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

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-200800809 Log # TXX-08086 Ref. #

Tech. Spec. 5.6.5 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 tiIZ 4.

Date:s ZZod~

Daniel E.

1frozak 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..................

TABLE OF CONTENTS LIST OF TABLES LIST OF FIGURES ii iii iv V

SECTION 1.0 CORE OPERATING LIMITS REPORT 2.0 OPERATING LIMITS 2.1 SAFETY LIMITS 2.2 SHUTDOWN MARGIN 2.3 MODERATOR TEMPERATURE COEFFICIENT 2.4 ROD GROUP ALIGNMENT LIMITS 2.5 SHUTDOWN BANK INSERTION LIMITS...............

2.6 CONTROL BANK INSERTION LIMITS 2.7 PHYSICS TESTS EXCEPTIONS MODE 2 2.8 HEAT FLUX HOT CHANNEL FACTOR 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 2.10 AXIAL FLUX DIFFERENCE 2.11 REACTOR TRIP SYSTEM INSTRUMENTATION 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE NUCLEATE BOILING LIMITS.......................

2.13 BORON CONCENTRATION

3.0 REFERENCES

PAGE 1

2 2

2 2

3 3

4 4

4 5

6 6

FROM 7

8 8

iii ERX-08-001, Rev.

1

COLR for CPNPP Unit 2 Cycle 11 LIST OF TABLES No Tables Listed TABLE PAGE 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

[ F Q(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 FR TPAH =

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)

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 Percent of Rated Thermal Power (3458 MWt) 140 9

ERX-08-001, Rev.

1

COLR for CPNPP Unit 2 Cycle 11 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240 220 200 I

I I (25.3,2j18)

B1ANK B I I~h~

I I (79.6,218)I EI I

I L 180 "4

.4 160 41

-,-I

  • 140 120 z0 H '

m 100 0

80 o

60 I

[TI))]

]!

.ii

'[

lI.

rr?

IIIIrrlIrr

-- (0,164)

/

'*~--

i.

.(

00,146)

BANK C

  • ,,01

/

/V BAN D

(0,49) - -

3 1 0 40 20 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 are at a position within the interval of 218 withdrawn, inclusive.

control rods and 231 steps

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 1.0 0.9 0.8 III 11I (0.011.0)

(6.0 11111111 1 -4 o,

0,0.925) 1H ffli H

I Hill o0.7 0.6 0

0.5 0.4 0.3 0.2 0.1

-- - F-*

-F I -I I

I I

I

]I I [ I

]. IIII.

I I II

-I -* -*

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

0.0 1 1 11 1L 0

1 BOTTOM Axial Node 61 0

60 0

59 0

58 0

57 0

56 0

55 0

54 0

2 3

4 5

6 7

8 9

10 CORE HEIGHT (FEET)

K(Z)

.9250

.9275

.9300

.9325

.9350

.9375

.9400

.9425 Axial Node 53 52 51 50 49 48 47 46 K (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 11 12 TOP K (Z) 0.9850 0.9875 0.9900 0.9925 0.9950 0.9975

-1.0000 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 1.250 1.200 1.150 1.100 1.050 1.000 fL L

--::I

/

-\\-I

-1 i

i I

i I-0 1

2 3

4 5

6 7

8 9

10 11 12 BOTTOM CORE HEIGHT (FEET)

TOP Axial Node 58 -

61 57 56 55 54 53 52 51 50 49 48 47 46 45 w(Z) 1.2807 1.2840 1.2879 1.2905 1.2878 1.2800 1.2662 1.2583 1.2536 1.2469 1.2408 1.2337 1.2310 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.2321 1.2363 1.2345 1.2304 1.2239 1.2170 1.2121 1.2085 1.2054 1.2030 1.1997 1.1937 1.1858 1.1750 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z) 1.1680 1.1677 1.1703 1.1709 1.1700 1.1679 1.1645 1.1599 1.1543 1.1479

