ML070510605

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Units 1 and 2, Unit 1 Cycle 21 Core Operating Limits Report - Revision 1, Unit 2 Cycle 18 Core Operating Limits Report - Revision 1
ML070510605
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 02/19/2007
From: George B
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-07-0339
Download: ML070510605 (31)
v • d • e


Text

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 February 19, 2007 SOUTHERN C O M P ~

A Energy to Serve Your WorldsM Docket Nos.: 50-348 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Unit 1 Cycle 2 1 Core Operating Limits Report - Revision I Unit 2 Cycle 18 Core Operating Limits Report - Revision 1 Ladies and Gentlemen:

In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company (SNC) submits Revision 1 to the enclosed Core Operating Limits Reports (COLRs) for Farley Nuclear Plant Unit 1 Cycle 21 and Unit 2 Cycle 18. These revisions incorporate a change to the Table 4 exclusion zone from the top and bottom 15% of the core to an exclusion zone from the top and bottom 8% of the core.

This letter contains no NRC commitments. If there are any questions, please advise.

Sincerely,

~ a n a ~ Nuclear

&, Licensing

Enclosure:

FNP Core Operating Limits Report Unit 1- Cycle 21, October 2006, Revision 1 FNP Core Operating Limits Report Unit 2- Cycle 18, October 2006, Revision I

U.S. Nuclear Regulatory Commission NL-07-0339 Page 2 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Plant Farley Mr. D. H. Jones, Vice President - Engineering RTY PE: CFA04.054; LC# 14538 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Ms. K. R. Cotton. NRR Project Manager - Farley Mr. C. A. Patterson, Senior Resident Inspector - Farley

Joseph M. Farley Nuclear Plant - Units 1 and 2 Unit 1 Cycle 21 Core Operating Limits Report - Revision 1 Unit 2 Cycle 18 Core O~eratingLimits Report - Revision 1 Enclosure FNP Core Operating Limits Report Unit 1- Cycle 21, October 2006, Revision 1 FNP Core Operating Limits Report Unit 2- Cycle 18, October 2006, Revision 1

SOUTHERN C O M M A

En- to Serve Yovr WmW Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 1 Cycle 21 October 2006 Revision 1

COLR for FNP Unit 1 Cycle 21 Revision 1 Page 1 of 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 CYCLE 21 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. I SHUTDOWN MARGIN - MODES 1 and 2 (with ken2 1)

The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN - MODES 2 (with bn< I), 3 , 4 and 5 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank lnsertion 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 Channnel Factor - F,N, 3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) Setpoint Parameter Values for Table 3.3.1-1 3.4.1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration

COLR for FNP Unit 1 Cycle 21 Revision 1 Page 2 of 13 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 NRC-approved methodologies, including those specified in Technical Specification 5.6.5.

2.1 SHUTDOWN MARGIN - MODES 1 and 2 (with keff2 1.0) (Technical Requirement 13.1. l )

2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Aklk.

2.2 SHUTDOWN MARGIN - MODES 2 (with bff< 1.0). 3. 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (bff < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Aklk.

2.2.2 Mode 5 - 'The SHUTDOWN MARGIN shall be greater than or equal to 1.O percent Aklk.

2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOUAROIHZP-MTC shall be less than or equal to +0.7 x l o 4 Aklkl°F for power levels up to 70 percent RTP with a linear ramp to 0 Aklkl°F at 100 percent RTP.

The EOUAROIRTP-MTC shall be less negative than -4.3 x lo4 AklWF.

2.3.2 The MTC Surveillance limits are:

The 300 ppmlARO1RTP-MTC should be less negative than or equal to -3.65 x 1o4 Aklkl°F.

The 100 ppmlAROlRTP-MTC should be less negative than -4.0 x 1oV4 AklWF.

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

COLR for FNP Unit 1 Cycle 21 Revision 1 Page 3 of 13 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 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.

2.6 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3.2.1)

F,RTP 2.6.1 FQ(Z)I-* K(Z) for P > 0.5 P

r RTP FQ(Z)5* ' K(Z) for P I 0.5 0.5 THERMALPOWER where: P=

RATED THERMALPOWER 2.6.3 K(Z) is provided in Figure 2.

2.6.4 FQ(Z)I F,RTP

  • K(Z) for P > 0.5 P
  • W (Z) for P 2 0.5 2.6.5 W(Z) values are provided in Table 4.

