CP-200800514, Cycle 11, Core Operating Limits Reports

Cycle 11, Core Operating Limits Reports

ML081200756
Person / Time
Site:	Comanche Peak
Issue date:	04/22/2008
From:	Madden F Luminant Generation Co, Luminant Power
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-200800514, TXX-08058
Download: ML081200756 (23)

Text

{{#Wiki_filter:um Luminant Mike Blevins Executive Vice President& Chief Nuclear Officer Mike.Blevins@Luminant.com Luminant Power P 0 Box 1002 6322 North FM 56 Glen Rose, TX 76043 T 254 897 5209 C 817 559 9085 F 254 897 6652 CP-200800514 Log # TXX-08058 Ref. # Tech. Spec. 5.6.5 April 22, 2008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NO. 50-446 CORE OPERATING LIMITS REPORTS

Dear Sir or Madam:

Pursuant to Technical Specification 5.6.5, Luminant Generation Company LLC (Luminant Power) hereby submits the Core Operating Limits Reports for Comanche Peak Unit 2, Cycle 11.This communication contains no new licensing basis commitments regarding Comanche Peak Units 1 and 2. Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.Sincerely, Luminant Generation Company LLC Mike Blevins By:: _ _ _ _ _/ Freýl W. Madden Director, Oversight & Regulatory Affairs Enclosure Unit 2, Cycle 11 Core Operating Limits Report (COLR)c -E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak A member of the STARS (Strategic Teaming and Resource Sharing) Alliance.. Callaway -Comanche Peak

• Diablo Canyon Palo Verde -South Texas Project -Wolf Creek ERX-08-001, Rev. 0 CPNPP UNIT 2 CYCLE 3.1'CORE OPERATING LIMITS REPORT April2008 Prepared: (_ 2z 'Date: Daniel E. Brozak Principal Engineer, Westinghouse El ectricý Co.~\ ~ReViewed: Reviewed: Somporn Srinilta Prin-cpalý Engineer, Date: ....Westinghouse Electric Co._____ Date: evin N. Roland Principal Engineer, Westinghouse El.ectric Co.Approved: JesBoatwi -Manager Date: r Westinghouse Engineering Serivices

-Texas DISCLAIMER The information contained in this report was prepared for the specific requirement of Energy Future Holdings Company LP and may not be appropriate for use in situations other than those for which it was specifically prepared. Energy Future Holdings Company LP PROVIDES NO WARRANTY HEREUNDER, EXPRESS OR IMPLIED, OR STATUTORY, OF ANY KIND) OR NATURE WHATSOEVER, REGARDING THIS REPORT OR ITS USE, INCLUDING BUT NOT LIMITED TO ANY WARRANTIES ON MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE.By making this report available, Energy Future Holdings Company LP does not authorize its use by others, and any such use is forbidden except with the prior written approval of Energy Future Holdings Company LP. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein.In no event shall Energy Future Holdings Company LP have any liability for any incidental or consequential damages of any type in connection with the use, authorized or unauthorized, of this' report or of the information in it.ii ii ERX-O8-O0l, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 TABLE OF CONTENTS DISCLAIMER...............................................................i TABLE OF CONTENTS.......................................................11 LIST OF TABLES........................................................... iv LIST OF FIGURES.......................................................... v SECTION PAGE 1.0 CORE OPERATING LIMITS REPORT......................................1 2.0 OPERATING LIMITS....................................................2 2.1 SAFETY LIMITS.................................................2 2.2 SHUTDOWN MARGIN...............................................2 2.3 MODERATOR TEMPERATURE COEFFICIENT.......................... 2 2.4 ROD GROUP ALIGNMENT LIMITS...................................3 2.5 SHUTDOWN BANK INSERTION LIMITS.............................. 3 2.6 CONTROL BANK INSERTION LIMITS............................... 4 2.7 PHYSICS TESTS EXCEPTIONS -MODE 2.......................... 4 2.8 HEAT FLUX HOT CHANNEL FACTOR................................ 4 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR....................5 2.10 AXIAL FLUX DIFFERENCE.........................................6 2.11 REACTOR TRIP SYSTEM INSTRUMENTATION.........................6 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS..................................... 7 2.13 BORON CONCENTRATION.......................................... 8

