NL-04-0623, Cycle 11 Core Operating Limits Report

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Cycle 11 Core Operating Limits Report
ML041200679
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 04/28/2004
From: Gasser J
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-04-0623
Download: ML041200679 (17)
v • d • e


Text

Jeffrey T.Gasser Southern Nuclear Vice President Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7721 Fax 205.992.0403 SOUTHERN £A April 28, 2004 COMPANY Energy to Serve Your World' Docket Nos.: 50-424 NL-04-0623 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Unit 2 Cycle 11 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 0 of the Unit 2 Cycle 11 Core Operting Limits Report (COLR).

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

Si IJTia4~-~--

Jeffrdy T. Gasser JTG/RJF/daj

Attachment:

Unit 2 Cycle 11 Core Operating Limits Report cc: Southern Nuclear Operating Company Mr. J. B. Beasley, Jr., Executive Vice President Mr. W. F. Kitchens, General Manager - Plant Vogtle Mr. M. Sheibani, Engineering Supervisor - Plant Vogtle RType: CVC7000 U. S. Nuclear Regulatorv Commission Mr. L. A. Reyes, Regional Administrator Mr. C. Gratton, NRR Project Manager - Vogtle Mr. J. Zeiler, Senior Resident Inspector - Vogtle

-AOD I

VOGTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 2 CYCLE 11 CORE OPERATING LIMITS REPORT REVISION 0 APRIL 2004

COLR for VEGP UNIT 2 CYCLE 11 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP UNIT 2 CYCLE 11 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 - F0(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor - FISH 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration PAGE 1 of 14

COLR for VEGP UNIT 2 CYCLE 11 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 Ak/k.

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 BOIJARO/HZP - MTC shall be less positive than +0.7 x 104 Ak/k/0F for power levels up to 70% RTP with a linear ramp to 0 Akk/I&F at 100% RTP.

The EOL/ARO/RTP-MTC shall be less negative than -5.50 x 104 Ak/kPF.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 104 Ak/kf1F.'

The 60 ppm/ARO/RTP-MTC should be less negative than

-5.35 x 104 Ak/k/0F.1 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.

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.

Applicable for full-power T-average of 586.40F to 587.40F.

PAGE 2 OF 14

COLR for VEGP UNIT 2 CYCLE 11 2.6 Heat Flux Hot Channel Factor - Fa(Z) (Specification 3.2.1)

RTP FQ 2.6.1 Fa(Z) S

  • K(Z) for P > 0.5 p

RTP Fo FQ(Z) s

  • K(Z) for P s 0.5

0.5 where

P =THERMAL POWER RATED THERMAL POWER RTP 2.6.2 Fa = 2.50 2.6.3 K(Z) is provided in Figure 4.

RTP 2.6.4 Fo(Z) S FQ K(Z) for P > 0.5 P *W(Z)

RTP Fa(Z) S Fn

  • K(Z) for P < 0.5 0.5
  • W(Z) 2.6.5 W(Z) values are provided in Figures 6 through 9.

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

PAGE 3 of 14

COLR for VEGP UNIT 2 CYCLE 11 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FISH (Specification 3.2.2) 2.7.1 FISH S F *H(1 + PFAH* (1-P))

THERMAL POWER where: P =

RATED THERMAL POWER 2.7.2 FRHT = 1.65 2.7.3 PFAH = 0.3 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.1

'This concentration bounds the condition of ken < 0.95 (all rods in less the most reactive rod) and subcriticality (I rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B10 depletion.

PAGE 4 of 14

COLR for VEGP UNIT 2 CYCLE 11 TABLE 1 Fa(Z) PENALTY FACTOR Cycle Fa(Z)

Burnup Penalty (MWD/MTU) Factor 4201 1.020 4414 1.021 4628 1.025 4841 1.025 5054 1.025 5267 1.023 5480 1.021 5694 1.020 Notes:

1. The Penalty Factor, to be applied to Fo(Z) 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 Fo(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 14

COLR for VEGP UNIT 2 CYCLE 11 5.00 S 4.00 I- 4 4 4-

  • ACCEPTABLE c:

0 OPERATING a)

REGION z (2500, 3.1L e5 3.00 c:

z (1600,2.

0 c:]

t- 2.00 C, UNACCEPTABLE w

a5 OPERATING (950, 1.30) REGION wa cc A Ion . I ., .

0 500 . 1000 1500 2000 2500 2175-1

. RCS BORON CONCENTRATION (ppm)

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

PAGE 6 of 14

COLR for VEGP UNIT 2 CYCLE 11 Ax 5.1 WVliii U

(250074.90)

'A

?4.00 ACCEPTABLE L.1 0.

