DCL-05-141, Core Operating Limits Report Unit 1, Cycle 14

From kanterella
Jump to navigation Jump to search
Core Operating Limits Report Unit 1, Cycle 14
ML053490110
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 12/02/2005
From: Becker J
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-05-141
Download: ML053490110 (14)
v • d • e


Text

Pacific Gas and Electric Company James R.Becker Diablo Canyon Power Plant Vice President-Diablo Canyon PO. Box 56 Operations and Station Director Avila Beach, CA 93424 805.545.3462 December 2, 2005 Fax: 805.545.4234 PG&E Letter DCL-05-141 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Diablo Canyon Unit I Core Operating Limits Report Unit 1. Cycle 14

Dear Commissioners and Staff:

In accordance with Diablo Canyon Power Plant Technical Specification 5.6.5.d, enclosed is the Core Operating Limits Report for Unit 1, Cycle 14.

ddm/2254/A0606639 Enclosure cclenc: 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 Caltaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

Enclosure PG&E Letter DCL-05-141 CORE OPERATING LIMITS REPORT (COLR)

DIABLO CANYON POWER PLANT UNIT 1, CYCLE 14, REVISION 0 (12 Pages)

EFFECTIVE DATE NOVEMBER 16, 2005

      • ISSUED FOR USE BY: DATE:_.__ EXPIRES:____

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR1-14 NUCLEAR POWER GENERATION REVISION 0 DIABLO CANYON POWER PLANT PAGE 1 OF 12 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR Fo,r Diablo Canyon Unit I Cycle 14 1 11/16/05 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 14 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 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 - FAHN 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 keff < 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 0F.

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 keff Ž1.0 is:

2.2.1 The shutdown margin shall be greater than or equal to 1.6% Ak/k.

C9GSXDOO.DOA 04B 1 115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 2 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 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 -3.9x10-4 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.OxlO-4 Ak/k/0 F (all rods withdrawn, RATED THERMAL POWER condition).

2.3.3 The MTC 60 ppm surveillance limit is -3.72x10-4 Ak/k/0 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)< L9 *K(Z) forP>0.5 P

F RT*

EQ,(Z)<? *K(Z) forP *0.5 0.5 THERMAL POWER where: P =

RATED THERMAL POWER FRTP = 2.58 Q

K(Z)= 1.0 j 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 14 burnups through the end of full power reactivity plus a power coast down of up to 1000 MWD/MT`L.

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.

NOTE: The W(Z) data is appropriate for use only if the predicted axial offset is within +/-3% of the measured value.

C9GSXDOO.DOA 04B 1115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 3 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 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:

F (Z)"< K( for P > 0.5 Q P F Q(z)< F RTP *K(Z) fr*.

for P s 0.5 Q 0.5 (Z)< FQ *K(Z) for P > 0.5 Q p W uRTP FQ(Z) *-'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 K(Z) is the normalized FQ(Z) as a function of core height P is the relative THERMAL POWER, and 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 F W(Z) is the total peaking factor, F (Z), multiplied by W(Z) which Q t gives the maximum FQ(Z) calculated to occur in normal operation.

C9GSXDOO.DOA 04B 1115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 4 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 UNIT 1 2.7 Nuclear Enthalpy Rise Hot Channel Factor - F i (TS 3.2.2)

FN < FA *[1+PFAH*(1-P))

where:

_ THERMAL POWER P = _ _ __ _

RATED THERAIAL POWER FNAll = Measured values of FN AHl obtained by using the moveable incore detectors to obtain a power distribution map.

FRTP = 1.59 (includes the 4% measurement uncertainty)

All PFAH = 0.3 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:

UF, =1 U0+A 100.0 where: UAH = Uncertainty for enthalpy rise as defined in equation (5-19) in Reference 6.2 and FRTP All = 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:

UFQ =( 100.0 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 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.

C9GSXDOO.DOA 04B 1115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 5 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 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 4,000 MWD/MTU as a Function of Core Height."

3.3 Table 2B, "Load Follow W(Z) Factors at 10,000 and 17,800 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 PCT-05-52, "Diablo Canyon Unit 1 Cycle 14 Final Reload Evaluation,"

July 25, 2005.

6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August, 1994.

C9GSXDOO.DOA 04B 1115.1003

PACIFIC Gj S AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 6 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 UNIT 1 TABLE 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Burnup in FQ Margin (MWD/MTU) 476 2.00 638 2.06 801 2.35 964 2.59 1127 2.80 1289 2.97 1452 3.09 1615 3.17 1778 3.16 1940 3.09 2103 2.97 2266 2.80 2429 2.58 2591 2.33 2754 2.06 2917 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.

