CP-200800809, Submittal of Core Operating Limits Reports

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Submittal of Core Operating Limits Reports
ML081700093
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 06/09/2008
From: Blevins M
Luminant Power
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-200800809, TXX-08086
Download: ML081700093 (22)
v • d • e


Text

Mike Blevins Luminant Power um Luminant Executive Vice President

& Chief Nuclear Officer Mike.Blevins @Luminant.com 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-200800809 Ref. # Tech. Spec. 5.6.5 Log # TXX-08086 June 9, 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 Revision 1 to 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:/iric/ <')'2aiL W. Madden Director, Oversight & Regulatory Affairs Enclosure - Unit 2, Cycle 11 Core Operating Limits Report (COLR), May 2008 (Revision 1) 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 A1 Callaway

  • Comanche Peak
  • Diablo Canyon - Palo Verde
  • Wolf Creek

1RX-08-001, Rev. 1 CPNPP UNIT 2 CYCLE 11 CORE OPERATING LIMITS REPORT May 2008 PJoathan M. Ralston "ae incipal Engineer, Westinghouse Electric Co.

Reviewed: I Ž Daniel E.

tiIZ 1frozak 4 . Date:s ZZod~

I f Principal EngineeZ, Westinghouse Electric Co.

Reviewed: ________________ ae et"*vin

^. RoTind Principal Engineer, Westinghouse Electric Co.

Approved: Kate:

amen oatwright, Manager Westi house Engineering Services - 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 ERX-08-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 11 TABLE OF CONTENTS DISCLAIMER .................. ii TABLE OF CONTENTS ........ iii 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 ERX-08-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 11 LIST OF TABLES TABLE PAGE No Tables Listed iv ERX-08-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 11 LIST OF FIGURES FIGURE PAGE 1 REACTOR CORE SAFETY LIMITS ............................... 9 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER ............ 10 3 K(Z) - NORMALIZED F0 (Z) AS A FUNCTION OF CORE HEIGHT ............................................. 11 4 ýW(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) ........................................... 12 5 W(Z) AS A FUNCTION OF CORE HEIGHT -

(5,000 MWD/MTU) .......................................... 13 6 W(Z) AS A FUNCTION OF CORE HEIGHT -

(10,000 MWD/MTU) .. ....................................... 14 7 W(Z) AS A FUNCTION OF CORE HEIGHT -

(20,000 MWD/MTU) ........................................ 15 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER . .................................. 16 v ERX-08-001, Rev. 1

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 SAFETY LIMITS LCO 3.1.1 SHUTDOWN MARGIN LCO 3.1.3 MODERATOR TEMPERATURE COEFFICIENT LCO 3.1.4 ROD GROUP ALIGNMENT LIMITS LCO 3.1.5 SHUTDOWN BANK INSERTION LIMITS LCO 3.1.6 CONTROL BANK INSERTION LIMITS LCO 3.1.8 PHYSICS TESTS EXCEPTIONS - MODE 2 LCO 3.2.1.2 HEAT FLUX HOT CHANNEL FACTOR LCO 3.2.2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LCO 3.2.3.2 AXIAL FLUX DIFFERENCE LCO 3.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LCO 3.4.1 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS LCO 3.9.1 BORON CONCENTRATION 1 ERX-08-001, Rev. 1

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 Keff < 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. 1

COLR for CPNPP Unit 2 Cycle 11 2.3.2 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/lF.

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. 1

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)

RTP FQ 2.8.1 FQ (Z) -5 [K(Z)] for P > 0.5 P

FRTP FQ FQ (Z) - [K(Z)] for P _ 0.5

0.5 where

P = THERMAL POWER RATED THERMAL POWER 4 ERX-08-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 11 RTP 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 [ FQ(Z) / K(Z) I, F W(z) shall be increased by a constant factor of 2% to increase FQW(Z) per Surveillance Requirement 3.2.1.2.2.a.

This requirement is for all cycle burnups.

