DCL-11-073, Core Operating Limits Report Cycle 17

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Core Operating Limits Report Cycle 17
ML11179A082
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 06/18/2011
From: Welsch J
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-11-073
Download: ML11179A082 (15)
v • d • e


Text

Pacific Gas and Electric Company' James M. Welsch Station Director Diablo Canyon Power Plant Mail Code 104/5/502 P. 0. Box 56 Avila Beach, CA 93424 805.545.3242 Internal: 691.3242 Fax: 805.545.4234 Internet: JMWl@pge.com June 18, 2011 PG&E Letter DCL-1 1-073 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 17

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 17.

There are no new or revised regulatory commitments in this submittal.

If there are any questions regarding the COLR, please contact Mr. Mark Mayer at (805) 545-4674.

Sincerely, m**esMch swh/60024751 Enclosure cc:

Diablo Distribution cc/enc:

Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector James T. Polickoski, NRR Project Manager Alan B. Wang, NRR Project Manager ko(

K(Vi A member of the STARS (Strategic Teaming and Resource Sharing) ALliance CaLlaway

  • Comanche Peak
  • Diablo Canyon
  • PaLo Verde
  • San Onofre e South Texas Project e Wolf Creek

Enclosure PG&E Letter DCL-1 1-073 CORE OPERATING LIMITS REPORTS (COLR)

DIABLO CANYON POWER PLANT UNIT 2, CYCLE 17 EFFECTIVE DATE May 18, 2011

      • ISSUED FOR USE BY:

PACIFIC GAS AND ELECTRIC COMPANY NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT CORE OPERATING LIMITS REPORT DATE:

EXPIRES: _**

NUMBER COLR 2 REVISION 6

PAGE 1 OF 13 UNIT TITLE:

COLR for Diablo Canyon Unit 2 2

05/18/11 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 17 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 kYff< 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-FN

  • ~All 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 I

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COLR for Diablo Canyon Unit 2 NUMBER REVISION PAGE UNIT COLR 2 6

2 OF 13 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 2.2 2.3 2.4 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% 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.

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 -3.9x 10-4 Ak/k/0 F 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 Ak/k/°F (all rods withdrawn, RATED THERMAL POWER condition).

2.2.3 The MTC 60 ppm surveillance limit is -3.72x 10- Ak/k/°F (all rods withdrawn, RATED THERMAL POWER condition).

Shutdown Bank Insertion Limits (TS 3.1.5) 2.3.1 Each shutdown bank shall be withdrawn to at least 225 steps.

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.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 6

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)

FRTP 2.5.1 FQ(Z)<La *K(Z) forP>0.5 P

FRTP Q(Z)<-*.5*K(Z) forP_<O0.5 0.5 THERMAL POWER where: P =

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.

2.5.2 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 Cycle 17 burnups 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 burnup 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 burnup steps.

For W(Z) data at a desired bumup outside of the listed burnup 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 burnup 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 1/P (P > 0.5) or 1/0.5 (P < 0.5), where P is the core relative power during the surveillance, to account for the increase in the FQ(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 (Z) per SR 3.2.1.2. A 2% penalty factor shall be used at all cycle burmups that are outside the range of Table 1.

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PAGE 4 OF 13 TITLE:

COLR for Diablo Canyon Unit 2 UNIT 2

2.5.3 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~TP *K(Z)

FQ (Z) <

forP> 0.5

(

R F*

  • K(Z)

F

_(Z)__ _

for P_* 0.5 Q

0.5 F

(Z) < *

  • K(Z) for P > 0.5 Q

P

<Q(.5 *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.

FRTP and K(Z) are specified in 2.5.1 and W(Z) is specified in 2.5.2.

Q COLR_2u2r06,DOC 04B 0517.0808

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 6 PAGE 5 OF 13 TITLE:

COLR for Diablo Canyon Unit 2 UNIT 2

2.6 Nuclear Enthalpy Rise Hot Channel Factor - FNH (TS 3.2.2)

F i<F RTP *[I + PFn * (l-P)]

AH -AH where:

THERMAL POWER P

= RATED THERMAL POWER FAN

= Measured values of F N obtained by using the moveable incore detectors to AH AH obtain a power distribution map.

FRTP

= 1.586 (prior to including 4% uncertainty)

AH PFA

= 0.3 = Power Factor Multiplier 2.7 Power Distribution Measurement Uncertainty (IS 3.2.1. and TS 3.2.2):

If the PDMS is OPERABLE, the uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F NA, shall be calculated by the following formula:

UFAH =1.0+ UO+

100.0 where:

UAH = 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 RTP = 1.65 for PDMS (in the above Section 2.6 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:

U FQ.0 + U Q )

  • U UFQ=l.0+100.0 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, F H, 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.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 6

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 I 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 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 NF-PGE-1 1-17, Rev. 2,"Diablo Canyon Unit 2 Cycle 17 Reload Evaluation and Core Operating Limits Report, Revision 2", May, 2011 6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August, 1994 COLR_2u2r06.DOC 04B 0517.0808

