SBK-L-06099, Revision to Cycle 11 Core Operating Limits Report

Revision to Cycle 11 Core Operating Limits Report

ML061300092
Person / Time
Site:	Seabrook
Issue date:	05/01/2006
From:	St.Pierre G Florida Power & Light Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SBK-L-06099
Download: ML061300092 (19)

Text

FPL Energy Seabrook Station FPL Energy P.O. Box 300 Seabrook, NH 03874 Seabrook Station (603) 773-7000 May 1, 2006 Docket No. 50-443 SBK-L-06099 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 - 0001 Seabrook Station Revision to Cycle 11 Core Operating Limits Report FPL Energy Seabrook, LLC encloses the latest revision of the Cycle 11 Core Operating Limits Report (COLR) for Seabrook Station pursuant to Technical Specification 6.8.1.6.c. The COLR was incorporated into the Technical Requirements Manual (SSTR) and was revised with SSTR Revision 98. The COLR was changed based on License Amendment 107 which allows a conditional exemption from performing the end of life moderator temperature coefficient measurement.

Should you require further information regarding this report, please contact Mr. Paul V. Gurney, Reactor Engineering Supervisor, at (603) 773-7776.

Very truly yours, FPL Energy Seabrook, LLC Gene St. Pierre Site Vice President cc: S. J. Collins, NRC Region I Administrator G. E. Miller, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector 1

an FPL Group company

ENCLOSURE TO SBK-L-06099 1.0 Core Operating Limits Report This Core Operating Limits Report for Seabrook Station Unit 1, Cycle 11 has been prepared in accordance with the requirements of Technical Specification 6.8.1.6.

The Technical Specifications affected by this report are:

1) 2.2.1 Limiting Safety System Settings

2) 2.1 Safety Limits

3) 3.1.1.1 Shutdown Margin Limit for MODES 1, 2, 3, 4

4) 3.1.1.2 Shutdown Margin Limit for MODE 5

5) 3.1.1.3 Moderator Temperature Coefficient

6) 3.1.2.7 Minimum Boron Concentration for MODES 4, 5, 6

7) 3.1.3.5 Shutdown Rod Insertion Limit

8) 3.1.3.6 Control Rod Insertion Limits

9) 3.2.1 Axial Flux Difference

10) 3.2.2 Heat Flux Hot Channel Factor

11) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor

12) 3.2.5 DNB Parameters

13) 3.5.1.1 Boron Concentration Limits for MODES 1, 2, 3

14) 3.5.4 Boron Concentration Limits for MODES 1, 2, 3, 4

15) 3.9.1 Boron Concentration Limits for MODE 6 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 6.8.1.6.

2.1 Limiting Safety System Settings: (Specification 2.2.1) 2.1.1 Cycle Dependent Overtemperature AT Trip Setpoint Parameters and Function Modifier:

2.1.1.1 K1 = 1.210 2.1.1.2 K2 = 0.021/ OF 2.1.1.3 K3 = 0.0011 / psig T = Measured RCS Tavg (0 F ), and T' = Indicated RCS Tavg at RATED THERMAL POWER (Calibration temperature for AT instrumentation, < 589. 10 F).

Pl = Nominal RCS operating pressure, 2235 psig 6-1 .1 SSTR Rev. 98

2.1.1.4 Channel Total Allowance (TA) = N.A.

2.1.1.5 Channel Z = N.A.

2.1.1.6 Channel Sensor Error (S) = N.A.

2.1.1.7 Allowable Value - The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 0.5% of AT span. Note that 0.5% of AT span is applicable to OTAT input channels AT, Tavg and Pressurizer Pressure; 0.25% of AT span is applicable to Al.

2.1.1.8 f1(AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with nominal gains to be selected based on measured instrument response during plant startup tests calibrations such that:

(1) For qt - qb between -20% and +8%, f1(AI) 2 0; where qt and qb are percent RATED THERMAL POWER in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RATED THERMAL POWER; (2) For each percent that the magnitude of qt - qb exceeds -20%, the AT Trip Setpoint shall be automatically reduced by 2 2.87% of its value at RATED THERMAL POWER.

(3) For each percent that the magnitude of qt - qb exceeds +8%, the AT Trip Setpoint shall be automatically reduced by 2 1.71% of its value at RATED THERMAL POWER.

See Figure 5.

2.1.1.9 a} = 0 seconds 2.1.1.10 X2 = 0 seconds 2.1.1.11 X3 <2 seconds 2.1.1.12 X4 2 28 seconds 2.1.1.13 5 < 4 seconds 2.1.1.14 ¶6 < 2 seconds 6-1 .2 SSTR Rev. 98

2.1.2 Cycle Dependent Overpower AT Trip Setpoint Parameters and Function Modifier:

2.1.2.1 K4 = 1.116 2.1.2.2 K5 = 0.020 / 0 F for increasing average temperature and K5 = 0.0 for decreasing average temperature.