2 z

j5 3.00 1 4 OPERATING REGION

4. -

7, 4.

(125c 2..85J 0 .

a 4 4 .4.

t- 2.00 V I a:

Lu 1.00 I _

Ai /

(460,1.00) .,

UNACCEPTABLE OPERATING REGION I

At U rIFlI__

.uu 0 500 1000 1500 2000 2500 217SI RCS BORON CONCENTRATION (ppm)

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

PAGE 7 of 14

COLR for VEGP UNIT 2 CYCLE 11 (Fully Withdrawn *)

225 220 i /80 '225)' (718.0%,

. 225)-

PI, ll lll r-uu -

ornn^lk asBANK B 180 0% ,~'1 61) I_ I_ (100%,

160 _ _ _

161)

I I.BAN C ts

~0 3: 140 I 7F I en a I' =c BAN =Ca U) z 1I "itI

&.W F -

0 F'

'A A 0 100 _I ZI -I1I flZ~iI z

7' A 80 0 BANK D acr 60 'd (0%,) ___6 __

4 0

2 (30.2%, 0) n - --

0 20 -40 60 80 100 (Fully Inserted) 2175-1 POWER (percent of rated thermal power)

Fully withdrawn shall be the condition where control rods are at a position within the interval >225 and 231 steps withdrawn.

Note: The Rod Bank Insertion Umits 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 8 of 14

COLR for VEGP UNIT 2 CYCLE 11 1.40 1.20 30 1.00 cc zas:

w a- 0.80 0

w N

0.60 a: F0 = 2.50 0

z CORE -

0.40 HEIGHT K(Z) -

0.000 1.000 6.000 1.000 0.20 12.000 0.925 0

0 2.0 4.0 6.0 8.0 10.0 12.0 CORE HEIGHT (ft)

-FIGURE 4 K(Z) - NORMALIZED F0 (Z) AS A FUNCTION OF CORE HEIGHT PAGE 9 of 14

COLR for VEGP UNIT 2 CYCLE 11 120 - . - S- SS U S * - S- S- S- U -

(-15, 100) (+10,100) l _ll IOC UNACCEPTABLE UNACCEPTABLE 0)

- 8C

0) ACCEPTABLE v 6C co a)

(-3 0, 50) (+26,5 0) 0 r-4C w

0 aJ 0~

2t C _ _

-50 -40 -3C) -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (percent AI)

-FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL POWER FOR RAOC PAGE 10 of 14

COLR for VEGP UNIT 2 CYCLE 11 Axial Elevation BOL Point (feet) W(Z) 1.b 1 12.00 1.0000

  • 2 11.80 1.0000
  • 3 11.60 1.0000
  • 4 11.40 1.0000 5 11.20 1.0000

' 6 11.00 1.0000 7 10.80 1.0000 C.. ' 8 10.60 1.0000

1.
  • 9 10.40 1.0000
  • 10 10.20 1.0000 11 10.00 1.3225 12 9.80 1.3149 13 9.60 1.3104 14 9.40 1.3001 15 9.20 1.2895 16 .9.00 1.2718
1. 4 17 8.80 1.2592 18 8.60 - .1.2532 A

19 8.40 1.2499 20 8.20 1.2485 A 21 8.00 1.2439 A 22 - 7.80 1.2463 23 7.60 1.2513 N 24 7.40 1.2517 1.

A 25 7.20 1.2498 A 26 7.00 1.2456 AAA A 27 6.80 1.2031

A-- - 28 6.60 1.1953 A 29 6.40 1.1857 A 30 6.20 1.1746 A - 31 6.00 1.1677

1. 2 -- -- -- --

32 5.80 1.1660 A A 33 5.60 1.1676 A A 34 5.40 1.1772 35 5.20 1.1913 36 5.00 1.2049 37 4.80 1.2174 38 4.60 1.2292 39 4.40 1.2399

1. 1-- -

40 4.20 1.2496 41 4.00 1.2581 42 3.80 1.2614 43 3.60 1.2630 44 3.40 1.2641 45 3.20 1.2731 46 3.00 1.2876 47 2.80 1.3052 I. 0I 48 2.60 1.3240 0.0 2.0 4.0 6.0 8.0 10.0 1, 49 2.40 1.3423 50 2.20 1.3603 Core Height - feet 51 2.00 1.3787

  • 52 1.80 1.0000 53 1.60 1.0000
  • 54 1.40 1.0000
  • 55 1.20. 1.0000

- 56 1.00 1.0000

  • 57 0.80 1.0000 This figure Isreferred to by Specification B3.2.1
  • 58 0.60 1.0000
  • 59 0.40 1.0000 These WV(Z) values are consistent with Figure 5,and arc valid
  • 60 0.20 1.0000 over the IIF T 815 temperature range from 586.4 to 587A40 F. 61 0.00 1.0000

