 3.6000 1.1620 3.6000 1.1587 3.8000 1.1592 3.8000 1.1587 4.0000 1.1582 4.0000 1.1575 4.2000 1.1571 4.2000 1.1558 4.4000 1.1551 4.4000 1.1533 4.6000 1.1524 4.6000 1.1499 4.8000 1.1489 4.8000 1.1459 5.0000 1.1451 5.0000 1.1410 5.2000 1.1396 5.2000 1.1357 5.4000 1.1347 5.4000 1.1296 5.6000 1.1412 5.6000 1.1219 5.8000 1.1530 5.8000 1.1228
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 8 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1
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TABLE 2A: Load Follow W(Z) Factors at 150 and 5000 MWD/MTU as a Function of Core Height (Continued)
HEIGHT 150 MWD/MTU HEIGHT 5000 MWD/MTU (FEET) W(Z) (FEET) W(Z) 6.0000 1.1670 6.0000 1.1343 6.2000 1.1824 6.2000 1.1507 6.4000 1.1964 6.4000 1.1664 6.6000 1.2091 6.6000 1.1810 6.8000 1.2205 6.8000 1.1945 7.0000 1.2302 7.0000 1.2064 7.2000 1.2382 7.2000 1.2169 7.4000 1.2446 7.4000 1.2259 7.6000 1.2488 7.6000 1.2329 7.8000 1.2505 7.8000 1.2376 8.0000 1.2493 8.0000 1.2399 8.2000 1.2454 8.2000 1.2395 8.4000 1.2384 8.4000 1.2362
(
8.6000 1.2275 8.6000 1.2294 8.8000 1.2184 8.8000 1.2252 9.0000 1.2205 9.0000 1.2274 9.2000 1.2350 9.2000 1.2455 9.4000 1.2513 9.4000 1.2662 9.6000 1.2677 9.6000 1.2865 9.8000 1.2846 9.8000 1.3058 10.0000 1.3001 10.0000 1.3230 10.2000 1.3103 10.2000 1.3360 10.4000 1.3150 10.4000 1.3439 10.6000 1.3250 10.6000 1.3513 10.8000 1.3434 10.8000 1.3606 11.0000 1.3594 11.0000 1.3640
- 11.2000 1.3649 '11.2000 1.3611
- 11.4000 1.3685 *11.4000 1.3690
- 11.6000 1.3611 "11.6000 1.3686
- 11.8000 1.3412 "11.8000 1.3562
- 12.0000 1.3243 *12.0000 1.3468
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 9 OF 12
( TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 TABLE 2B: Load Follow W(Z) Factors at 12000 and 22000 MWD/MTU as a Function of Core Height HEIGHT 12000 MWD/MTU HEIGHT 22000 MWD/MTU (FEET) W(Z) (FEET) W(Z)
- 0.0000 1.3147 *0.0000 1.3623
- 0.2000 1.3129 *0.2000 1.3513
- 0.4000 1.3112 *0.4000 1.3404
- 0.6000 1.3095 *0.6000 1.3303
- 0.8000 1.3047 *0.8000 1.3214 1.0000 1.2972 1.0000 1.3104 1.2000 1.2877 1.2000 1.2970 1.4000 1.2771 1.4000 1.2828 1.6000 1.2658 1.6000 1.2683 1.8000 1.2538 1.8000 1.2535 2.0000 1.2413 2.0000 1.2383 2.2000 1.2284 2.2000 1.2229 2.4000 1.2151 2.4000 1.2071 2.6000 1.2018 2.6000 1.1911 2.8000 1.1869 2.8000 1.1740 3.0000 1.1799 3.0000 1.1599 3.2000 1.1789 3.2000 1.1591 3.4000 1.1761 3.4000 1.1738 3.6000 1.1770 3.6000 1.1882 3.80QO 1.1785 3.8000 1.2013 4.0000 1.1796 4.0000 1.2130 4.2000 1.1797 4.2000 1.2229 4.4000 1.1789 4.4000 1.2308 4.6000 1.1771 4.6000 1.2367 4.8000 1.1742 4.8000 1.2412 5.0000 1.1708 5.0000 1.2432 5.2000 1.1651 5.2000 1.2482 5.4000 1.1614 5.4000 1.2716 5.6000 1.1751 5.6000 1.2930 5.8000 1.1907 5.8000 1.3114
