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

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| issue date = 05/16/2011
| issue date = 05/16/2011
| title = Cycle 17 Core Operating Limits Report
| title = Cycle 17 Core Operating Limits Report
| author name = Ajluni M J
| author name = Ajluni M
| author affiliation = Southern Nuclear Operating Co, Inc
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:Mark J. Ajluni, Southern Nuclear Nuclear Licensing 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'\
{{#Wiki_filter:Mark J. Ajluni, P.E.        Southern Nuclear Nuclear Licensing Director  Operating Company, Inc.
COMPANY U. S. Nuclear Regulatory Commission NL-11-0919 ATTN: Document Control Desk Washington.
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'\
D. C. 20555-0001 VogUe Electric Generating Plant Unit 1 Cycle 17 Core Operating Limits Report Ladies and Gentlemen:
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 Company submits the enclosed Core Operating Limits Report (COLR) for Electric Generating Plant Unit 1 Cycle 17, Version This letter contains no NRC commitments.
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.
If there are any questions, Respectfully submitted, M. J. Nuclear Licensing MJA/SY AJlac
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:==
==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


Core Operating Limits Report, VEGP Unit 1 Cycle 17, Version 1 Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. T. E. Tynan, Vice President
Vogtle Electric Generating Plant Unit 1 Cycle 17 Core Operating Limits Report Enclosure Core Operating Limits Report, VEGP Unit 1 Cycle 17, Version 1
-Vogtle Ms. P. M. Marino, Vice President
 
-Engineering RType: CVC7000 U. S. Nuclear Regulatory Mr. V. M. McCree, Regional Mr. P. G. Boyle, NRR Project Manager -Mr. M. Cain, Senior Resident Inspector
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:
Vogtle Electric Generating Unit 1 Cycle 17 Core Operating Limits Core Operating Limits Report, VEGP Unit 1 Cycle 17, Version CORE OPERATING LIMITS REPORT, VEGP UNIT I CYCLE 17 FEBRUARY 1.0 CORE OPERATING LIMITS This Core Operating Limits Report (COLR) for VEGP Unit I Cycle 17 has been prepared in with the requirements of Technical Specification The Technical Requirement affected by this report is listed 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 -FN3.2.3 Axial Flux Difference 3.9.1 Boron Concentration Page 1 of 11 CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE FEBRUARY 2011 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the ing subsections.
13.1.1             SHUTDOWN MARGIN - MODES I and 2 The Technical Specifications affected by this report are listed below:
These limits have been developed using NRC-approved methodologies including those specified in Technical Specification 5.6.5. 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. SHUTDOWN MARGIN -MODES 3,4 and 5 (Specification 3.1.1) The SHUTDOWN MARGIN shall be greater than or cqual to the limits shown in Figures 1 and 2. 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 BOL stands for Beginning of Cycle ARO stands for All Rods HZP stands for Hot Zero THERMAL EOL stands for End of Cycle RTP stands for RATED THERMAL 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 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 --;;;...",-
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
.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. F Q(Z) s 0.5. W(Z) for PS 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 2.7 Nuclear Enthalpy Rise Hot Channel Factor -FN dH (Specification 3.2.2) N RTP 2.7.1 F '5:, F . (1 + P F dH' (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 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 FEBRUARY Table FQ{Z) PENALTY FQ(Z)I Bumup Penalty (MWD/MTU)
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.
Factor 1.026 I 150 1.026 i 367 1.027 I 1.027 i 802 1.027 1019 1.026 1236 1.025 1454 1.022 1671 1.020 Notes: The Penalty Factor, to be applied to FQ(Z) in accordance with SR 3.2.1.2, is the maximum factor by which F Q(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) ing from the bumup at which the F Q(Z) was determined. Linear interpolation is adequate for intermediate cycle bumups. For all cycle bumups outside the range of the table, a penalty factor of 1.020 shall be used. Page 5 of 11 CORE OPERA TlNG 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
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.
* I 12.00 1.0000 1.0000 1.0000 1.0000
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 11.80 1.0000 1.0000 1.0000 1.0000
2.3      Moderator Temperature Coefficient (Specification 3.1.3) 2.3,1   The Moderator Temperature Coefficient (MTC) limits are:
* 3 11.60 1.0000 1.0000 1.0000 1.0000
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.
* 4 11.40 1.0000 1.0000 1.0000 1.0000
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:
* 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
The 300 ppmlARO/RTP-MTC should be less negative than or equal to
* 57 0.80 1.0000 1.0000 1.0000 1.0000
                -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
* 58 0.60 1.0000 1.0000 1.0000 1.0000
 
