NL-10-1213, Cycle 15 Version 3 Core Operating Limits Report

Cycle 15 Version 3 Core Operating Limits Report

ML101810068
Person / Time
Site:	Vogtle
Issue date:	06/28/2010
From:	Ajluni M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-10-1213
Download: ML101810068 (14)

Text

Southem Nuclear Operating Company, Inc.

"DOD June 28, 2010 SOUTHERN A COMPANY Docket Nos.: 50-425 NL-10-1213 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant-Unit 2 Cycle 15 Version 3 Core Operating Limits Report Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5d, Southern Nuclear Operating Company submits the enclosed Core Operating Limits Report (COLR) for Vogtle Electric Generating Plant (VEGP) Unit 2 Cycle 15 Version 3. Changes were made to the previous COLR to revise the Fq(z) penalty factor and the W(z} values (Tables 1 and 2 respectively).

This letter contains no NRC commitments. If there are any questions, please contact Jack Stringfellow at (205)992-7037.

Respectfully submitted, M. J. Ajluni Manager - Nuclear Licensing MJA IPAH/lac

Enclosure:

Core Operating Limits Report VEGP Unit 2 Cycle 15, Version 3

U.S. Nuclear Regulatory commission Log: NL-10-1213 Page 2 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President (w/o enclosure)

Mr. T. E. Tynan, Vice President - Vogtle Ms. P. M. Marino, Vice President - Engineering (w/o enclosure)

RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Vogtle Mr. M. Cain, Senior Resident Inspector - Vogtle Mr. P. Boyle, NRC Project Manager State of Georgia Mr. C. Clark, Commissioner-Department of Natural Resources

Vogtle Electric Generating Plant - Unit 2 Cycle 15 Core Operating Limits Report Enclosure Core Operating Limits Report VEGP Unit 2 Cycle 15, Version 3

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP Unit 2 Cycle 15 Revision 2 has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Technical Requirement affected by this report is listed below:

13.1.1 SHUTDOWN MARGIN - MODES 1 and 2 The Technical Specifications affected by this report are listed below:

3.1.1 SHUTDOWN MARGIN - YIODES 3, 4 and 5 3.1.3 Moderator Temperature Coefficient 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 - FN ~H 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration Page 1 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the follow ing subsections. These limits have been developed using NRC-approved methodologies including those specified in Technical Specification 5.6.5.

2.1 SHUTDOWN MARGIN - MODES 1 and 2 (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent i1kJk.

2.2 SHUTDOWN MARGIN - MODES 3,4 and 5 (Specification 3.1.1) 2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1 and 2.

2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOLIARO/HZP-MTC shall be less positive than +0.7 x 10-4 i1kJkloF for power levels up to 70% RTP with a linear ramp to 0 i1kJkloF at 100% RTP.

The EOLIAROIRTP-MTC shall be less negative than -5.50 x 10-4 i1kJk/°F. 1 2.3.2 The MTC Surveillance limits are:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to

-4.75 x 10-4 i1k1k10F. 1 The 60 ppml ARO/RTP-MTC should be less negative than -5.35 x 10-4 i1k1kJ°F. 1 where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THE~\1AL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER

1. Applicable for full-power T-average of 584.4 to 587.4°F.

Page 2 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.

2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 3.

2.6 Heat Flux Hot Channel Factor - FO(Z) (Specification 3.2.1)

F RTP 2.6.1 F O(Z) :<:; -T .K(Z) for P > 0.5 FO(Z):<:; 0.5 . K(Z) for P ~ 0.5 THERMAL POWER where:

P = RATED THERMAL POWER 2.6.2 2.6.3 K(Z) is provided in Figure 4.

. FORTP'K(Z) 2.6.4 FO(Z):<:; p.W(Z) forP> 0.5 FQ RTP . K(Z)

FO(Z):<:; 0.5. W(Z) for P ~ 0.5 2.6.5 W(Z) values are provided in Table 2.

2.6.6 The FO(Z) penalty factors are provided in Table I.

Page 3 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FNt>H (Specification 3.2.2)

N RTP 2.7.1 F ~ F . (1 + PFt>H . ( I P>>

ilH ilH THERMAL POWER where: P RATED THERMAL POWER RTP 2.7.2 F l.65 ilH 2.7.3 PFt>H 0.3 2.8 (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Acceptable Operation Limits are provided in Figure 5.

2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 1815 ppm. 1 I.This concentration bounds the condition ofkeff~ 0.95 (all rods in less the most reactive rod) and subcriticality (all rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B 10 depletion.

Page 4 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 Table 1 FQ(Z) PENALTY FACTOR Cycle FQ(Z)

Burnup Penalty (MWD/MTU) Factor 30 1.031 150 1.031 367 1.032 584 1.031 801 1.029 1018 1.026 1236 1.021 1453 1.020 Notes:

1. The Penalty Factor, to be applied to FQ(Z) in accordance with SR 3.2.1.2, is the maximum factor by which FQ{Z) is expected to increase over a 39 EFPD interval (surveillance interval of31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) start ing from the burnup at which the FQ(Z) was determined.

2. Linear interpolation is adequate for intermediate cycle burnups.

3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.

