NL-07-0744, Cycle 13 Core Operating Limits Report, Rev. 0

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Cycle 13 Core Operating Limits Report, Rev. 0
ML071010444
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 04/11/2007
From: George B
Southern Nuclear Operating Co
To:
Document Control Desk, NRC/NRR/ADRO
References
NL-07-0744
Download: ML071010444 (14)


Text

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham. Alabama 35201-1295 A p r i l 11, 2007 COMPANY Energy to Serve Your WorldsM Docket No.: 50-425 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Unit 2 Cycle 13 Core Operating Limits Report. Rev. 0 Ladies and Gentlemen:

Pursuant to the reporting requirements of Vogtle Electric Generating Plant (VEGP)

Technical Specification 5.6.5 Southern Nuclear Operating Company (SNC) is submitting Revision 0 of the Unit 2 Cycle 13 Core Operating Limits Report (COLR).

This letter contains no NRC commitments. If you have any questions, please advise.

Sincerely, k$---

B. J. Geo e Manager, Nuclear Licensing

Enclosure:

Unit 2 Cycle 13 Core Operating Limits Report, Rev. 0 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, Vice President - Vogtle Mr. D. H. Jones, Vice President - Engineering RType: CVC7000 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. B. K. Singal, NRR Project Manager - Vogtle Mr. G. J. McCoy, Senior Resident Inspector - Vogtle

Enclosure Vogtle Electric Generating Plant Unit 2 Cycle 13 Core Operating Limits Report, Rev. 0

VOGTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 2 CYCLE 13 CORE OPERATING LIMITS REPORT REVISION 0 March 2007

COLR for VEGP UNlT 2 CYCLE 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP UNlT 2 CYCLE 13 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 .I SHUTDOWN MARGIN - MODES 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 - Fo(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor - F&

3.2.3 Axial Flux Difference 3.9.1 Boron Concentration Page 1 of 11

COLR for VEGP UNIT 2 CYCLE 13 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following 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 AWk.

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 Tem~eratureCoefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOUAROIHZP - MTC shall be less positive than +0.7 x lo4 AWkPF for power levels up to 7ooh RTP with a linear ramp to 0 AWkPF at 100% RTP.

The EOUAROIRTP-MTC shall be less negative than -5.50 x 10-~AklkPF.'

2.3.2 The MTC Surveillance limits are:

The 300 ppmlARO1RTP-MTC should be less negative than or equal to

-4.75 x 104 A W ~ P F . ~

The 60 ppmlARO1RTP-MTC should be less negative than -5.35 x A W ~ ~ F . ~

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.4 Shutdown Bank lnsertion 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 banks shall be limited in physical insertion as shown in Figure 3.

1 Applicable for full-power T-average of 586.4"F to 587.4"F.

Page 2 of 1 1

COLR for VEGP UNIT 2 CYCLE 13 2.6 Heat Flux Hot Channel Factor - FQ(Z)(Specification 3.2.1) 2.6.1 GTP FQ(Z) 5 -* K(Z) for P > 0.5 P

F T;P FQ(z) 5 05* K(Z) for P 5 0.5 THERMAL POWER where: P=

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

F,RTP *K(Z) 2.6.4 FQ(Z) I for P > 0.5 P

  • W(Z)

F ; ~ ~ *K(Z)

FQ(z)5 0.5

  • W(Z) for P S0.5 2.6.5 W(Z) values are provided in Table 2.

2.6.6 The Fo(Z) penalty factors are provided in Table 1.

Page 3 of 11

COLR for VEGP UNIT 2 CYCLE 13 2.7 Nuclear Enthalpv Rise Hot Channel Factor - F& (Specification 3.2.2)

THERMAL POWER where: P =

RATED THERMAL POWER 2.8 Axial Flux Difference (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 1920 ppm.l h his concentration bounds the condition of kefl5 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" depletion.

Page 4 of 11

COLR for VEGP UNIT 2 CYCLE 13 TABLE 1 Fo(Z) PENALTY FACTOR Cycle FQ(Z)

Burnup Penalty

/MWD/MTU) Factor 30 1.0225 150 363 577 790 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 Fo(Z) is expected to increase over a 39 EFPD interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) starting 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

COLR for VEGP UNIT 2 CYCLE 13 TABLE 2 RAOC W (Z)

Axial Elevation 150 4000 Point (feet) MWDIMTU MWDIMTU 1 12.00 1.0000 1.0000 2 11.80 1.0000 1.oooo 3 11.60 1.oooo 1.oooo 4 11.40 1.oooo 1.OOQO 5 11.20 1.0000 1.oooo 6 11.oo 1.2937 1.3738 7 10.80 1.2798 1.3599 8 10.60 1.2603 1.3439 9 10.40 1.2399 1.3271 10 10.20 1.2240 1.3128 11 10.00 1.2184 1.2928

  • Top md Bottom 5 Points Excluded per Techr~icalSpecification B3.2.1.

These W(Z) values are consistent with Figure 5 and are valid over the HFP T,, temperature range from 586.4 to 587.4"F.

Page 6 of 1 1

COLR for VEGP UNIT 2 CYCLE 13 500 1000 1500 2000 2500 RCS BORON CONCENTRAT ION (pprn)

FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED AND VENTED AND AT LEAST ONE REACTOR COOLANT PUMP RUNNING)

Page 7 of 11

COLR for VEGP UNIT 2 CYCLE 13 0 500 1000 1500 2000 2500 RCS BORON CONCENTRAT ION ( p p )

FIGURE 2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE)

Page 8 of 11

COLR for VEGP UNIT 2 CYCLE 13 (Fully withdrawn*)

  • F'ully withdrawn shall be the condition where control rods are at a position within the interval 2 2 2 5 and 5 231 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.

FIGURE 3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER Page 9 of 11

COLR for VEGP UNIT 2 CYCLE 13 CORE HEIGHT (feet)

FIGURE 4 K(Z) - NORMALIZED Fa(Z) AS A FUNCTION OF CORE HEIGHT Page 10of 1 1

COLR for VEGP UNIT 2 CYCLE 13 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF

% OF RATED THERMAL POWER FOR RAOC Page I 1 of 1 1