2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNAHI (LCO 3.2.2) 2.9.1 FNAH 5 FRTPH [1 + PFAH (l-P)]

where: P = THERMAL POWER RATED THERMAL POWER 2.9.2 FRTPAH = 1.41 for Region 1-13B and lIB Fuel Assemblies FRTPAH = 1.60 for all other Fuel Assembly Regions 2.9.3 PFA = 0.3 5 ERX-08-001, Rev. 1

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; Ki = .1.15 K2 = 0.0139 /°F K3 = 0.00071 /psig T°o = indicated loop specific T, at Rated Thermal Power, °F P1

  • 2235 psig T, 10 sec T2 5 3 sec f 1 (Aq) = -2.78 {(qt-qb) + 18%} when (qt-q,) 5 -18% RTP

= 0% when -18% RTP < (qt-q,) < +10.0% RTP

= 2.34 {(q,-qb) - 10.0%} when (qt-qb) * +10.0% RTP 6 ERX-08-001, Rev. 1

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

  • 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 5 592 °F (4 channels) 591 °F (3 channels)

The RCS average temperature limits correspond to the analytical limit of 595.2 OF 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. 1

COLR for CPNPP Unit 2 Cycle 11 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be 2 408,000 gpm.

2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be 2 408,000 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. 1

COLR for CPNPP Unit 2 Cycle 11 Figure 1 Reactor Core Safety Limits 680 660 640 620 600 580 560 0 20, 40 60 80 100 120 140 Percent of Rated Thermal Power (3458 MWt) 9 ERX-08-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 11 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 I I I EI I I~h~

220 (25.3,2j18) I I (79.6,218)I 200 I ." I L B1ANK B 180 I [TI))]  !! ]! .ii '[  ! lI. rr? IIIIrrlIrr "4

-- (0,164) /

41 160

.4

-,-I

'*~-- i .- - .( 00,146)

  • 140 BANK C *,,01
* / /V 120 z

H0 '

m 100 0

80

BAN D  :

o 60 (0,49) - - - - --- --

40 20 31 0 - - - - -

0 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.

10 ERX-08-001, Rev. 1

-I

COLR for CPSES Unit 2 Cycle 11 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 III 11I 1.0 (0.011.0) 11111111 1-4 (6.0 o,

0.9 0,0.925) 1H ffli H I Hill 0.8 o0.7

- -F

-- I --I F-* * -I I - I 0.6 ]I II [ I ].IIII. I I II

-I -*-*-II-I-I

-- -* I - -- --

0 0.5

- 0.4 0.3 0.2 0.1 0.0 1 1 11 1L 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node K(Z) Node K (Z) Node K (Z) Node K (Z) 61 0 .9250 53 0. 9450 45 0.9650 37 0.9850 60 0 .9275 52 0. 9475 44 0. 9675 36 0.9875 59 0 .9300 51 0. 9500 43 0.9700 35 0.9900 58 0 .9325 50 0. 9525 42 0. 9725 34 0.9925 57 0 .9350 49 0. 9550 41 0. 9750 33 0.9950 56 0 .9375 48 0. 9575 40 0.9775 32 0.9975 55 0 .9400 47 0.9600 39 0. 9800' 1 - 31 -1.0000 54 0 .9425 46 0.9625 38 0. 9825 Core Height (ft) = (Node - 1)

  • 0.2 11 ERX-08-001, Rev. 1

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 fLL --::I 1.250 1.200

/

-\-I 1.150 -1 1.100 1.050 i i I  ! ! i I-1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node w(Z) Node w(Z) Node w(Z) Node w(Z) 58 - 61 44 1.2321 30 1.1680 16 1.1270 57 1.2807 43 1.2363 29 1.1677 15 1.1326 56 1.2840 42 1.2345 28 1.1703 14 1.1393 55 1.2879 41 1.2304 27 1.1709 13 1. 1458 54 1.2905 40 1.2239 26 1.1700 12 1. 1524 53 1.2878 39 1.2170 25 1.1679 11 1. 1598 52 1.2800 38 1.2121 24 1.1645 10 1.1693 51 1.2662 37 1.2085 23 1.1599 9 1.1798 50 1.2583 36 1.2054 22 1 .1543 8 1. 1893 49 1.2536 35 1.2030 21 1.1479 .7 1.1982 48 1.2469 34 1.1997 20 1. 1406 6 1. 2053 47 1.2408 33 1.1937 19 1 .1331 5 1.2080 46 1.2337 32 1.1858 18 1.1273 1 - 4 45 1.2310 31 1.1750 17 1.1254 Core Height (ft) = (Node - 1)