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 10 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT I TABLE 2B: Load Follow W(Z) Factors at 12000 and 22000 MWD/MTU as a Function of Core Height (Continued)
HEIGHT 12000 MWD/MTU HEIGHT 22000 MWD/MTU (FEET) W(Z) (FEET) W(Z) 6.0000 1.2028 6.0000 1.3277 6.2000 1.2143 6.2000 1.3411 6.4000 1.2239 6.4000 1.3518 6.6000 1.2317 6.6000 1.3596 6.8000 1.2375 6.8000 1.3641 7.0000 1.2414 7.0000 1.3657 7.2000 1.2436 7.2000 1.3643 7.4000 1.2434 7.4000 1.3593 7.6000 1.2407 7.6000 1.3506 7.8000 1.2354 7.8000 1.3379 8.0000 1.2274 8.0000 1.3213 8.2000 1.2166 8.2000 1.3008 8.4000 1.2041 8.4000 1.2765
(
8.6000 1.1939 8.6000 1.2513 8.8000 1.1857 8.8000 1.2399 9.0000 1.1868 9.0000 1.2364 9.2000 1.2042 9.2b 1.2294.
9.4000 1.2312 9.4000 1.2278 9.6000 1.2563 .9.6000 1.2375 9.8000 1.2788 9.8000 1.2581 10.0000 1.3003 10.0000 1.2807 10.2000 1.3201 10.2000 1.3012 10.4000 1.3377 10.4000 1.3205 10.6000 1.3525 10.6000 1.3382 10.8000 1.3660 10.8000 1.3553 11.0000 1.3737 11.0000 1.3676 "11.2000 1.3729 "11.2000 1.3723
- 11.4000 1.3699 *11.4000 1.3746 "11.6000 1.3559 "11.6000 1.3642
- 11.8000 1.3296 "11.8000 1.3399
- 12.0000 1.3062 "12.0000 1.3188
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 0 PAGE 11 OF 12 TITLE: COLR for Diablo Canyon Unit I Cycle 15 UNIT 1 225
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0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power FIGURE 1: Control Bank Insertion Limits Versus Rated Thermal Power FIOUUCOO.doa 04B 0509.0824
Enclosure 2 PG&E Letter DCL-07-060 CORE OPERATING LIMITS REPORT (COLR)
DIABLO CANYON POWER PLANT UNIT 1, CYCLE 15, REVISION 1 (12 Pages)
EFFECTIVE DATE MAY 25, 2007
- UNCONTROLLED PROCEDUE-D NTUET PERFORM WORK or ISSUE FOR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 NUCLEAR POWER GENERATION REVISION 1 DIABLO CANYON POWER PLANT PAGE 1 OF 12 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 105/25/07 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 15 has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.5.
The Technical Specifications affected by this report are listed below:
3.1.1 - Shutdown Margin (MODE 2 with kff < 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 - F N 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 k1%< 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.
2.2 Shutdown Margin (SDM) (TS 3.1.4, 3.1.5, 3.1.6)
The SDM for MODE 1 and MODE 2 with kff_> 1.0 is:
2.2.1 The shutdown margin shall be greater than or equal to 1.6% Ak/k.
F10UUCO1.DOC 04B 0525.1527
UNCONTROLLED _PROEDURE -DO NOT USE' TO E#R'FORM WORK or ISSUE FOR tmE PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 2 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 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 .9 x10-4 Ak/k/ 0 F for all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.