2.1.2.3 K6 = 0.00175 / OF for T > T" and K6 = 0.0 for T < T",

where:

T = Measured Tavg (OF ), and T1 l = Indicated Tayg at RATED THERMAL POWER (Calibration temperature for AT instrumentation, < 589.1 OF).

2.1.2.4 Channel Total Allowance (TA) = N.A.

2.1.2.5 Channel Z =N.A.

2.1.2.6 Channel Sensor Error (S) = N.A.

2.1.2.7 Allowable Value - The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 0.5% of AT span. Note that 0.5% of AT span is applicable to OPAT input channels AT and Tavg.

2.1.2.8 f2(AI) is disabled.

2.1.2.9 Al as defined in 2.1.1.9, above.

2.1.2.10 r2 as defined in 2.1.1.10, above.

2.1.2.11 X3 as defined in 2.1.1.11, above.

2.1.2.12 T6 as defined in 2.1.1.14, above.

2.1.2.13 A7 Ž 10 seconds. It is recognized that exactly equal values cannot always be dialed into the numerator and denominator in the protection system hardware, even if the nominal values are the same (10 seconds). Thus given the inequality sign in the COLR (greater than or equal to) the intent of the definition of this time constant applies primarily to the rate time constant (i.e. the Tau value in the numerator). The lag time constant (denominator Tau value) may be less than 10 seconds or less than the value of the numerator Tau value (e.g., if the numerator is set at 10.5, the denominator may be set to 10 or 9.5) and still satisfy the intent of the anticipatory protective feature.

6-1.3 SSTR Rev. 98

2.2 Safety Limits: (Specification 2.1.1) 2.2.1 In Modes I and 2, the combination of Thermal Power, reactor coolant system highest loop average temperature and pressurizer pressure shall not exceed the limits in Figure 6.

2.3 Shutdown Margin Limit for MODES 1, 2,3, and 4: (Specification 3.1.1.1) 2.3.1 The Shutdown Margin shall be greater than or equal to 1.3% AK/K, in MODES 1, 2 and 3.

2.3.2 The Shutdown Margin shall be greater than or equal to 2.3% AUK, in MODE 4.

2.3.3 The Boric Acid Storage System boron concentration shall be greater than or equal to 7000 ppm.

2.4 Shutdown Margin Limit for MODE 5: (Specification 3.1.1.2) 2.4.1 The Shutdown Margin shall be greater than or equal to 2.3% AK/K.

2.4.2 The RCS boron concentration shall be greater than or equal to 2000 ppm when the reactor coolant loops are in a drained condition.

2.4.3 The Boric Acid Storage System boron concentration shall be greater than or equal to 7000 ppm.

2.5 Moderator Temperature Coefficient: (Specification 3.1.1.3) 2.5.1 The Moderator Temperature Coefficient (MTC) shall be less positive than

+3.024 x 10-5AK/K/F for Beginning of Cycle Life (BOL), All Rods Out (ARO), Hot Zero Thermal Power conditions.

2.5.2 MTC shall be less negative than -5.5 x 10-4 AK/KIF for End of Cycle Life (EOL),

ARO, Rated Thermal Power conditions.

2.5.3 The 300 ppm ARO, Rated Thermal Power MTC shall be less negative than -4.6 x 104 AK/K/'F (300 ppm Surveillance Limit).

2.5.4 The Revised Predicted near-EOL 300 ppm MTC shall be calculated using the algorithm contained in WCAP 13749-P-A:

Revised Predicted MTC = Predicted MTC + AFD Correction - 3 PCM/degree F If the Revised Predicted MTC is less negative than the SR 4.1.1.3.b 300 ppm surveillance limit and all the benchmark data contained in the surveillance procedure are met, then an MTC measurement in accordance with SR 4.1.1.3.b is not required to be performed.

6-1.4 SSTR Rev. 98

2.6 Minimum Boron Concentration for MODES 4, 5, 6 (Specification 3.1.2.7) 2.6.1 The Boric Acid Storage System boron concentration shall be greater than or equal to 7000 ppm.

2.7 Shutdown Rod Insertion Limit: (Specification 3.1.3.5) 2.7.1 The shutdown rods shall be fully withdrawn. The fully withdrawn position is defined as the interval within 225 steps withdrawn to the mechanical fully withdrawn position inclusive.

2.8 Control Rod Insertion Limits: (Specification 3.1.3.6) 2.8.1 The control rod banks shall be limited in physical insertion as specified in Figure 1.