C9GSXDOO.DOA 04B X1115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 7 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 UNIT 1 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 1.0000 *0.0000 1.0000
  • 0.2000 1.0000 *0.2000 1.0000
  • 0.4000 1.0000 *0.4000 1.0000
  • 0.6000 1.0000 *0.6000 1.0000
  • 0.8000 1.0000 *0.8000 1.0000
  • 1.0000 1.0000 *1.0000 1.0000
  • 1.2000 1.0000 *1.2000 1.0000
  • 1.4000 1.0000 *1.4000 1.0000
  • 1.6000 1.0000 *1.6000 1.0000
  • 1.8000 1.0000 *1.8000 1.0000 2.0000 1.2902 2.0000 1.3067 2.2000 1.2681 2.2000 1.2813 2.4000 1.2458 2.4000 1.2568 2.6000 1.2235 2.6000 1.2371 2.8000 1.1993 2.8000 1.2176 3.0000 1.1835 3.0000 1.1978 3.2000 1.1757 3.2000 1.1836 3.4000 1.1695 3.4000 1.1774 3.6000 1.1696 3.6000 1.1709 3.8000 1.1694 3.8000 1.1693 4.0000 1.1681 4.0000 1.1685 4.2000 1.1662 4.2000 1.1662 4.4000 1.1633 4.4000 1.1632 4.6000 1.1596 4.6000 1.1594 4.8000 1.1550 4.8000 1.1547 5.0000 1.1503 5.0000 1.1492 5.2000 1.1435 5.2000 1.1432 5.4000 1.1377 5.4000 1.1363 5.6000 1.1477 5.6000 1.1295 5.8000 1.1627 5.8000 1.1345
  • Top and Bottom 15% Excluded C9GSXDOO.DOA 04B 1115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 8 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 UNIT 1 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/MITU (FEET) W(Z) (FEET) W(Z) 6.0000 1.1764 6.0000 1.1482 6.2000 1.1893 6.2000 1.1627 6.4000 1.2010 6.4000 1.1765 6.6000 1.2114 6.6000 1.1891 6,8000 1.2203 6.8000 1.2005 7.0000 1.2274 7.0000 1.2102 7.2000 1.2329 7.2000 1.2183 7.4000 1.2366 7.4000 1.2250 7.6000 1.2380 7.6000 1.2295 7.8000 1.2369 7.8000 1.2316 8.0000 1.2331 8.0000 1.2312 8.2000 1.2263 8.2000 1.2281 8.4000 1.2165 8.4000 1.2221 8.6000 1.2056 8.6000 1.2119 8.8000 1.2011 8.8000 1.2091 9.0000 1.2019 9.0000 1.2141 9.2000 1.2088 9.2000 1.2333 9.4000 1.2122 9.4000 1.2554 9.6000 1.2202 9.6000 1.2773 9.8000 1.2403 9.8000 1.2981 10.0000 1.2660 10.0000 1.3165

  • 10.2000 1.0000 *10.2000 1.0000
  • 10.4000 1.0000 *10.4000 1.0000
  • 10.6000 1.0000 *10.6000 1.0000
  • 10.8000 1.0000 *10.8000 1.0000
  • I 1.0000 1.0000
  • 11.0000 1.0000
  • 11.2000 1.0000 *11.2000 1.0000
  • 11.4000 1.0000
  • 11.4000 1.0000
  • 11.6000 1.0000 *11.6000 1.0000
  • 11.8000 1.0000 *11.8000 1.0000
  • 12.0000 1.0000 *12.0000 1.0000
  • Top and Bottom 15% Excluded C9GSXDOO.DOA 04B I1115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 9 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 UNIT 1 TABLE 2B: Load Follow W(Z) Factors at 10000 and 17800 MWD/MTU as a Function of Core Height HEIGHT 10000 MWD/MTU HEIGHT 17800 MWD/MTU (FEET) W(Z) (FEET) W(Z)