2.3.2 The MTC 300 ppm surveillance limit is -3.0x104 Ak/k/0 F (all rods withdrawn, RATED THERMAL POWER condition).
2.3.3 The MTC 60 ppm surveillance limit is -3.72x104 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)
F T 2.6.1 FQ (Z)< Q *K(Z) for P > 0.5 P
FRTP FQ (Z)<Q- *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 bumups through the end of full power reactivity plus a power coast down of up to 1000 MWD/MTU.
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 W(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.
F1OUUCO1.DOC 04B 0525.0327
UNCONTROLLED PROCEDURE DO0, NOTLUSE TO PERFORM WORK orJISSUE FOR USE~
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 3 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 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:
c FR* *K(Z)
F C (Z)
Q< Q P for P > 0.5 cFQRrh *K(Z)
F Q(Z) for P__ 0.5 0.5 W Fr F (Z) < Q *K(Z) for P > 0.5 Q P RTP FW* (Z) _*.5F *K(Z) for P__ 0.5 Q 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 Q F 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.
F RTP and K(Z) are specified in 2.6.1 and W(Z) is specified in 2.6.2.
Q F10UUCO.LDOC 04B 0525.0327
UNOTOLDPOEUE-D NOTUSE T POFRMWRK orISSUE FORf USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 4 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F M (TS 3.2.2)
FN <_FRTP *[l +PFH * (l1-P)]
where:
THERMAL POWER P =
RATED THERMAL POWER FNAH
= 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 PFm = 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 N, shall be calculated by the following formula:
UFA =1.0+ UAH 100.0 where: UAH = Uncertainty for enthalpy rise as defined in equation (5-19) in Reference 6.2 and F RTP Ae = 1.65 for PDMS (in the above Section 2.7 equation). i 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:
UF= ] .O+ U Q *U UFQ .0100.0),*U where: UQ = Uncertainty for power peaking factor as defined in equation (5-19) in Reference 6.2.
U, = Engineering uncertainty factor
= 1.03 If the PDMS is inoperable, the Nuclear Enthalpy Rise Hot Channel Factor, F NI 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.
FIOUUCO1 .DOC 04B 0525.0327
UNCONTROLLED PROCQEDUlRE - DO NOT USET PERFORM WORK oriSSU'E FOR USE`~
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 5 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 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.
- 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 5,000 MWD/MTU as a Function of Core Height."
3.3 Table 2B, "Load Follow W(Z) Factors at 12,000 and 22,000 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 "Diablo Canyon Unit 1 Cycle 15 Final Reload Evaluation, Revision 1,"
May, 2007.
6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August, 1994.
F10UUCO0.DOC 04B 0525.0327
UNCONfTROLLED PROCEDU&E - DO NOT USE7TPERF7ORMI W6RK or ISSUE FOR~ USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 6 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT I TABLE 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Burnup in FQ Margin (MWD/MTU) 0 150 2.05 2.05 I
313 2.32 475 2.56 638 2.76 801 2.88 963 2.93 1126 2.88 1289 2.75 1451 2.54 1614 2.26 1777 2.00 I
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.