  • 0.2 12 ERX-08-001, Rev. 1

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 I r I A I 1.300 -1+--

1.250 1*200 I

1.150 1.100 1.050 1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node W(Z) Node w(Z) Node w(Z) Node w(Z) 58 - 61 44 1.1629 30 1. 1279 16 1.1489 57 1.3804 43 1.1658 29 1.1270 15 1.1699 56 1.3743 42 1.1644 28 1.1271 14 1.1921 55 1. 3634 41 1.1621 27 1.1295 13 1.2147 54 1.3489 40 1.1616 26 1.1314 12 1.2374 53 1.3295 39 1.1611 25 1.1325 11 1.2598 52 1.3059 38 1.1594 24 1.1329 10 1.2815 51 1.2795 37 1.1587 23 1. 1326 9 1.3019 50 1.2522 36 1.1560 22 1.1321 8 1.3206 49 1.2255 35 1.1514 21 1. 1332 7 1.3375 48 1.1978 34 1.1447 20 1. 1353 6 1.3517 47 1.1697 33 1.1372 19 1.1368 5 1.3614 46 1.1565 32 1.1329 18 1.1380 1 - 4 45 1.1573 31 1.1301 17 1. 1386 Core Height (ft) = (Node -1 )

  • 0.2.

13 ERX-08-001, Rev. 1

COLR for CPNPP Unit 2 Cycle 11 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT t (10,000 MWD/MTU) 1.450 1.400 1.350 1.300 /

I 1.250

  • 1.200 1.150 I I I I I 7

~4zj\

1.100 1.050

! -I-1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node w(Z) Node w (Z) Node w (Z) Node w(Z) 58 - 61 44 1.2033 30 1.1348 16 1.1221 57 1.3937 43 1.1990 29 1.1319 15 1.1292 56 1.3848 42 1.1931 28 1. 1307 14 1.1416 55 1.3722 41 1.1880 27 1. 1296 13 1.1533 54 1.3567 40 1.1859 26 1.1276 12 1.1670 53 1.3385 39 1.1840 25 1.1245 11 1.1811 52 1.3180 38 1.1812 24 1.1209 10 1.1946 51 1.2956 37 1.1802 23 1.1165 9 1. 2080 50 1.2685 36 1.1770 22 1.1114 8 1.2218 49 1.2497 35 1.1713 21 1.1104 7 1.2339 48 1.2421 34 1.1638 20 1.1118 6 1.2437 47 1.2293 33 1.1544 19 1.1151 5 1. 2496 46 1.2125 32 1.1444 18 1.1177 1 - 4 45 1.2049 31 1.1386 17 1.1202 Core Height (ft) = (Node - 1)

  • 0.2 14 ERX-08-001, Rev. 1

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 f-

  1. --A 1.250 A

~4z4zzz 1.200 1.150 I . i . I -I, 1.100 1.050 1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP

\j ,

Axial Axial Axial Axial Node w(Z) Node w(Z) Node w (Z) Node w (Z) 58 - 61 44 1.2584 30 1.2046 16 1.1081 57 1.3358 43 1.2672 29 1.1996 15 1.1222 56 1.3340 42 1.2702 28 1.1993 14 1.1348 55 1.3279 41 1. 2708 27 1. 1966 13 1.1480 54 1.3169 40 1.2678 26 1.1919 12 1.1612 53 1.3028 39 1.2640 25 1.1855 11 1.1742 52 1.2868 38 1.2603 24 1.1773 10 1.1869 51 1.2689 37 1. 2536 23 1.1678 9 1.1989 50 1.2543 36 1.2542 22 1.1570 8 1.2101 49 1.2475 35 1.2543 21 1.1453 7 1.2202 48 1.2420 34 1.2494 20 1.1329 6 1.2282 47 1.2319 33 1.2419 19 1. 1200 5 1. 2320 46 1.2369 32 1.2314 18 1.1076 1 - 4 45 1.2478 31 1.2173 17 1.1024 Core Height (ft) = (Node - 1)

  • 0.2 15 ERX-08-001 Rev. 1

COLR for CPNPP Unit 2 Cycle 11 FIGURE 8 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100

- (-9.5,100) - - - - - (.,00) - -- - -

90 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION 80

- - - - ACCEPTABLE

- OPERATION 70 0

60 I:: 50 (-2 5 ,5 S(-25, 50) - 2~o 40 0

U 30 20 10 n

-40 -30 -20 -10 0 10 20 30 40 AXIAL FLUX DIFFERENCE (%)

16 ERX-08-001, Rev. 1

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