COLR for VEGP UNIT 2 CYCLE 11 Axial Elevation MOL-1 Point (feet) W(Z) 1.i 5 1 12.00 1.0000 1

  • 2 3

4 5

6 11.80 11.60 11.40 11.20 11.00 1.0000 1.0000 1.0000 1.0000 1.0000 7 10.80 1.0000 8 10.60 1.0000

1. 9 10.40 1.0000 10 10.20 1.0000 11 10.00 1.3366 12 9.80 1.3278 13 9.60 1.3167 14 9.40 1.3020 15 9.20 1.2869 16 9.00 1.2695
1. 17 8.80 1.2590 18 8.60 1.2566 19 8.40 1.2557 20 8.20 1.2527 21 8.00 1.2537 22 7.80 1.2533

.4---iWs~S-r _ 23 7.60 1.2496 N 24 7.40 1.2436

- 1.

2: 25 7.20 1.2354 26 7.00 1.2254 27 6.80 1.1954 28 6.60 1.1830 29 6.40 1.1705 30 6.20 1.1568

___ _ _ _ 31 6.00 1.1634

1. 32 5.80 1.1557 33 5.60 1.1542 34 5.40 1.1611

_ _ _ _ _ _A 35 5.20 1.1694 36 5.00 1.1772 37 4.80 1.1841 38 4.60 1.1902 39 4.40 1.1955

1. 40 4.20 1.1997 41 4.00 1.2028 42 3.80 1.2074 43 3.60 1.2110 44 3.40 1.2138 45 3.20 1.2176 46 3.00 1.2312 47 2.80 1.2532
1. 48 2.60 1.2777 0.0 2.0 4.0 6.0 8.0 10.0 12.0 49 2.40 1.3017 50 2.20 1.3255 Core Height - feet 51 2.00 1.3492 52 1.80 1.0000 53 1.60 1.0000 54 1.40 1.0000
  • 55 1.20 1.0000
  • 56 1.00 1.0000 57 0.80 1.0000 This figure Isreferred to by Specification B3.2.1 58 - 0.60 1.0000
  • 59 0.40 1.0000 These W(Z) values are consistent with Figure 5, and are valid
  • 60 0.20 1.0000 over the 1IFP Tayg temperature range from 586.4 to 587A°F.
  • 61 0.00 1.0000
  • Top and Bottom 15% Excluded per Tecdnical Specification B3.2.1 FIGURE 7 PAGE 12 of 14 RAOC W (Z) AT 4000 MWD/MTU

COLR for VEGP UNIT 2 CYCLE 11 Axial Elevation MOL-2

. . . . Point (feet) W(Z)

Of . . . . . . 1 12.00 1.0000

1. .
  • 2 11.80 1.0000 3 11.60 1.0000 4 11.40 1.0000
  • 5 11.20 1.0000
  • 6 11.00 1.0000
  • 7 10.80 1.0000
  • 8 10.60 1.0000
1.
  • 9 10.40 1.0000 C.. _ __
  • 10 10.20 1.0000 11 10.00 1.2922 12 9.80 1.2803 13 9.60 1.2711 14 9.40 1.2604 15 9.20 1.2500 16 9.00 1.2425
1. 17 8.80 1.2355 18 8.60 1.2340 19 8.40 1.2383 20 8.20 1.2386 4-_ __ _, 21 8.00 1.2365 22 7.80 1.2352 23 7.60 1.2316 N 24 7.40 1.2259

-* 1. 25 7.20 1.2181 26 7.00 1.2085 27 6.80 1.1980 28 6.60 1.1877 X . . NS~sA 29 6.40 1.1777 z ~~~~ad . __- 30 6.20 1.1676 31 6.00 1.1575

_ __ _ . __ _ 32 5.80 1.1519

1. 33 5.60 1.1523 34 5.40 1.1563 35 5.20 1.1614

.- . _' . 36 5.00 1.1655 37 4.80 1.1683 38 4.60 1.1701

_ _A ~~~A _ _ _ 39 4.40 1.1706

1. 40 4.20 1.1703 41 4.00 1.1700 42 3.80 1.1688 43 3.60 1.1667 44 3.40 1.1655 45 3.20 1.1655 46 3.00 1.1672 47 2.80 1.1729
1. . 48 2.60 1.1817 0.0 2.0 4.0 6.0 8.0 10.0 12.0 49 2.40 1.1895 50 2.20 1.1971 Core Height - feet 51 2.00 1.2057
  • 52 1.80 1.0000
  • 53 1.60 1.0000
  • 54 1.40 1.0000 55 1.20 1.0000
  • 56 1.00 1.0000
  • 57 0.80 1.0000 This figure is referred to by Specification 133.2.1
  • 58 0.60 1.0000
  • 59 0.40 1.0000 These W(Z) values are consistent with Figure 5, and are valid 60 0.20 1.0000 over the IIFP Tang temperature range from 586.4 to 587.4WF.
  • 61 0.00 1.0000