F1OUUCO1 .DOC 04B 0525.0327
UNCONRLE DiOCEDJRE - DO NOfT USETO PERFORM WORK or ISSUE OR USE~
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 7 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 TABLE 2A: Load Follow W(Z) Factors at 150 and 5000 MWD/MTU as a Function of Core Height HEIGHT 150 MWD/MTU HEIGHT 5000 MWD/MTU (FEET) W(Z) (FEET) W(Z)
- 0.0000 1.4014 *0.0000 1.4209
- 0.2000 1.3937 *0.2000 1.4182
- 0.4000 1.3843 *0.4000 1.4120
- 0.6000 1.3740 *0.6000 1.4037
- 0.8000 1.3628 *0.8000 1.3930 1.0000 1.3496 1.0000 1.3797 1.2000 1.3340 1.2000 1.3637 1.4000 1.3168 1.4000 1.3456 1.6000 1.2986 1.6000 1.3259 1.8000 1.2795 1.8000 1.3048 2.0000 1.2597 2.0000 1.2829 2.2000 1.2396 2.2000 1.2602 2.4000 1.2190 2.4000 1.2373 2.6000 1.1983 2.6000 1.2145 2.8000 1.1827 2.8000 1.1908 3.0000 1.1747 3.0000 1.1739 3.2000 1.1713 3.2000 1.1643 3.4000 1.1672 3.4000 1.1582 3.6000 1.1620 3.6000 1.1587 3.8000 1.1592 3.8000 1.1587 4.0000 1.1582 4.0000 1.1575 4.2000 1.1571 4.2000 1.1558 4.4000 1.1551 4.4000 1.1533 4.6000 1.1524 4.6000 1.1499 4.8000 1.1489 4.8000 1.1459 5.0000 1.1451 5.0000 1.1410 5.2000 1.1396 5.2000 1.1357 5.4000 1.1347 5.4000 1.1296 5.6000 1.1412 5.6000 1.1219 5.8000 1.1530 5.8000 1.1228
- Topand Bottom 8% Excluded F1OUUCO1.DOC 04B 0525.0327
! I ý, ; ?17j4,
<UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WOIor ISSUE' FOR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 8 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 TABLE 2A: Load Follow W(Z) Factors at 150 and 5000 MWD/MTU as a Function of Core Height (Continued)
HEIGHT 150 MWD/MTU HEIGHT 5000 MWD/MTU (FEET) W(Z) (FEET) W(Z) 6.0000 1.1670 6.0000 1.1343 6.2000 1.1824 6.2000 1.1507 6.4000 1.1964 6.4000 1.1664 6.6000 1.2091 6.6000 1.1810 6.8000 1.2205 6.8000 1.1945 7.0000 1.2302 7.0000 1.2064 7.2000 1.2382 7.2000 1.2169 7.4000 1.2446 7.4000 1.2259 7.6000 1.2488 7.6000 1.2329 7.8000 1.2505 7.8000 1.2376 8.0000 1.2493 8.0000 1.2399 8.2000 1.2454 8.2000 1.2395 8.4000 1.2384 8.4000 1.2362 8.6000 1.2275 8.6000 1.2294 8.8000 1.2184 8.8000 1.2252 9.0000 1.2205 9.0000 1.2274 9.2000 1.2350 9.2000 1.2455 9.4000 1.2513 9.4000 1.2662 9.6000 1.2677 9.6000 1.2865 9.8000 1.2846 9.8000 1.3058 10.0000 1.3001 10.0000 1.3230 10.2000 1.3103 10.2000 1.3360 10.4000 1.3150 10.4000 1.3439 10.6000 1.3250 10.6000 1.3513 10.8000 1.3434 10.8000 1.3606 11.0000 1.3594 11.0000 1.3640
- 11.2000 1.3649 "11.2000 1.3611
- 11.4000 1.3685 "11.4000 1.3690
- 11.6000 1.3611 "11.6000 1.3686
- 11.8000 1.3412 *11.8000 1.3562
- 12.0000 1.3243 *12.0000 1.3468
- Top and Bottom 8% Excluded F1OUUCO1.DOC 04B 0525.0327
~UNCONTROLLED PROCEDURE-~DO NOT USE TO PERFORM WORKo ISSUE FOR UE*"
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 9 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 TABLE 2B: Load Fo~llow W(Z) Factors at 12000 and 22000 MWD/MTU as a Function of Core Height HEIGHT 12000 MWD/MTU HEIGHT 22000 MWD/MTU (FEET) W(Z) (FEET) W(Z)
- 0.0000 1.3147 *0.0000 1.3623
- 0.2.000 1.3129 *0.2000 1.3513
