NL-07-0012, Revision 1 of Unit 1 Cycle 14 Core Operating Limits Report

Revision 1 of Unit 1 Cycle 14 Core Operating Limits Report

ML070330622
Person / Time
Site:	Vogtle
Issue date:	01/30/2007
From:	Tynan T Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-07-0012
Download: ML070330622 (13)

Text

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 COMPM Energy to Serve Your WorldsM January 30, 2007 Docket No.: 50-424 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Revision 1 of Unit 1 Cycle 14 Core Operating Limits Report 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 1 of the Unit 1 Cycle 14 Core Operating Limits Report (COLR).

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

Sincerely, T. E. Tynan Vice President - Vogtle Vogtle Electric Generating Plant 782 1 River Road Waynesboro, GA 30830

Enclosure:

Unit 1 Cycle 14 Core Operating Limits Report cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President RType: CVC7000 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Vogtle Mr. G. J. McCoy, Senior Resident Inspector - Vogtle

VOGTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 1 CYCLE 14 CORE OPERATING LIMITS REPORT REVISION 1 December 2006

COLR for VEGP UNlT 1 CYCLE 14 1.0 CORE OPERATING LIMITS REPORT

'This Core Operating Limits Report (COLR) for VEGP UNlT 1 CYCLE 14 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 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 k 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration PAGE 1 of 11

COLR for VEGP UNIT 1 CYCLE 14 2.0 OPERA-I-ING 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 . l )

2.1 .I The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent Aklk.

2.2 SHUTDOWN MARGIN - MODES 3,4 AND 5 (Specification 3.1 .l) 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 l o 4 AklkPF for power levels up to 70 percent RTP with a linear ramp to 0 AklkPF at 100 percent RTP.

The EOUAROIRTP-MTC shall be less negative than

-5.50 x 104 A W ~ P F . ~

2.3.2 The MTC Surveillance limits are:

The 300 ppmlAROIR'rP-MTC should be less negative than or equal to -4.75 x 10" ~ k l k P ~ . '

The 60 ppmlAROIRTP-MTC should be less negative than

-5.35 x i04 A W ~ P 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 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.

'~pplicablefor full-power T-average of 586.4OF to 587.4OF.

PAGE 2 of 11

COLR for VEGP UNIT 1 CYCLE 14 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.

2.6 Heat Flux Hot Channel Factor - FQ(Z)(Specification 3.2.1) l$y 2.6.1 FQ(Z) 5 -* K(Z) for P > 0.5 P

FRTP FQ(Z) 5 - 0.5

• K(Z) for P 5 0.5 THERMAL POWER where: P =

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

2.6.4 FQ(z) 5 FF' *K(Z) for P > 0.5 P

• W(Z)

F~;P *K(Z)

FQ(z) 5 for P 50.5 0.5

• W(Z) 2.6.5 W(Z) values are provided in Table 2.

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

COLR for VEGP UNIT 1 CYCLE 14 2.7 -

Nuclear Enthal~vRise Hot Channel Factor F& (Specification 3.2.2) 2.7.1 F& S F:iP * (1 + P F A*~(1 - P))

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 1900 ppm.'

h his concentration bounds the condition of Ign s 0.95 (all rods in less the most reactive rod) and subcriticality @! rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and 6 depletion.

PAGE 4 of 11

COLR for VEGP UNIT 1 CYCLE 14 TABLE 1 FQ(Z)PENALTY FACTOR Cycle Fa@)

Burnup Penalty (MWDIMTU) Factor 6124 1.020 6338 1.021 7831 1.021 8044 1.020

1. The Penalty Factor, to be applied to Fa@) in accordance with SR 3.2.1.2, is the maximum factor by which Fa(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 bumups outside the range of the table, a penalty factor of 1.020 shall be used.

PAGE 5 of 11

COLR for VEGP UNIT 1 CYCLE 14 Table 2 RAOC W(Z)

Axial Elevation Poird 1 I11.80 fi71 11.60 11.40 11.20 11.00 10.80 10.60 10.40 10.20 10.00 9.80 9.60 9.40 Top mdBottom 5 PointsExcluded pcr Thnical Specification B3.2.1.

ll~heseW(Z) values are consistent with Figure 5, and are valid over the HFP TaVgtemperature range from 586.4to 587.4OF.

COLR for VEGP UNIT 1 CYCLE 14 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 1 CYCLE 14 RCS BORON CONCENTRATION ( 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 1 CYCLE 14 (Fully withdrawnf)

POWER (% of Rated Thermal Power)

• ~ u l l ywithdrawn shall be the condition where control rods are at a position within the interval 2 225 and I 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 1 CYCLE 14 CORE HEIGHT (feet)

FIGURE 4 K(Z) - NORMALIZED Fp(Z) AS A FUNCTION OF CORE HEIGHT PAGE 10 of 11

COLR for VEGP UNIT 1 CYCLE 14 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL POWER FOR RAOC PAGE 11 of l?