* 59 0.40 1.0000 1.0000 1.0000 1.0000
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.
* 60 0.20 1.0000 1.0000 1.0000 1.0000
2.5                                   (Specification 3.1.6) 2.5.1   The control rod banks shall be limited in physical insertion as shown in Figure 3.
* 61 0.00 1.0000 1.0000 1.0000 1.0000
2.6   Heat Flux Hot Channel Factor - FQ(Z) (Specification 3.2.1) 2.6.1   F Q( Z) S -=::--
* 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 FIGURE REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED VENTED AND AT LEAST ONE REACTOR PUMP 5.0
* 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.
* 4.0 PERATING REGION ,11:--(2 00, .10)-....... ,11: ./""<] 3.0 dP V./"" V H Z REQUIRED SHUTDOWN MARGIN ./"" t!1 (1 00, .2 V ...... i ,,/V/'0 2.0 Q V E-4 fa /tI.l /' IUNACCEPTABLE OPERATING REGION I (.95C, ..."l 0) 1.0 0.0 *o 500 1000 1500 2000 2500
2.6.4 FQRTP.       K(Z)
* RCS BORON CONCENTRATION (ppm) Page 7 of 11 CORE OPERATING LIMITS REPORT, VEGP UNIT I CYCLE FEBRUARY FIGURE REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 5.0 (2 00, .9 / / / / *IACCEPTABLE OPERATING REGION / / I Y l/'<l 3.0 *I IREQUIRED SHUTDOWN  
F Q(Z) s   0.5. W(Z)         for PS 0.5 2.6.5   W(Z) values are provided in Table 2.
/ (1 50 , .85):z; H ! CI p:; *//2.0 /. til /. V UNACCEPTABLE OPERATING REGION / / ! ( .dO)6C , 0.0 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm) Page 8 of 11 CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY FIGURE ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL (Fully Withdrawn*)  
2.6.6   The FQ{Z) penalty factors are provided in Table 1.
-.. 180 m 3: til .5 III 140 til 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 and 231 steps withdrawn.
Page 3 of 11
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 FEBRUARY 201 FIGURE K(Z) -NORMALIZED FQ(Z) AS A FUNCTION OF CORE 1.4 I 1.2 -FQ = 2.50 HT. 0.00 1. 00 6.00 1. 00 12.0 .925 1)1 110:: 0.4 0.2 0.0 2 4 6 8 10 12 CORE HEIGHT (feet) Page 10 of 11 CORE OPERATING LIMITS REPORT, VEGP UNIT 1 CYCLE 17 FEBRUARY FIGURE AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL 120 I I I I 110 I ( 15, 100) (+10, 100) I 100 !I1\ ...... 101 U tJAC rEP' AB E UN CCI PT.P BLE OJ \90 I II \ .r-I J 1\ ttl 80 B I \ OJ ArCE TAl LE *..c:: / \E-t 70 i II 'tI ! I I 1\(I) .jJ ttl / \ c:: 60 I \I Ilol 0 V 1\df' 50 c:: I I (-30, 50 ) I (+26, 50) 40 I 30 i 20 10 ! I o 40 20 10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (percent Page 11 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&deg;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}}

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