3.0 REFERENCES

...........................................................8 iii iii ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 LIST OF TABLES TABLE PAGE 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD ....... 9 iv ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 LIST OF FIGURES FIGURE PAGE 1 REACTOR CORE SAFETY LIMITS .............................. 10 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER ............. 11 3 K(Z) -NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT ............................................. 12 4 W(Z) AS A FUNCTION OF CORE HEIGHT -(150 MWD/MTU) ........................................... 13 5 W(Z) AS A FUNCTION OF CORE HEIGHT -(5,000 MWD/MTU) ......................................... 14 6 W(Z) AS A FUNCTION OF CORE HEIGHT -(10,000 MWD/MTU) ........................................ 15 7 W(Z) AS A FUNCTION OF CORE HEIGHT -(20,000 MWD/MTU) ........................................ 16 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER ................................... 17 V ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 2 CYCLE 11 has been prepared in accordance with the requirements of Technical Specification 5.6.5.The Technical Specifications affected by this report are listed below: SL 2.1 LCO 3.1.1 LCO 3.1.3 LCO 3.1.4 LCO 3.1.5 LCO 3.1.6 LCO 3.1.8 LCO 3.2.1.2 LCO 3.2.2 LCO 3.2.3.2 LCO 3.3.1 LCO 3.4.1 LCO 3.9.1 SAFETY LIMITS SHUTDOWN MARGIN MODERATOR TEMPERATURE COEFFICIENT ROD GROUP ALIGNMENT LIMITS SHUTDOWN BANK INSERTION LIMITS CONTROL BANK INSERTION LIMITS PHYSICS TESTS EXCEPTIONS -MODE 2 HEAT FLUX HOT CHANNEL FACTOR NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR AXIAL FLUX DIFFERENCE REACTOR TRIP SYSTEM INSTRUMENTATION RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS BORON CONCENTRATION ERX-08-001, Rev. 0 COLR for CPNPP 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 the NRC-approved methodologies specified in Technical Specification 5.6.5b, Items 1, 2, 14, 16, 17, 18 and 21 through 29. These limits have been determined such that all applicable limits of the safety analysis are met.2.1 SAFETY LIMITS (SL 2.1)2.1.1 In MODES 1 and 2, the combination of thermal power, reactor coolant system highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 1.2.2 SHUTDOWN MARGIN (SDM) (LCO 3.1.1)2.2.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODE 2 with K... < 1.0, and in MODES 3, 4, and 5.2.3 MODERATOR TEMPERATURE COEFFICIENT (MTC) (LCO 3.1.3)2.3.1 The MTC upper and lower limits, respectively, are: The BOL/ARO/HZP-MTC shall be less positive than +5 pcm/*F.The EOL/ARO/RTP-MTC shall be less negative than -40 pcm/°F.2 ERX-08-001, Rev. 0 2.3.2 COLR for CPNPP Unit 2 Cycle 11 SR 3.1.3.2 The MTC surveillance limit is: The 300 ppm/ARO/RTP-MTC shall be less negative than or equal to -31 pcm/'F.The 60 ppm/ARO/RTP-MTC shall be less negative than or equal to -38 pcm/*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 ROD GROUP ALIGNMENT LIMITS (LCO 3.1.4)2.4.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODES 1 and 2.2.5 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.5)2.5.1 The shutdown rods shall be fully withdrawn. Fully withdrawn shall be the condition where shutdown rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive. 3 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 2.6 CONTROL BANK INSERTION LIMITS (LCO 3.1.6)2.6.1 The control banks shall be limited in physical insertion as shown in Figure 2.2.6.2 The control banks shall always be withdrawn and inserted in the prescribed sequence. For withdrawal, the sequence is control bank A, control bank B, control bank C, and control bank D. The insertion sequence is the reverse of the withdrawal sequence.2.6.3 A 115 step Tip-to-Tip relationship between each sequential control bank shall be maintained. 2.7 PHYSICS TESTS EXCEPTIONS -MODE 2 (LCO 3.1.8)2.7.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODE 2 during PHYSICS TESTS.2.8 HEAT FLUX HOT CHANNEL FACTOR (F. (Z) (LCO 3.2.1.2)FRTP F 2.8.1 FQ(Z) -- [K(Z)] for P > 0.5 P IRTP FQ FQ(Z) <_<0.5 where: P = I RATI[K(Z)] for P S 0.5 FHERMAL POWER ED THERMAL POWER 4 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 FRTP 2.8.2 F = 2.50 2.8.3 K(Z) is provided in Figure 3.2.8.4 Elevation and burnup dependent W(Z) values are provided in Figures 4, 5, 6, and 7. The burnup dependent values can be used to interpolate or extrapolate (via a three point fit)the W(Z) at a particular burnup.2.8.5 SR 3.2.1.2.2 If the two most recent FQ(Z) evaluations show an increase in the expression maximum over Z[ FQC(Z) / K(Z) ], the burnup dependent values in Table 1 shall be used instead of a constant 2% to increase FQw(Z) per Surveillance Requirement 3.2.1.2.2.a. A constant factor of 2% shall be used for all cycle burnups that are outside the range of Table 1.2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNAHI (LCO 3.2.2), 2.9.1 FNAH 5 F'T'AH [1 + PFA (l-P)]where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 F TPAH = 1.41 for Region 1-13B and liB Fuel Assemblies FRTPAH = 1.60 for all other Fuel Assembly Regions 2.9.3 PFAH = 0.3 5 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 2.10 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3.2)2.10.1 The AFD Acceptable Operation Limits are provided in Figure 8.2.11 REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION (LCO 3.3.1)2.11.1 The numerical values pertaining to the Overtemperature N-16 reactor trip setpoint are listed below;K, = 1.15 K = 0.0139 I°F K 3 = 0.00071 /psig TC 0 = indicated loop specific T, at Rated Thermal Power, 0 F P 1 Z 2235 psig T, 10 sec T 2 5 3 sec f 1 (Aq) = -2.78 -{(q-qb) + 18%} when (q,-q 1) 5 -18% RTP= 0% when -18% RTP < (qt-q,) < +10.0% RTP= 2.34 {(qt-q,) -10.0%) when (qt-qb) a +10.0% RTP 6 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS (LCO 3.4.1)2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the surveillance limits specified below: 2.12.2 SR 3.4.1.1 Pressurizer pressure 2 2220 psig (4 channels)2222 psig (3 channels)The pressurizer pressure limits correspond to the analytical limit of 2205 psig used in the safety analysis with allowance for measurement uncertainty. These uncertainties are based on the use of control board indications and the number of available channels.2.12.3 SR 3.4.1.2 RCS average temperature S 592 'F (4 channels)5 591 'F (3 channels)The RCS average temperature limits correspond to the analytical limit of 595.2 0 F used in the safety analysis with allowance for measurement uncertainty. These uncertainties are based on the use of control board indications and the number of available channels.7 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be 408,000 gpm.2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be 408,000 gpm.The required RCS flow, based on an elbow tap differential pressure instrument measurement prior to MODE 1 after the refueling outage, shall be greater than 327,000 gpm.2.13 BORON CONCENTRATION (LCO 3.9.1)2.13.1 The required refueling boron concentration is 2!1899 ppm.