Control Bank A shall be at least 225 steps withdrawn.

2.9 Axial Flux Difference: (Specification 3.2.1) 2.9.1 The indicated AFD must be within the Acceptable Operation Limits specified in Figure 2.

2.10 Heat Flux Hot Channel Factor: (Specification 3.2.2) 2.10.1 FRTPQ =2.50 2.10.2 K(Z) is specified in Figure 3.

2.10.3 W(Z) is specified in Figures 4.1 to 4.4 and in Table 1.

The W(Z) data is applied over the cycle as follows:

BU < 150 MWD/MTU, linear extrapolation of 150 and 3000 MWD/MTU W(Z) data 150 < BU < 6500 MWD/MTU, quadratic interpolation of 150, 3000, and 10000 MWD/MTU data 6500 < BU <19000 MWD/MTU, quadratic interpolation of 3000, 10000, and 19000 MWD/MTU W(Z) data BU > 19000 MWDIMTU, linear extrapolation of 10000 and 19000 MWD/MTU W(Z) data Note: The FQ(Z) surveillance exclusion zone is specified by Technical Specification 4.2.2.2.g 2.10.4 The FMQ(Z) penalty factor is 1.02 6-1 .5 SSTR Rev. 98

2.11 Nuclear Enthalpy Rise Hot Channel Factor: (Specification 3.2.3) 2.11.1 FNA*H < FNAH(RTP) x ( I + PF x ( 1 - P))

where P = THERMAL POWER / RATED THERMAL POWER.

2.11.2.a For FNAH measured by the fixed incore detectors:

FNAH(RTP) = 1.585.

2.11.2.b For FNAH measured by the movable incore detectors:

FNAH(RTP) = 1.587.

2.11.3 Power Factor Multiplier for FNAH = PF = 0.3.

2.12 DNB Parameters (Specification 3.2.5) 2.12.1 The Reactor Coolant System Tavg shall be less than or equal to 595.1 degrees F.

2.12.2 The Pressurizer Pressure shall be greater than or equal to 2185 PSIG.

Note: Technical Specification Bases 3/4.2.5, "DNB Parameters" indicates that the limits on DNB-related parameters assure consistency with the normal steady-state envelope of operation assumed in the transient and accident analyses. Operating procedures include allowances for measurement and indication uncertainty so that the limits in the COLR for Tavg and pressurizer pressure are not exceeded. Consistent with the Bases, the values of these DNB parameters are the limiting Tavg and pressurizer pressure assumed in the transient and accident analyses.

2.13 Accumulator Boron Concentration Limits for MODES 1,2,3 (Specification 3.5.1.1) 2.13.1 Each Accumulator shall have a boron concentration between 2300 and 2600 ppm.

2.14 Refueling Water Storage Tank Boron Concentration Limits for MODES 1, 2, 3, 4 (Specification 3.5.4) 2.14.1 The RWST shall have a boron concentration between 2400 and 2600 ppm.

2.15 Refueling Boron Concentration Limits for MODE 6 (Specification 3.9.1) 2.15.1 The Refueling Boron Concentration during ORIO and Cyclel 1 shall be greater than or equal to 2140 ppm.

2.15.2 The Boric Acid Storage System boron concentration shall be greater than or equal to 7000 ppm.

6-1.6 SSTR Rev. 98

Figure 1: Control Bank Insertion Limits Versus Thermal Power 225-20M c

E 175 _

B 150_

in 0L 42 125 CO

=0 100 0

CL 75 Im 50 0

5o-25-0-

Qo0 0.2 0.4 0.6 0.8 1.0 Fraction of Rated Themal Power 6-1 .7 SSTR Rev. 98

Figure 2: Axial Flux Difference Operating Limits Versus Thermal Power Note: %DI = %Al 6-1 .8 SSTR Rev. 98

Figure 3: K(Z) Versus Core Height 12--_

I -e 0.8 0.4 _ _

02 0 L 4 I I I. I. I I 4I I 0 1 2 3 4 5 6 7 8 9 10 11 12 ComHItft' 6-l1.9 SSTR Rev. 98

Figure 4.1: W(Z) Versus Core Height 150 MWD/MTU 1.5 ,,,, .,., I.,,,, ., , .,,, ... . , sr ,'srr, 1111111111 I I 1111111111111111111111111111I .1111111111111111 1.4 ............ -

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0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (Feet) 6-1 .10 SSTR Rev. 98

Figure 4.2: W(Z) Versus Core Height 3000 MWD/MTU 1.5 . . . . , ...'.r 1 ,r-

.- . r.. .r.-...

-v.