Page 5 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 Table 2 RAoe W(Z)

Axial Elevation 150 4000 12000 20000 Point (feet) \1WD/MTU MWDIMTU MWD/Mn; MWDI\1TU I 12.00 1.0000 1.0000 1.0000 1.0000

+ 2 11.80 1.0000 1.0000 1.0000 1.0000

+

• 3 11.60 1.0000 1.0000 1.0000 1.0000

. 4 5

11.40 11.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 6 11.00 1.2254 1.3001 1.3064 1.2166 7 10.SO 1.2253 1.2873 1.2986 1.2009 8 10.60 1.2213 1.2700 1.2917 1.1894 9 10.40 1.2095 1.2514 1.2818 1.1855 10 10.20 1.1957 1.2411 1.2717 1.1854 II 10.00 1.1958 1.2354 1.2715 1.1881 12 9.80 1.1951 1.2315 1.2714 1.1911

\3 9.60 1.1921 1.2250 1.2707 1.1920 14 9.40 1.1885 1.2149 1.2678 1.1960 15 9.20 1.1806 1.2024 1.2591 1.2092 16 9.00 1.1752 1.1836 1.2502 1.2198 17 S.80 1.1746 1.1784 1.2385 1.2305 18 8.60 1.1786 1.1793 1.2339 1.2405 19 8.40 1.1890 1.1823 1.2386 1.2502 20 8.20 1.1960 1.1845 1.2400 1.2634 21 8.00 1.2055 1.1894 1.2448 1.2731 22 7.80 1.2133 1.1928 1.2484 1.2842 23 7.60 1.2176 1.1932 1.2482 1.2951 24 7.40 1.2196 1.1914 1.2457 1.3013 25 7.20 1.2190 1.1875 1.2405 1.3043 26 7.00 1.2163 1.1817 1.2329 1.3040 27 6.80 1.2115 1.1741 1.2232 1.3006 28 6.60 1.2052 1.1655 1.2116 1.2942 29 6.40 1.1985 1.1575 1.1988 1.2851 30 6.20 1.1911 1.1513 1.1858 1.2736 31 6.00 1.1817 1.1465 1.1727 1.2594 32 5.80 1.1739 1.1411 1.1638 1.2445 33 5.60 1.1674 1.1402 1.1628 1.2343 34 5.40 1.1639 1.1483 1.1674 1.2321 35 5.20 1.1720 1.1593 1.1699 1.2338 36 5.00 1.1807 1.1705 1.1723 1.2345 37 4.80 1.1878 1.1811 1.1748 1.2331 38 4.60 1.1941 1.1907 1.1763 1.2297 39 4.40 1.1993 1.1995 1.1764 1.2241 40 4.20 1.2034 1.2071 1.1753 1.2165 41 4.00 1.2062 1.2137 1.1730 1.2068 42 3.80 1.2080 1.2190 1.1693 1.1963 43 3.60 1.2082 1.2236 1.1654 1.1878 44 3.40 1.2078 1.2283 1.1629 1.1820 45 3.20 1.2130 1.2345 1.1626 1.1752 46 3.00 1.2268 1.2477 1.1657 1.1695 47 2.80 1.2433 1.2669 1.1750 1.1692 48 2.60 1.2580 1.2873 1.1871 1.1734 49 2.40 1.2727 1.3072 1.1984 1.1786 50 2.20 1.2902 1.3293 1.2095 1.1873 51 2.00 1.3089 1.3518 1.2205 1.1969 52 1.80 1.3272 1.3737 1.2313 1.2066 53 1.60 1.3450 1.3948 1.2419 1.2166 54 1.40 1.3621 1.4149 1.2523 1.2268 55 1.20 1.3783 1.4338 1.2622 1.2372 56 1.00 1.3931 1.4504 1.2711 1.2471

. 57 0.80 1.0000 1.0000 1.0000 LOOOO

. 58 0.60 1.0000 1.0000 1.0000 1.0000 1.0000

.* 59 60 0.40 0.20 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

. 61 0.00 1.0000 1.0000 1.0000 1.0000

• Top and Bottom 5 Points Excluded per Technical Specification B3.2. I.

These W(Z) values are consistent with Figure 5, and are valid over the HFP Tavg temperature range from 584.4 to 587.4°F.

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CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED AND VENTED AND AT LEAST ONE REACTOR COOLANT PUMP RUNNING) 5.0 I  !

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Page 7 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 FIGURE 2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE) 5.0

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Page 8 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 FIGURE 3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER (Fully Withdrawn*)

1I Ol%~ 225 i# 78. 2= ) i 0

220 I I / I I I V

~m~~ ~

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• I 0 10 20 30 40 50 60 70 80 90 1 o POWER (% of Rated Thermal Power)

• Fully withdrawn shall be the condition where control rods are at a ion within the interval ~225 and ~ 231 steps withdrawn.

NOTE: The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip to-tip distance of 115 steps.

Page 9 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A F{;NCTIO~ OF CORE HEIGHT 1.4 I I

I I I I 1.2 I

1 -

I FQ = 2.501 I

CORE I. HT . K(Z) 0.00 1. 00 6.00 1. 00 12.0 .925 N

ro::

0.4 0.2 0.0 I o 2 4 6 8 10 12 CORE HEIGHT (feet)

Page 10 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 2 CYCLE 15 REVISION 2 JUNE 2010 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL POWER FORRAOC 120 I i 1 1 1 i

i I I I 110 I , i 100

-r I

( 15, 100)

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I i 1

(+10,

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10 I I I 1 I I I i 0 I 1 i i

-50 -40 -30 20 10 o 10 20 30 40 50 AXIAL FLUX DIFFERENCE (percent ~I)

Page 11 of 11