1. 1406 1.1331 1.1273 1.1254 Axial Node 16 15 14 13 12 11 10 9

8

.7 6

5 1 -

4 w(Z) 1.1270 1.1326 1.1393

1. 1458
1. 1524
1. 1598 1.1693 1.1798
1. 1893 1.1982
1. 2053 1.2080 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 1.300 1.250 1* 200 1.150 1.100 1.050 1.000 I

r I

A I

-1+--

I 0

1 2

3 4

5 6

7 8

9 10 11 12 BOTTOM CORE HEIGHT (FEET)

Axial Node 58 -

61 57 56 55 54 53 52 51 50 49 48 47 46 45 W(Z) 1.3804 1.3743

1. 3634 1.3489 1.3295 1.3059 1.2795 1.2522 1.2255 1.1978 1.1697 1.1565 1.1573 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.1629 1.1658 1.1644 1.1621 1.1616 1.1611 1.1594 1.1587 1.1560 1.1514 1.1447 1.1372 1.1329 1.1301 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w(Z)
1. 1279 1.1270 1.1271 1.1295 1.1314 1.1325 1.1329
1. 1326 1.1321
1. 1332
1. 1353 1.1368 1.1380
1. 1386 Axial Node 16 15 14 13 12 11 10 9

8 7

6 5

1 -

4 TOP w(Z) 1.1489 1.1699 1.1921 1.2147 1.2374 1.2598 1.2815 1.3019 1.3206 1.3375 1.3517 1.3614 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 1.250 1.200 1.150 1.100 1.050 1.000

/

I 7

I I

I I

I

~4zj\\

! -I-0 1

2 3

4 5

6 7

8 9

10 11 12 BOTTOM CORE HEIGHT (FEET)

Axial Node 58 -

61 57 56 55 54 53 52 51 50 49 48 47 46 45 w(Z) 1.3937 1.3848 1.3722 1.3567 1.3385 1.3180 1.2956 1.2685 1.2497 1.2421 1.2293 1.2125 1.2049 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w (Z) 1.2033 1.1990 1.1931 1.1880 1.1859 1.1840 1.1812 1.1802 1.1770 1.1713 1.1638 1.1544 1.1444 1.1386 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w (Z) 1.1348 1.1319

1. 1307
1. 1296 1.1276 1.1245 1.1209 1.1165 1.1114 1.1104 1.1118 1.1151 1.1177 1.1202 Axial Node 16 15 14 13 12 11 10 9

8 7

6 5

1 - 4 TOP w(Z) 1.1221 1.1292 1.1416 1.1533 1.1670 1.1811 1.1946

1. 2080 1.2218 1.2339 1.2437
1. 2496 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 1.250 1.200 1.150 1.100 1.050 1.000 f-

  1. --A A

~4z4zzz I.

i. I

-I, 0

1 2

3 4

5 6

7 8

9 10 11 12 BOTTOM CORE HEIGHT (FEET)

\\j,

Axial Node 58 -

61 57 56 55 54 53 52 51 50 49 48 47 46 45 w(Z) 1.3358 1.3340 1.3279 1.3169 1.3028 1.2868 1.2689 1.2543 1.2475 1.2420 1.2319 1.2369 1.2478 Axial Node 44 43 42 41 40 39 38 37 36 35 34 33 32 31 w(Z) 1.2584 1.2672 1.2702

1. 2708 1.2678 1.2640 1.2603
1. 2536 1.2542 1.2543
1. 2494 1.2419 1.2314 1.2173 Axial Node 30 29 28 27 26 25 24 23 22 21 20 19 18 17 w (Z) 1.2046 1.1996 1.1993
1. 1966 1.1919 1.1855 1.1773 1.1678 1.1570 1.1453 1.1329
1. 1200 1.1076 1.1024 Axial Node 16 15 14 13 12 11 10 9

8 7

6 5

1 -

4 TOP w (Z) 1.1081 1.1222 1.1348 1.1480 1.1612 1.1742 1.1869 1.1989 1.2101 1.2202 1.2282

1. 2320 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 90 80 70 0

I::

0 U

60 50 40 30

(-9.5,100)

(.,00)

UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION ACCEPTABLE OPERATION

(-2 5

,5 S(-25, 50) 2~o 20 10 n

-40

-30

-20

-10 0

10 AXIAL FLUX DIFFERENCE

(%)

20 30 40 16 ERX-08-001, Rev.

1

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