ML090920409

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Submittal of Core Operating Limits Report
ML090920409
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 03/23/2009
From: Becker J R
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-09-017
Download: ML090920409 (14)
v • d • e


Text

Pacific Gas and Electric CompanyJames R. Becker Site Vice President Diablo Canyon Power Plant Mail Code 104/5/601 P 0. Box 56 Avila Beach, CA 93424 805.545.3462 Internal:

691.3462 Fax: 805.545.6445 March 23, 2009 PG&E Letter DCL-09-017 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 Operating Limits Report for Unit 1 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 1. The COLR has been revised for Unit 1, Cycle 16, consistent with NRC-approved License Amendment 195.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.dd m/2254/50040450 Enclosure cc: Diablo Distribution cc/enc: Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Alan B. Wang, NRR Project Manager 4oo!A member of the STARS (Strategic Teaming and Resource Sharing) ALliance Catlaway

  • Comanche Peak
  • Diabto Canyon
  • Palo Verde
  • San Onofre
  • Wolf Creek Enclosure PG&E Letter DCL-09-017 CORE OPERATING LIMITS REPORT (COLR)DIABLO CANYON POWER PLANT UNIT 1, CYCLE 16, EFFECTIVE DATE MARCH 6, 2009 ISSUED FOR USE BY:__PACIFIC GAS AND ELECTRIC COMPANY NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT CORE OPERATING LIMITS REPORT DATE: EXPIRES:____

NUMBER COLR 1 REVISION 1 PAGE 1 OF 12 UNIT TITLE: COLR for* Diablo Canyon Unit 1 Cycle 16 1 03/06/09 EFFECTIVE DATE PROCEDURE CLASSIFICATION:

QUALITY RELATED 1. CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 16 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)3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits.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 klff < 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 0 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.

I COLR_lulr01.DOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 1 PAGE 2 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 UNIT 1 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 -3.9xl0-4 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 -3.0xl 0 4 Ak/k/°F (all rods withdrawn, RATED THERMAL POWER condition).

2.3.3 The MTC 60 ppm surveillance limit is -3.72xl104 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)FRTP 2.6.1 FQ(Z)<-- *K(Z) forP>0.5 FP FQ(Z)<L.5*K(Z) for P___0.5 0.5 THERMAL POWER where: P =RATED THERMAL POWER FR TP = 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 16 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.COLR luIrODOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 1 PAGE 3 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 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 FT *K(Z)F (Z)< forP>0.5 Q P FC(Z\< FRTP *K(Z)Q() .5 for0P..5 W ' FRTP F (Z) < Q *K(Z) for P > 0.5 Q P FRTP F (Z) 0 Q *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 (Z), multiplied by W(Z) which QQ 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.QI COLR luIrOl.DOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 1 PAGE 4 OF 12 TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 UNIT 1 2.7 Nuclear Enthalpy Rise Hot Channel Factor -F M (TS 3.2.2)FN _<FRTP *[I+ * (1-P)]AH -AH where: THERMAL POWER P =RATED THERMAL POWER FN esrdvle fFN ot FAMeasured values of F N m obtained by using the moveable incore detectors to obtain a power distribution map.F RTP = 1.59 (includes the 4% measurement uncertainty)