3.0 REFERENCES

Technical Specification 5.6.5.8 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 Table 1 DECREASES IN EXCESS OF 2% PER 31 EFPD F, (Z) MARGIN Cycle Maximum Decrease Burnup In F, (Z) MARGIN (MWD/MTU) (Percent)982 2.00 1190 2.65 1398 3.75 1606 4.78 1814 5.21 2022 4.51 2230 3.83 2438 3.21 2647 2.63 2855 2.11 3063 2.00 Note: All Cycle burnups outside the range of the table shall use a constant 2% decrease in FQ(Z)margin for compliance with the 3.2.1.2.2.a Surveillance Requirements. Linear interpolation is acceptable to determine the FQ(Z) margin decrease for cycle burnups which fall between the specified burnups.9 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 Figure 1 Reactor Core Safety Limits 680-660 ______ ______ _____660 5 pUnacceptable 640O 0 0.E 620 620- 100 120 14 0 600)580 560 0 20 40 60 80 100 120 140 Percent of Rated Thermal Power (3458 MWt)10 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 220 200 180 ,n 160 4J-,-I 140 4J 120 0 H H 100 0 80 o 60 40 20 0--(2 .3,28).(79.6,218) BANK B--(0,164)--(00,146)BANK C + -+ /II BANK D 0 10 20 30 40 50 60 70 80. 90 100 PERCENT OF RATED THERMAL POWER NOTES: 1. Fully withdrawn shall be the condition where control rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.

2. Control Bank A shall be fully withdrawn.

11 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 FIGURE 3 K(Z) -NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 1.0 0.9 0.8 0 0.7 N 0.6 o 0.5 1 1 1 1 1 1 1 1 ý I I I I I (0.011.0) 6.0,1.0-7 71 j, H 111 11411, -11 1 1 2 .0, 0.925).7; 7 IHF~I-0.4 0.3 0.2... I ......... I ..... I ..... ..1 -.1- .... -I 0.1 0.0 H I+rHi+/- Hr FM H [++I+I 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET)Axial Node 61 60 59 58 57 56 55 54 K(Z)0.9250 0.9275 0.9300 0.9325 0.9350 0.9375 0.9400 0.9425 Axial Node 53 52 51 50 49 48 47 46 KI(Z)0.9450 0.9475 0.9500 0.9525 0.9550 0.9575 0.9600 0.9625 Axial Node 45 44 43 42 41 40 39 38 K(Z)0.9650 0.9675 0.9700 0.9725 0.9750 0.9775 0.9800 0.9825 Axial Node 37 36 35 34 33 32 1 -31 TOP K(Z)0.9850 0.9875 0.9900 0.9925 0.9950 0.9975 1.0000 Core Height (ft) = (Node -1)