- 0.4000 1.3112 *0.4000 1.3404
- 0.6000 1.3095 *0.6000 1.3303
- 0.8000 1.3047 *0.8000 1.3214 1.0000 1.2972 1.0000 1.3104 1.2000 1.2877 1.2000 1.2970 1.4000 1.2771 1.4000 1.2828 1.6000 1.2658 1.6000 1.2683 1.8000 1.2538 1.8000 1.2535 2.0000 1.2413 2.0000 1.2383 2.2000 1.2284 2.2000 1.2229 2.4000 1.2151 2.4000 1.2071 2.6000 1.2018 2.6000 1.1911 2.8000 1.1869 2.8000 1.1740 3.0000 1.1799 3.0000 1.1599 3.2000 1.1789 3.2000 1.1591 3.4000 1.1761 3.4000 1.1738 3.6000 1.1770 3.6000 1.1882 3.8000 1.1785 3.8000 1.2013 4.0000 1.1796 4.0000( 1.2130 4.2000 1.1797 4.2000 1.2229 4.4000 1.1789 4.4000 1.2308 4.6000 1.1771 4.6000 1.2367 4.8000 1.1742 4.8000 1.2412 5.0000 1.1708 5.0000 1.2432 5.2000 1.1651 5.2000 1.2482 5.4000 1.1614 5.4000 1.2716 5.6000 1.1751 5.6000 1.2930 5.8000 1.1907 5.8000 1.3114
- Top and Bottom 8% Excluded F1OUUCO1.DOC 04B 0525.0327
UNCONTROLLED PROCEDURE~ -DO NOT US OPROMWOKo SU O USE `1 PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 10 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 TABLE 2B: Load Follow W(Z) Factors at 12000 and 22000 MWD/MTU as a Function of Core Height (Continued)
HEIGHT 12000 MWD/MTU HEIGHT 22000 MWD/MTU (FEET) W(Z) (FEET) W(Z) 6.0000 1.2028 6.0000 1.3277 6.2000 1.2143 6.2000 1.3411 6.4000 1.2239 6.4000 1.3518 6.6000 1.2317 6.6000 1.3596 6.8000 1.2375 6.8000 1.3641 7.0000 1.2414 7.0000 1.3657 7.2000 1.2436 7.2000 1.3643 7.4000 1.2434 7.4000 1.3593 7.6000 1.2407 7.6000 1.3506 7.8000 1.2354 7.8000 1.3379 8.0000 1.2274 8.0000 1.3213 8.2000 1.2166 8.2000 1.3008 8.4000 1.2041 8.4000 1.2765 8.6000 1.939 8.6000 1.2513 8.8000 1.1857 8.8000 1.2399 9.0000 1.1868 9.0000 1.2364 9.2000 1.2042 9.2000 1.2294 9.4000 1.2312 9.4000 1.2278 9.6000 1.2563 9.6000 1.2375 9.8000 1.2788 9.8000 1.2581 10.0000 1.3003 10.0000 1.2807 10.2000 1.3201. 10.2000 1.3012 10.4000 1.3377 10.4000 1.3205 10.6000 1.3525 10.6000 1.3382 10.8000 1.3660 10.8000 1.3553 11.0000 1.3737 11.0000 1.3676 "11.2000 1.3729 "11.2000 1.3723 "11.4000 1.3699 "11.4000 1.3746 "11.6000 1.3559 "11.6000 1.3642
- 11.8000 1.3296 *11.8000 1.3399
- 12.0000 1.3062 *12.0000 1.3188
- Top and Bottom 8% Excluded FIOUUC01.DOC 04B 0525.0327
- UNCONTROLLED PROCEDURE - DO NOTLUSE>TO PEýýfORM WORK or ISSUE FOR7t USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 11 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 225 - .I I I I
- ----17 2-6 25 -,-
--. - - 8, --. -. - --- .
200 BANKB - -- -- --
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- -... 2 .. .s--- Valid for Fully Withdrawn Rod 11...2907 411--
IPositions:
1141
>225 StepssAd<3 An czi
, I,I I - I I I, I ,
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 FI0UUCO1.DOC 04B 0525.0327
UNCONT ROLLED PROCEDURE - DONOT USE TO PERFORM , WORK ISSUE FR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-15 DIABLO CANYON POWER PLANT REVISION 1 PAGE 12 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 15 UNIT 1 120 100 80 L-l-
0 0* 60 E
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 F10UUCO0.DOC 04B 0525.0327