AH PFAI = 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, UFAN, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F N shall be calculated by the following formula: UFAH =1.0+ AUl 100.0 where: UQ = Uncertainty for power peaking factor as defined in equation (5-19) in Reference 6.2 and F RTP = 1.65 for PDMS (in the above Section 2.7 AH 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= 1.0+ U° J*Ue 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 AH, 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.COLR luIrOLDOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 NUMBER REVISION PAGE UNIT COLR 1 1 5 OF 12 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 kff 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 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 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" I 4. FIGURES 4.1 Figure 1, "Control Bank Insertion Limits Versus Rated Thermal Power" 4.2 r lgure z, ArL) Limits as a r unction or Rated inermal rower" 5. RECORDS None 6. REFERENCES 6.1 "Diablo Canyon Unit 1 Cycle 16 Final Reload Evaluation," December, 2008 6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August, 1994 COLRIuir01.DOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 NUMBER REVISION PAGE COLR 1 1 6 OF 12 1 UNIT Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Burnup in FQ Margin (MWD/MTU)0 2.01 150 2.01 313 2.33 475 2.57 638 2.69 801 2.64 963 2.41 1126 2.06 1288 2.00 4866 2.00 5029 2.48 5191 2.93 5354 3.39 5517 3.85 5679 4.26 5842 4.55 6005 4.30 6167 4.05 6330 3.80 6493 3.52 6655 3.24 6818 2.96 6980 2.66 7143 2.37 7306 2.07 7468 2.00 18527 2.00 18690 2.03 18852 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.COLRluIrOLDOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 NUMBER COLR 1 REVISION 1 PAGE 7 OF 12 UNIT 1 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height HEIGHT (FEET)*0.0000*0.2000*0.4000*0.6000*0.8000 1.0000 1.2000 1.4000 1.6000 1.8000 2.0000 2.2000 2.4000 2.6000 2.8000 3.0000 3.2000 3.4000 3.6000 3.8000 4.0000 4.2000 4.4000 4.6000 4.8000 5.0000 5.2000 5.4000 5.6000 5.8000 150 MWD/MTU W(Z)1.5977 1.5923 1.5834 1.5722 1.5587 1.5424 1.5234 1.5023 1.4795 1.4553 1.4299 1.4035 1.3765 1.3490 1.3191 1.2987 1.2891 1.2813 1.2755 1.2687 1.2603 1.2508 1.2401 1.2283 1.2155 1.2019 1.1876 1.1726 1.1585 1.1557 HEIGHT (FEET)*0.0000*0.2000*0.4000*0.6000*0.8000 1.0000 1.2000 1.4000 1.6000 1.8000 2.0000 2.2000 2.4000 2.6000 2.8000 3.0000 3.2000 3.4000 3.6000 3.8000 4.0000 4.2000 4.4000 4.6000 4.8000 5.0000 5.2000 5.4000 5.6000 5.8000 4000 MWD/MTU W(Z)1.5792 1.5745 1.5659 1.5548 1.5410 1.5242 1.5043 1.4820 1.4576 1.4315 1.4040 1.3755 1.3463 1.3166 1.2889 1.2674 1.2535 1.2438 1.2342 1.2282 1.2229 1.2158 1.2078 1.1988 1.1889 1.1781 1.1668 1.1546 1.1411 1.1368* Top and Bottom 8% Excluded COLRluIrOLDOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 NUMBER COLR 1 REVISION 1 PAGE 8 OF 12 UNIT 1 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWD/MTU as a Function of Core Height (Continued)

HEIGHT (FEET)6.0000 6.2000 6.4000 6.6000 6.8000 7.0000 7.2000 7.4000 7.6000 7.8000 8.0000 8.2000 8.4000 8.6000 8.8000 9.0000 9.2000 9.4000 9.6000 9.8000 10.0000 10.2000 10.4000 10.6000 10.8000 11.0000'11.2000"11.4000"11.6000*11.8000* 12.0000 150 MWD/MTU W(Z)1.1581 1.1643 1.1693 1.1731 1.1758 1.1770 1.1768 1.1753 1.1719 1.1665 1.1590 1.1491 1.1368 1.1254 1.1131 1.1097 1.1164 1.1370 1.1654 1.1942 1.2207 1.2464 1.2707 1.2928 1.3122 1.3283 1.3425 1.3582 1.3736 1.3882 1.4024 HEIGHT (FEET)6.0000 6.2000 6.4000 6.6000 6.8000 7.0000 7.2000 7.4000 7.6000 7.8000 8.0000 8.2000 8.4000 8.6000 8.8000 9.0000 9.2000 9.4000 9.6000 9.8000 10.0000 10.2000 10.4000 10.6000 10.8000 11.0000"11.2000"11.4000"11.6000"11.8000"12.0000 4000 MWD/MTU W(Z)1.1394 1.1508 1.1608 1.1697 1.1775 1.1838 1.1886 1.1915 1.1924 1.1912 1.1876 1.1817 1.1732 1.1603 1.1545 1.1512 1.1504 1.1709 1.1932 1.2135 1.2300 1.2400 1.2479 1.2581 1.2672 1.2761 1.2873 1.2948 1.2980 1.2974 1.2977* Top and Bottom 8% Excluded COLR luIrOLDOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 NUMBER COLR 1 REVISION 1 PAGE 9 OF 12 UNIT 1 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWD/MTU as a Function of Core Height HEIGHT (FEET)*0.0000*0.2000*0.4000*0.6000*0.8000 1.0000 1.2000 1.4000 1.6000 1.8000 2.0000 2.2000 2.4000 2.6000 2.8000 3.0000 3.2000 3.4000 3.6000 3.8000 4.0000 4.2000 4.4000 4.6000 4.8000 5.0000 5.2000 5.4000 5.6000 5.8000 12000 MWD/MTU W(Z)1.2730 1.2651 1.2556 1.2450 1.2337 1.2203 1.2058 1.1931 1.1841 1.1752 1.1659 1.1566 1.1475 1.1385 1.1278 1.1253 1.1298 1.1321 1.1360 1.1434 1.1515 1.1581 1.1638 1.1684 1.1716 1.1742 1.1748 1.1747 1.1875 1.2063 HEIGHT (FEET)*0.0000*0.2000*0.4000*0.6000*0.8000 1.0000 1.2000 1.4000 1.6000 1.8000 2.0000 2.2000 2.4000 2.6000 2.8000 3.0000 3.2000 3.4000 3.6000 3.8000 4.0000 4.2000 4.4000 4.6000 4.8000 5.0000 5.2000 5.4000 5.6000 5.8000 20000 MWD/MTU W(Z)1.3639 1.3510 1.3365 1.3213 1.3057 1.2876 1.2709 1.2582 1.2447 1.2311 1.2176 1.2039 1.1903 1.1765 1.1619 1.1587 1.1620 1.1694 1.1779 1.1889 1.1996 1.2083 1.2171 1.2265 1.2349 1.2383 1.2467 1.2716 1.2936 1.3124* Top and Bottom 8% Excluded COLRluIrODOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 NUMBER COLR 1 REVISION 1 PAGE 10 OF 12 UNIT 1 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWD/MTU as a Function of Core Height (continued)