  • 0.0000 1.0000 *0.0000 1.0000
  • 0.2000 1.0000 *0.2000 1.0000
  • 0.4000 1.0000 *0.4000 1.0000
  • 0.6000 1.0000 *0.6000 1.0000
  • 0.8000 1.0000 *0.8000 1.0000
  • 1.0000 1.0000 *1.0000 1.0000
  • 1.2000 1.0000 *1.2000 1.0000
  • 1.4000 1.0000 *1.4000 1.0000
  • 1.6000 1.0000 *1.6000 1.0000
  • 1.8000 1.0000 *1.8000 1.0000 2.0000 1.2490 2.0000 1.2311 2.2000 1.2336 2.2000 1.2163 2.4000 1.2180 2.4000 1.2013 2.6000 1.2021 2.6000 1.1861 2.8000 1.1850 2.8000 1.1698 3.0000 1.1726 3.0000 1.1563 3.2000 1.1678 3.2000 1.1544 3.4000 1.1666 3.4000 1.1672 3.6000 1.1661 3.6000 1.1828 3.8000 1.1672 3.8000 1.1974 4.0000 1.1685 4.0000 1.2105 4.2000 1.1682 4.2000 1.2219 4.4000 1.1670 4.4000 1.2315 4.6000 1.1668 4.6000 1.2389 4.8000 1.1669 4.8000 1.2447 5.0000 1.1673 5.0000 1.2470 5.2000 1.1658 5.2000 1.2508 5.4000 1.1651 5.4000 1.2654 5.6000 1.1832 5.6000 1.2884 5.8000 1.2032 5.8000 1.3102
  • Top and Bottom 15% Excluded C9GSXDOO.DOA 04B I1115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 10 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 UNIT 1 TABLE 2B: Load Follow W(Z) Factors at 10000 and 17800 MWD/MTU as a Function of Core Height (Continued)

HEIGHT 10000 MWD/MTU HEIGHT 17800 MWD/MTU (FEET) W(Z) (FEET) W(Z) 6.0000 1.2197 6.0000 1.3284 6.2000 1.2354 6.2000 1.3443 6.4000 1.2491 6.4000 1.3571 6.6000 1.2608 6.6000 1.3669 6.8000 1.2703 6.8000 1.3734 7.0000 1.2777 7.0000 1.3767 7.2000 1.2827 7.2000 1.3768 7.4000 1.2854 7.4000 1.3733 7.6000 1.2851 7.6000 1.3658 7.8000 1.2818 7.8000 1.3543 8.0000 1.2753 8.0000 1.3387 8.2000 1.2656 8.2000 1.3192 8.4000 1.2527 8.4000 1.2958 8.6000 1.2352 8.6000 1.2674 8.8000 1.2232 8.8000 1.2433 9.0000 1.2226 9.0000 1.2281 9.2000 1.2301 9.2000 1.2271 9.4000 1.2424 9.4000 1.2477 9.6000 1.2663 9.6000 1.2734 9.8000 1.2919 9.8000 1.2981 10.0000 1.3140 10.0000 1.3215

  • 10.2000 1.0000 *10.2000 1.0000
  • 10.4000 1.0000 *10.4000 1.0000
  • 10.6000 1.0000 *10.6000 1.0000
  • 10.8000 1.0000 *10.8000 1.0000
  • 1.0000 1.0000 *1 1.0000 1.0000
  • 11.2000 1.0000 *11.2000 1.0000
  • 11.4000 1.0000 *11.4000 1.0000
  • 11.6000 1.0000 *11.6000 1.0000
  • 11.8000 1.0000 *11.8000 1.0000
  • 12.0000 1.0000 *12.0000 1.0000
  • Top and Bottom 15% Excluded C9GSXDOO.DOA 04B I1115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 11 OF 12 TITLE: COLR For Diablo Canyon Unit 1 Cycle 14 UNIT 1 225 200 175 0-c 150 C) 125 0

0~ 100 1 1 , -- I ...I (U - -- - r--- - -

ro 75 2l- -- - - - --- - - - - - --- - - --

- -2 - - - ---------

yt

--- r -- --------- --------

/ -'-- -- ---------- ~~ ------ r------ -~----- ----- ----- ~~~;-------- /I~ ~ n-- ~~ '~~~~~~~~~- ~~~~~

50

- ------ -- -- - - - -I 25

. . . , . Valid; for Fully Aithdrawn1 W Rod (0_2-0)-ositons: >225 Step A <23---- ----

S 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 C9GSX]DOO.DOA 04B 11503 1115.1003

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1-14 DIABLO CANYON POWER PLANT REVISION 0 PAGE 12 OF 12 TITLE: COLR For Diablo Canyon Unit I Cycle 14 UNIT 1 120

_ ___ - (-14,1 00) (+

_;10,1 00) _-- ___

100 UNACCEPTABLE - - -- - - NCCEP TABLE OPERATION _ OPERATION 80 S..

0

-W ACCEPTABLE -

0 OPERATION

'R 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 C9GSXDOO.DOA 04B I1115.1003 1

Retrieved from "https://kanterella.com/w/index.php?title=DCL-05-141,_Core_Operating_Limits_Report_Unit_1,_Cycle_14&oldid=2588355"