NL-11-0919, Cycle 17 Core Operating Limits Report: Difference between revisions

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CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17                                FEBRUARY 2011 FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED Al~D VENTED AND AT LEAST ONE REACTOR COOLAl~T PUMP RUNNING) 5.0
CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17                                FEBRUARY 2011 FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED Al~D VENTED AND AT LEAST ONE REACTOR COOLAl~T PUMP RUNNING) 5.0 4.0 PERATING REGION
* 4.0 PERATING REGION
--
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-.......
(2 00,      .10)
(2 00,      .10)
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-..
   ~
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   ~
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<l 3.0 dfI
<l 3.0 dfI
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CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17                FEBRUARY 2011 FIGURE 3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER (Fully Withdrawn*)
CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17                FEBRUARY 2011 FIGURE 3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER (Fully Withdrawn*)
-..
  ~ 180 m
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CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17              FEBRUARY 201 1 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.4 I
CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17              FEBRUARY 201 1 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.4 I
1.2
1.2 FQ    =  2.50 CORE HT.      K(Z) 0.00 1. 00 6.00 1. 00 12.0 .925 1)1 110::
                                                                          -
FQ    =  2.50 CORE HT.      K(Z)
                            - - --  - - --
0.00 1. 00 6.00 1. 00 12.0 .925
--
1)1 110::
0.4 0.2 0.0 o        2          4            6        8      10          12 CORE HEIGHT (feet)
0.4 0.2 0.0 o        2          4            6        8      10          12 CORE HEIGHT (feet)
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CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17                                        FEBRUARY 2011 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL POWER FORRAOC 120 I                                                                                        I I                                    I 110
CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17                                        FEBRUARY 2011 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL POWER FORRAOC 120 I                                                                                        I I                                    I 110
(  15, 100)                        (+10, 100)                              I 100                                                                                I
(  15, 100)                        (+10, 100)                              I 100                                                                                I
......
                                               ~                  1\                      I            !
                                               ~                  1\                      I            !
101 OJ    90 U tJAC rEP' AB E I                      \          UN CCI PT.P BLE
101 OJ    90 U tJAC rEP' AB E I                      \          UN CCI PT.P BLE
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40 I
40 I
30 i
30 i
20
20 10 I
                          !
10 I
o
o
           -50      -40    -30        -20        10    0      10          20        30    40      50 AXIAL FLUX DIFFERENCE (percent ~I)
           -50      -40    -30        -20        10    0      10          20        30    40      50 AXIAL FLUX DIFFERENCE (percent ~I)
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Latest revision as of 22:51, 10 March 2020

Cycle 17 Core Operating Limits Report
ML111370263
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 05/16/2011
From: Ajluni M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-11-0919
Download: ML111370263 (13)


Text

Mark J. Ajluni, P.E. Southern Nuclear Nuclear Licensing Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 May 16, 2011 Docket Nos.: 50-424 SOUTHERN'\

COMPANY U. S. Nuclear Regulatory Commission NL-11-0919 ATTN: Document Control Desk Washington. D. C. 20555-0001 VogUe Electric Generating Plant Unit 1 Cycle 17 Core Operating Limits Report Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company submits the enclosed Core Operating Limits Report (COLR) for Vogtle Electric Generating Plant Unit 1 Cycle 17, Version 1.

This letter contains no NRC commitments. If there are any questions, please advise.

Respectfully submitted,

~~uf'-'

M. J. Ajluni Nuclear Licensing Director MJA/SYAJlac

Enclosure:

Core Operating Limits Report, VEGP Unit 1 Cycle 17, Version 1 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, Vice President - Vogtle Ms. P. M. Marino, Vice President - Engineering RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. P. G. Boyle, NRR Project Manager - Vogtle Mr. M. Cain, Senior Resident Inspector - Vogtle

Vogtle Electric Generating Plant Unit 1 Cycle 17 Core Operating Limits Report Enclosure Core Operating Limits Report, VEGP Unit 1 Cycle 17, Version 1

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYCLE 17 FEBRUARY 2011 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP Unit I Cycle 17 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 I 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 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 1 CYCLE 17 FEBRUARY 2011 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 I and 2 (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent dkJk.

2.2 SHUTDOWN MARGIN - MODES 3,4 and 5 (Specification 3.1.1) 2.2.1 The SHUTDOWN MARGIN shall be greater than or cqual 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 dkJkJoF for power levels up to 70% RTP with a linear ramp to 0 dkJkJoF at 100% RTP.