• 0.2 12 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU)1.450 1.400 1.350 1.300 N 1.250 1.200 1.150 1.100 1.050 1.000/J S I I N J 2N I I i 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Axial Node W (Z)58 --57 1.1794 56 1.1791 55 1.1789 54 1.1770 53 1.1718 52 1.1644 51 1.1583 50 1.1574 49 1.1591 48 1.1591 47 1.1561 46 1.1537 45 1.1558 CORE HEIGHT (FEET)Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z)1.1608 1.1624 1.1632 1.1643 1.1685 1.1735 1.1774 1.1832 1.1868 1.1880 1.1873 1.1847 1.1802 1.1740 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.1672 1.1610 1.1558 1.1509 1.1449 1.1383 1.1313 1.1233 1.1145 1.1057 1.0983 1.0920 1.0850 1.0790 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 TOP w(Z)1.0802 1.0849 1.0887 1.0931 1.0978 1.1023 1.1083 1.1171.1.1264 1.1343 1.1414 1.1490 Core Height (ft) = (Node -1)
• 0.2 13 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (5,000 MWD/MTU)1.450 1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000-I------i i F --- 4-I/ffiAffiLX-l+ I I~-I~-I-~0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET)TOP Axial Node W (Z)58 --57 1.3237 56 1.3102 55 1.2936 54 1.2735 53 1.2504 52 1.2241 51 1.1950 50 1.1746 49 1.1621 48 1.1518 47 1.1424 46 1.1329 45 1.1340 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(z)1.1437 1.1516 1.1533 1.1527 1.1498 1.1478 1.1479 1.1482 1.1469 1.1440 1.1401 1.1363 1.1329 1.1301 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.1281 1.1264 1.1241 1.1207 1.1163 1.1112 1.1054 1.0990 1.0926 1.0914 1.0915 1.0916 1.0914 1.0917 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 w(Z)1.0959 1.1062 1.1203 1.1343 1.1488 1.1618 1.1805 1. 2093 1. 2406 1. 2669 1.2886 1.3071 Core Height (ft) = (Node -1)
• 0.2 14 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (10,000 MWD/MTU)1.450 1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 I I I I i ! i i i i i I i I I A.F --- IV IHý-fýwl 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Axial Node W(Z)58 --57 1.2732 56 1.2689 55 1.2628 54 1.2563 53 1.2495 52 1.2420 51 1.2338 50 1.2251 49 1.2160 48 1.2069 47 1.1977 46 1.1879 45 1.1870 CORE HEIGHT (FEET)Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z)1.1897 1.1922 1.1900 1.1858 1.1792 1.1719 1.1669 1.1653 1.1634 1.1598 1.1545 1.1485 1.1438 1.1390 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.1348 1.1317 1.1284 1.1240 1.1185 1.1122 1.1052 1.0977 1.0912 1.0847 1.0773 1.0719 1.0712 1.0702 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 TOP w(Z)1.0689 1.0691 1.0747 1.0868 1.0986 1.1126 1.1276 1.1462 1.1718 1.1927 1.2088 1.2223 Core Height (ft) = (Node -1)
• 0.2 15 ERX-08-001, Rev. 0 COLR for CPNPP Unit 2 Cycle 11 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU)1.450 1.400 1.350 1.300 1.250 1 1200 1.150 1.100 1.050--ýF/- 71 1.000 I I I I 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM Axial Node W(Z)58 -61 57 1.2502 56 1.2492 55 1.2444 54 1.2344 53 1.2232 52 1.2161 51 1.2086 50 1.1980 49 1.1874 48 1.1808 47 1.1778 46 1.1799 45 1.1822 CORE HEIGHT (FEET)Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z)1.1852 1.1903 1.1948 1.1998 1.2074 1.2150 1.2211 1.2287 1. 2333 1.2348 1. 2336 1.2296 1.2230 1.2137 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)1.2037 1.1966 1.1927 1.1861 1.1775 1.1674 1.1556 1.1426 1.1285 1.1136 1.0983 1.0826 1.0672 1.0558 Axial Node 16 15 14 13 12 11 10 9 8 7 6 5 1 -4 TOP w(Z)1.0564 1.0649 1.0747 1.0846 1.0948 1.1051 1.1152 1.1249 1.1341 1.1425 1.1480 1.1534 Core Height (ft) = (Node -1)
• 0.2 16 ERX-08-001 Rev. 0 COLR for CPNPP Unit 2 Cycle 11 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 90 80 70 0 E-4 0 u P4, 60 so 40 30 20 10 0--40-30 10 0 10 AXIAL FLUX DIFFERENCE

(%)20 30 40 17 ERX-08-001, Rev. 0}}