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0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (Feet) 6-1.11 SSTR Rev. 98

Figure 43: W(Z) Versus Core Height 10,000 MWD/MTU 1.5 ~-

r.,,, . . . . . , -. . . . . ,r ,.. . .r . l. .r . . . . . . . . . . . ..,

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0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (Feet) 6-1 .12 SSTR Rev. 98

Figure 4.4: W(Z) Versus Core Height 19,000 MWDIMTU 1.5 , _, . . . .. . . I - .

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0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (Feet) 6-1 .13 SSTR Rev. 98

Figure 5: f1(AI) Function

-40.91, 60 +43.09, 60

-60 -40 -20 0 20 40 60 E- &I Band (percentJ~f 6-1.14 SSTR Rev. 98

Figure 6: Safety Limits 680 -

660 - -

U-

-a640 - -~< ~

I-E='620 - - pp1 0

Cen C-,

Fraction of Rated Thermal Power 6-1 .15 SSTR Rev. 98

Table 1: W(ZBU) versus Axial Height HEIGHT (Z) W(Z,BU) W(Z,BU) W(Z,BU) W(ZBU)

(Feet) 150 3000 10000 19000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU

<1.0 1.0000 1.0000 1.0000 1.0000 1.2 1.3103 1.3068 1.2786 1.2817 1.4 1.2980 1.2933 1.2675 1.2690 1.6 1.2844 1.2780 1.2548 1.2547 1.8 1.2695 1.2613 1.2405 1.2392 2.0 1.2534 1.2433 1.2262 1.2227 2.2 1.2368 1.2246 1.2126 1.2058 2.4 1.2208 1.2069 1.1991 1.1886 2.6 1.2057 1.1928 1.1853 1.1714 2.8 1.1911 1.1798 1.1714 1.1564 3.0 1.1753 1.1683 1.1657 1.1441 3.2 1.1628 1.1601 1.1610 1.1376 3.4 1.1581 1.1551 1.1560 1.1375 3.6 1.1562 1.1499 1.1506 1.1374 3.8 1.1541 1.1438 1.1444 1.1401 4.0 1.1515 1.1388 1.1397 1.1443 4.2 1.1486 1.1356 1.1363 1.1473 4.4 1.1452 1.1328 1.1322 1.1497 4.6 1.1413 1.1294 1.1277 1.1521 4.8 1.1369 1.1255 1.1227 1.1537 5.0 1.1320 1.1210 1.1173 1.1544 5.2 1.1263 1.1161 1.1113 1.1539 5.4 1.1208 1.1106 1.1049 1.1524 5.6 1.1159 1.1037 1.0989 1.1517 5.8 1.1190 1.1028 1.0984 1.1542 6.0 1.1297 1.1080 1.1060 1.1624 6.2 1.1413 1.1147 1.1185 1.1727 6.4 1.1517 1.1201 1.1306 1.1813 6.6 1.1613 1.1247 1.1421 1.1895 6.8 1.1700 1.1289 1.1526 1.1982 7.0 1.1773 1.1336 1.1618 1.2059 7.2 1.1832 1.1426 1.1697 1.2117 7.4 1.1874 1.1507 1.1760 1.2158 7.6 1.1897 1.1574 1.1806 1.2179 7.8 1.1904 1.1634 1.1837 1.2181 8.0 1.1882 1.1692 1.1844 1.2164 8.2 1.1856 1.1747 1.1842 1.2127 8.4 1.1868 1.1789 1.1862 1.2071 8.6 1.1872 1.1821 1.1869 1.1991 8.8 1.1887 1.1874 1.1879 1.1917 6-1.16 SSTR Rev. 98

Table 1: W(Z,BU) versus Axial Height HEIGHT (Z) W(ZBU) W(Z,BU) W(ZBU) W(Z,BU)

(Feet) 150 3000 10000 19000 MWD/MTU MWD/MTU MWD/MTU MWD/MTU 9.0 1.1956 1.1991 1.1922 1.1914 9.2 1.2129 1.2177 1.2016 1.1916 9.4 1.2439 1.2407 1.2212 1.1952 9.6 1.2769 1.2719 1.2463 1.2092 9.8 1.3067 1.3084 1.2693 1.2233 10.0 1.3317 1.3450 1.2908 1.2449 10.2 1.3538 1.3772 1.3146 1.2760 10.4 1.3770 1.4037 1.3402 1.3033 10.6 1.3944 1.4318 1.3630 1.3265 10.8 1.4084 1.4542 1.3814 1.3458

>I 1.0 1.0000 1.0000 1.0000 1.0000 Note: The FQ(Z) surveillance exclusion zone is specified by Technical Specification 4.2.2.2.g 6-1.17 SSTR Rev. 98