The EOLIARO/RTP-MTC shall be less negative than -5,50 x 10.4 dkJkJ°F,1 2.3,2 The MTC Surveillance limits are:

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

-4,75 x 10.4 dkJkJ°F,1 The 60 ppm!ARO/RTP-MTC should be less negative than -5.35 x lO* 4 dkJkJ°F. 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 I Applicable for full-power T-average of 584.4 to 587.4°F, Page 2 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY 2011 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 (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 - FQ(Z) (Specification 3.2.1) 2.6.1 F Q( Z) S -=::--

  • K( Z) for P > 0.5 F Q(Z) s --;;;...",- . K(Z) for P S 0.5 THERMAL POWER where: P RATED THERMAL POWER 2.6.2 2.6.3 K(Z) is provided in Figure 4.

2.6.4 FQRTP. K(Z)

F Q(Z) s 0.5. W(Z) for PS 0.5 2.6.5 W(Z) values are provided in Table 2.

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

Page 3 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY 2011 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FNdH (Specification 3.2.2)

N RTP 2.7.1 F '5:, F . (1 + P FdH' (1 - P))

m m THERMAL POWER where:

P = RATED THERMAL POWER 2.7.2 1.65 2.7.3 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 1845 ppm.'

'This concentration bounds the condition of~tT':;; 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 IO depletion.

Page 4 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY 2011 Table 1 FQ{Z) PENALTY FACTOR Cycle FQ(Z)

I Bumup Penalty (MWD/MTU) Factor 30 1.026 I

i i 150 1.026 367 1.027 I

i 585 1.027 802 1.027 1019 1.026 1236 1.025 1454 1.022 1671 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 of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) start ing from the bumup at which the FQ(Z) was determined.
2. Linear interpolation is adequate for intermediate cycle bumups.
3. For all cycle bumups outside the range of the table, a penalty factor of 1.020 shall be used.

Page 5 of 11

CORE OPERATlNG LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY 2011 Table 2 RAOCW(Z)

Axial Elevation 150 4000 12000 20000 Point (feet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU

  • 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 11.40 1.0000 1.0000 1.0000 1.0000
  • 5 11.20 1.0000 1.0000 1.0000 1.0000 6 11.00 1.1820 1.2630 1.2970 1.2346 7 10.80 1.1826 1.2504 1.2919 1.2253 8 10.60 1.1840 1.2424 1.2875 1.2192 9 10.40 1.1838 1.2401 1.2822 1.2129 10 10.20 1.1842 1.2415 1.2737 1.2069 11 10.00 1.1845 1.2447 1.2620 1.2058 12 9.80 1.1854 1.2435 1.2591 1.2043 13 9.60 1.1847 1.2387 1.2584 1.2046 14 9.40 1.1822 1.2302 1.2543 1.2112 15 9.20 1.1801 1.2150 1.2458 1.2220 16 9.00 1.1765 1.1974 1.2364 1.2290 17 8.80 1.\ 776 1.1815 1.2247 1.2346 18 8.60 1.1856 1.1757 1.2212 1.2387 19 8.40 1.\ 954 1.1754 1.2240 1.2440 20 8.20 1.2013 1.1742 1.2250 1.2550 21 8.00 1.2096 1.1771 1.2300 1.2627 22 7.80 1.2163 1.1796 1.2339 1.2730 23 7.60 1.2195 1.1789 1.2341 1.2839 24 7.40 1.2204 1.1765 1.2322 1.2900 25 7.20 1.2189 1.1722 1.2277 1.2931 26 7.00 1.2152 1.1662 1.2210 1.2931 27 6.80 1.2095 1.1586 1.2123 1.2899 28 6.60 1.2023 1.1501 1.2017 1.2840 29 6.40 1.1945 1.1422 1.1899 1.2755 30 6.20 1.1862 1.1360 1.1780 1.2646 31 6.00 1.1760 1.1313 1.1659 1.2506 32 5.80 1.1672 1.1291 1.1579 1.2391 33 5.60 1.1603 1.1312 1.1578 1.2327 34 5.40 1.1581 1.1438 1.1636 1.2305 35 5.20 1.1666 1.1546 1.1674 1.2328 36 5.00 1.1750 1.1645 1.1700 1.2343 37 4.80 1.1815 1.1738 1.1715 1.2335 38 4.60 1.1875 1.1822 1.1716 1.2307 39 4.40 1.1923 1.1896 1.1707 1.2259 40 4.20 1.1960 1.1960 1.1685 1.2189 41 4.00 1.1986 1.2013 1.1644 1.2 101 42 3.80 1.1995 1.2057 1.1631 1.1995 43 3.60 1.2005 1.2084 1.1650 1.1876 44 3.40 1.2040 1.2107 1.1657 1.1765 45 3.20 1.2086 1.2194 1.1662 1.1696 46 3.00 1.2137 1.2310 1.1671 1.1687 47 2.80 1.2263 1.2469 1.1699 1.1715 48 2.60 1.2460 1.2682 1.1760 1.1804 49 2.40 1.2639 1.2922 1.1851 1.1912 50 2.20 1.2816 1.3159 1.1940 1.2018 51 2.00 1.2990 1.3391 1.2029 1.2122 52 1.80 1.3160 1.3618 1.2120 1.2229 53 1.60 1.3326 1.3836 1.2210 1.2336 54 1.40 1.3486 1.4044 1.2300 1.2445 55 1.20 1.3639 1.4237 1.2387 1.2553 56 1.00 1.3777 1.4407 1.2466 1.2655
  • 57 0.80 1.0000 1.0000 1.0000 1.0000
  • 58 0.60 1.0000 1.0000 1.0000 1.0000
  • 59 0.40 1.0000 1.0000 1.0000 1.0000
  • 60 0.20 1.0000 1.0000 1.0000 1.0000
  • 61 0.00 1.0000 1.0000 1.0000 1.0000
  • Top and 8ottom 5 Points Excluded per Technical Specification 83.2.1.