COLR for VEGP UNIT 2 CYCLE 11 Axial Elevation EOL 1.i LII I

  • Point 1

2 3

4 5

6 (feet) 12.00 11.80 11.60 11.40 11.20 11.00 W(Z) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000

  • 7 10.80 1.0000
  • 8 10.60 1.0000 1.5 9 10.40 1.0000
  • 10 10.20 1.0000 11 10.00 1.2488 12 9.80 1.2565 13 9.60 1.2619 14 9.40 1.2649 15 9.20 1.2G79 16 9.00 1.2666
1. 17 8.80 1.2617 18 8.60 1.2613 19 8.40 1.2678 20 8.20 1.2760 21 8.00 1.2874 22 7.80 1.2852 23 7.60 1.2916 N 24 7.40 1.2949

- 1. 25 7.20 1.2951 A A __ _ 26 7.00 1.2923 27 6.80 1.2868 A AAA AA 28 6.60 1.2785 29 6.40 1.2681 AAA 30 6.20 1.2570 31 6.00 1.2444 32 5.80 1.2337

1. 33 5.60 1.2292

__A ~~~~a A& A__t K____

__ "^^ In^A 34 5.40 1.2290 35 5.20 1.2329 36 5.00 1.2353 37 4.80 1.2354 38 4.60 1.2336 39 4.40 1.2296 40 4.20 1.2236

1. 41 4.00 1.2156 42 3.80 1.2057 43 3.60 1.1944 44 3.40 1.1816 45 3.20 1.1695 46 3.00 1.1829 47 2.80 1.1900
1. i 48 2.60 1.1954 0.0 2.0 4.0 6.0 8.0 .10.0 12.( ) 49 2.40 1.2050 50 2.20 1.2159

-Core Height - feet 51 2.00 1.2268

  • 52 1.80 1.0000 53 1.60 1.0000 54 1.40 1.0000
  • 55 1.20 1.0000

' 56 1.00 1.0000 57 0.80 1.0000 This figure is referred to by Specification 1D3.2.1 58 0.60 1.0000

' 59 0.40 1.0000 These W(Z) values are consistent with Figure 5, and are valid

  • 60 0.20 1.0000 over the JIFP Tayg temperature range from 586.4 to 587AF.4
  • 61 0.00 1.0000

A SNC - Nuclear Licensing NRC Correspondence Routing and Information Sheet Applicable to: 10 CFR 50 Docket No. 10 CFR 72 No.

NRC Due Date: 4/ /0t Hatch Ul-321 U2-366 72-36 Author: R. J. Florian Farley UI-348 U2-364 LC #__ 72-42 Lic Letter No. NL-04-0623 Vogtle UI-424 U2-425 N/A Subject of Letter: Plant Vogtle Unit 2 Cycle 11 Core Operating Limits Report Response to: NRC Review I Concurrence Person Initials/Date Person InitialslDate 1 Site Mgmt. Concurrence 1J/A l 3 SRB Sub. Concurrence zJIf4 2 PRB Concurrence zJ1 4 Other WA Nuclear Licensing / Management Routing General Distributions:

O All extra copies to be issued via email in PDFMWORD format If possible (Except for NRC or State, issue hard copy)

O Allegation letters to JB Beasley in Confidential envelope O All letters to Executive: JB Beasley. Corp Licensing: BJ George, BD McKinney, RD Baker, NJ Stringfellow. Site NSACILicensing: GP Crone, M Sheibani, SB Tipps. TA Ruckman, TE Webb, WL Marlar, Submittals Review - FNP only.

o OPC (HNP & VNP only) - Laurence Bergen, Ken Rosanski and Bob Massey.

O All LERs to the respective LER Book, and LEReventseinpo.org as a WORD doc.

o NRR Project Managers: All TS Changes, RAI Responses and other items that require a response from the NRC.

Farlev: Sean Peters (sep~nrc.gov) Hatch & Vogtle: Christopher Gratton (cxg1 nrc.gov)

Other Distributions and comments: (List all distribution NOT shown in General Distributions above)

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