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

COLR for Diablo Canyon Unit 2 NUMBER REVISION PAGE COLR 2 6

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UNIT 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 2.01 476 2.46 638 2.75 801 2.86 964 2.78 1127 2.54 1289 2.13 1452 2.00 6009 2.00 6172 2.33 6335 2.79 6497 2.69 6660 2.54 6823 2.38 6986 2.21 7148 2.03 7311 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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COLR for Diablo Canyon Unit 2 NUMBER REVISION PAGE UNIT COLR 2 6

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Table 2A: Load Follow W(Z) Factors at 150 and 5000 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) 1.4587 1.4483 1.4375 1.4268 1.4164 1.4043 1.3899 1.3741 1.3574 1.3398 1.3214 1.3025 1.2830 1.2632 1.2433 1.2218 1.2044 1.1977 1.1960 1.1939 1.1906 1.1864 1.1811 1.1750 1.1679 1.1606 1.1513 1.1432 1.1508 1.1597 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 5000 MWD/MTU W(Z) 1.5386 1.5339 1.5252 1.5141 1.5005 1.4837 1.4639 1.4414 1.4168 1.3905 1.3629 1.3343 1.3052 1.2758 1.2465 1.2181 1.1990 1.1937 1.1903 1.1870 1.1831 1.1783 1.1726 1.1660 1.1587 1.1506 1.1421 1.1328 1.1216 1.1214
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COLR for Diablo Canyon Unit 2 NUMBER COLR 2 REVISION 6 PAGE 9 OF 13 UNIT 2

Table 2A: Load Follow W(Z) Factors at 150 and 5000 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) 1.1674 1.1767 1.1844 1.1913 1.1990 1.2063 1.2118 1.2155 1.2174 1.2172 1.2148 1.2102 1.2031 1.1932 1.1829 1.1739 1.1705 1.1768 1.1816 1.1835 1.1846 1.1851 1.1834 1.1791 1.1795 1.1873 1.1971 1.2031 1.2032 1.1962 1.1893 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 5000 MWD/MTU W(Z) 1.1304 1.1407 1.1499 1.1581 1.1653 1.1713 1.1760 1.1792 1.1815 1.1823 1.1812 1.1784 1.1736 1.1654 1.1634 1.1724 1.1872 1.1999 1.2114 1.2242 1.2373 1.2484 1.2576 1.2667 1.2738 1.2798 1.2838 1.2806 1.2782 1.2714 1.2647
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COLR for Diablo Canyon Unit 2 NUMBER COLR 2 REVISION 6 PAGE 10 OF 13 UNIT 2

Table 2B: Load Follow W(Z) Factors at 12000 and 22000 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) 1.2578 1.2567 1.2556 1.2545 1.2505 1.2438 1.2353 1.2258 1.2157 1.2051 1.1942 1.1829 1.1715 1.1602 1.1469 1.1430 1.1440 1.1442 1.1439 1.1440 1.1455 1.1486 1.1504 1.1513 1.1516 1.1501 1.1497 1.1559 1.1696 1.1837 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 22000 MWD/MTU W(Z) 1.2827 1.2861 1.2853 1.2817 1.2752 1.2660 1.2553 1.2442 1.2332 1.2224 1.2117 1.2011 1.1906 1.1802 1.1684 1.1636 1.1645 1.1728 1.1821 1.1939 1.2058 1.2157 1.2239 1.2301 1.2345 1.2366 1.2379 1.2453 1.2661 1.2869
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COLR for Diablo Canyon Unit 2 NUMBER COLR 2 REVISION 6 PAGE 11 OF 13 UNIT 2

Table 2B: Load Follow W(Z) Factors at 12000 and 22000 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 12000 MWD/MTU W(Z) 1.1976 1.2118 1.2242 1.2349 1.2439 1.2508 1.2557 1.2592 1.2605 1.2594 1.2558 1.2494 1.2403 1.2331 1.2315 1.2334 1.2399 1.2436 1.2455 1.2444 1.2433 1.2440 1.2422 1.2410 1.2401 1.2407 1.2427 1.2373 1.2309 1.2182 1.2055 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 22000 MWD/MTU W(Z) 1.3039 1.3192 1.3318 1.3418 1.3491 1.3532 1.3545 1.3534 1.3490 1.3411 1.3295 1.3145 1.2960 1.2739 1.2587 1.2492 1.2372 1.2241 1.2223 1.2236 1.2261 1.2294 1.2355 1.2464 1.2651 1.2865 1.3015 1.3069 1.3003 1.2800 1.2599
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COLR for Diablo Canyon Unit 2 NUMBER COLR 2 REVISION 6

PAGE 12 OF 13 UNIT 2

co (0

0.

9L C'

M co 225 200 175 150 125 100 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 COLR_2u2r06.DOC 04B 0517.0808

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COLR for Diablo Canyon Unit 2 NUMBER COLR 2 REVISION 6

PAGE 13 OF 13 UNIT 2

120 100 80 I-0 I-C" nM 60 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 COLR_2u2r06.DOC 04B 0517.0808

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