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.

Page 6 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY 2011 FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED Al~D VENTED AND AT LEAST ONE REACTOR COOLAl~T PUMP RUNNING) 5.0 4.0 PERATING REGION

,11:

(2 00, .10)

,11:

<] 3.0 ./""

dP V

./""

Z REQUIRED SHUTDOWN MARGIN ./""

V H

t!1 ~

V ...

i (1 00, .2 ~)

,,/

~ /'

V 0 2.0 Q

E-4 V fa /

tI.l V

/'

IUNACCEPTABLE OPERATING REGION I 1.0

(.95C, ...

"l 0) 0.0 o *

  • 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 7 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT I CYCLE 17 FEBRUARY 2011 FIGURE 2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE) 5.0 (2 00, /

~

.9

/

/

/

4.0

  • IACCEPTABLE OPERATING REGION I .A'

/

/ I

~

~

<l 3.0 dfI

  • I IREQUIRED SHUTDOWN MARGIN~ /

Y l/'

(1 50 , ~ .85)

z; H  !

CI p:;

~ *

/

~A 2.0

/

/.

~

til /.

V UNACCEPTABLE OPERATING REGION 1.0 /

/  !

( 6C , .dO) 0.0 o 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)

Page 8 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY 2011 FIGURE 3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER (Fully Withdrawn*)

~ 180 m

~

~ l60~+-~~~~I-++-I-+~I-++-I-+~I-++-~+-I-+~I-+~I-+~I-+~I-+~~

3:

til III

.5 140 I-++-I-++

til

~ 80~~~~~~~~~~~~~~~~~~~~r+~~~r+~r+~r+~r+~~

Q

~

10 20 30 40 50 60 70 80 90 1 0 POWER (% 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 Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank -tip distance of 115 steps.

Page 9 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY 201 1 FIGURE 4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.4 I

1.2 FQ = 2.50 CORE HT. K(Z) 0.00 1. 00 6.00 1. 00 12.0 .925 1)1 110::

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

Page 10 of 11

CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY 2011 FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL POWER FORRAOC 120 I I I I 110

( 15, 100) (+10, 100) I 100 I

~ 1\ I  !

101 OJ 90 U tJAC rEP' AB E I \ UN CCI PT.P BLE

~

~ II \ . i--

r-I 80 J 1\

ttl B

OJ I \

..c::

E-t 70 i II

/ ArCE TAl LE *

\

! I

'tI (I)

I 1\

.jJ ttl c:: 60

/ \

Ilol I I

\

0 df' 50 V 1\

I c:: I (-30, 50 ) I (+26, 50)

~

~

40 I

30 i

20 10 I

o

-50 -40 -30 -20 10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (percent ~I)

Page 11 of 11