HEIGHT (FEET)6.0000 6.2000 6.4000 6.6000 6.8000 7.0000 7.2000 7.4000 7.6000 7.8000 8.0000 8.2000 8.4000 8.6000 8.8000 9.0000 9.2000 9.4000 9.6OOO 9.8000 10.0000 10.2000 10.4000 10.6000 10.8000 11.0000"11.2000"11.4000"11.6000'11.8000"12.0000 ,12000 MWD/MTU W(Z)1.2245 1.2409 1.2555 1.2682 1.2786 1.2870 1.2932 1.2968 1.2974 1.2949 1.2893 1.2802 1.2678 1.2561 1.2571 1.2737 1.2971 1.3178 1.3368 1.3549 1.3723 1.3882 1.4011 1.4095 1.4198 1.4324 1.4423 1.4489 1.4475 1.4378 1.4300 HEIGHT (FEET)6.0000 6.2000 6.4000 6.6000 6.8000 7.0000 7.2000 7.4000 7.6000 7.8000 8.0000 8.2000 8.4000 8.6000 8.8000 9.0000 9.2000 9.4000 9.6000 9.8000 10.0000 10.2000 10.4000 10.6000 10.8000 11.0000"11.2000"11.4000*11.6000*11.8000*12.0000 20000 MWD/MTU W(Z)1.3292 1.3431 1.3542 1.3624 1.3673 1.3693 1.3682 1.3634 1.3548 1.3423.1.3257 1.3052 1.2808 1.2539 1.2466 1.2450 1.2397 1.2365 1.2268 1.2316 1.2519 1.2719 1.2906 1.3080 1.3247 1.3407 1.3555 1.3682 1.3730 1.3694 1.3678* Top and Bottom 8% Excluded 'COLRIulr01.DOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 NUMBER COLR 1 REVISION 1 PAGE 11 OF 12 UNIT 1 C 0 ,-a (0 c.0 0 0 m 225 200 175 150 125 100-75.. .. ...__, -_ I_ ... .. ... .(0.17,225)

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-.: '- -- Positions:

>225 Steps And <23"1 Ses.. ..(029 O)I I--'I -I- T '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 COLRluirOiDOC 04B 0306.1024 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE: COLR for Diablo Canyon Unit 1 Cycle 16 NUMBER REVISION PAGE UNIT COLR 1 1 12 OF 12 1 120 0 ,C I-4-, 0-60 40 20 -10 0 10 20 30 40 50 60 Flux Difference (DELTA I) %Figure 2: AFD Limits as a Function of Rated Thermal Power COLRluIrOlDOC 04B 0306.1024

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