2.6.6 The FQ(Z) penalty factors are provided in Table 1

COLR for FNP Unit 1 Cycle 21 Revision 1 Page 4 of 13 2.7 Nuclear Enthal~yRise Hot Channel Factor - F$ (Specification 3.2.2)

THERMAL POWER where: P =

RATED THERMAL POWER 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 3.

2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm.'

2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1.1) 2.10.1 In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 4.

2.1 1 Reactor Trip System lnstrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.1 1.1 The Reactor Trip System lnstrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) setpoint parameter values for TS Table 3.3.1-1 are listed in COLR Tables 2 and 3.

1 This concentration bounds the condition of kef5 0.95 (all rods in less the most reactive rod) and subcriticality (aJ rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B depletion.

COLR for FNP Unit 1 Cycle 21 Revision 1 Page 5 of 13 2.12 RCS DNB Parameters for Pressurizer Pressure, RCS Average Tem~erature, and RCS Total Flow Rate (Specification 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure 2 2209 psig;
b. RCS average temperature I580.3 OF; and
c. The minimum RCS total flow rate shall be 2 263,400 GPM when using the precision heat balance method and 2 264,200 GPM when using the elbow tap method.

Table 1 FQ(Z)Penalty Factor Cycle FdZ)

Burnup Penalty (MWDIMTU) Factor 5051 1.020 5255 1.022 5460 1.025 5664 1.021 5868 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 OO/ of the surveillance interval per SR 3.0.2) starting from the burnup at which the FQ(Z)was determined.
2. Linear interpolation is adequate for intermediate cycle burnups.
3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.

Table 2 Reactor Trip System Instrumentation Overtemperature AT (OTAT)

Setpoint Parameter Values T' 5577.2 OF P' = 2235 psig K1= 1.17 K2 = 0.017 I OF K3 = 0.000825 I psi r l 2 30 sec 721 4 sec r 4 = 0 sec r 5 5 6 sec fl(AI) = -2.48 (23 + (qt - qb)) when (qt - qb) I -23 % RTP 0 % of RTP when -23 % RTP < (qt -qb) I 15 % RTP 2.05 {(qt - qb) - 15) when (qt - qb) > 15 % RTP

COLR for FNP Unit 1 Cycle 21 Revision 1 Page 8 of 13 Table 3 Reactor Trip System Instrumentation Overpower AT (OPAT)

Setpoint Parameter Values b=1.10 K5 = 0.02 1 OF for increasirrg Tavg K6 = 0.00109 / OF when T > T" K5 = 0 / OF for decreasing Tavg Kg=O/OFwhenTsT" rg 2 10 sec

~4 = 0 sec r5 I 6 sec

~g 5 6 sec f2(A1) = 0 % RTP for all AI

COLR for FNP Unit 1 Cycle 21 Revision 1 Page 9 of 13 Table 4 RAOC W(Z)

Top and bottom 5 uhl pointn excluded per Teebnkd SI#cincation B33.1.

COLR for FNP Unit 1 Cycle 21 Revision 1 Page 10 of 13 Figure 1 Rod Bank Insertion Limits versus Rated 'Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive Fully Withdrawn shall be the condition where control rods are at a position within the interval r 225 and s 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-to-tip distance of 128 steps.

Figure 2 K(Z) - Normalized FdZ) as a Function of Core Height Core Height (ft.1 K(Z) 0.000 1.ooo 6.000 1.OOO '

12.000 1.ooo Fa = 2.50 4 6 8 Core Height (feet)

COLR for FNP Unit 1 Cycle 21 Revision 1 Page 12 of 13 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC

(-12, 100) (+9,100) 1

- UNACCEPTABLE A UNACCEPTABLE -

OPERATION OPERATION l1 I

\

ACCEPTABLE I

OPERATION I \

(-30, 50) (+24,50) 50 40 -30 -20 -10 0 10 20 30 40 50 60 Axial Flux Difference (Delta I) %

Figure 4 Reactor Core Safety Limits

+2425 psig

+2235 psig 6--1985 psig 0.0 0.2 0.4 0.6 0.8 I.O I.2 Power (Fraction of RATED THERMAL POWER)

Energy to Serve Your World' Joseph M. Farley Nuclear Plant Core Operating Limits Report Unit 2 Cycle 18 October 2006 Revision 1

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 1 of 13 1.0 CORE OPERATING LIMITS REPORT This Core Operating I-imits Report (COLR) for FNP UNIT 2 CYCLE 18 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 1 and 2 (with ken21)

The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN - MODES 2 (with keff < I ) , 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)

N 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor - F~~

3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) Setpoint Parameter Values for Table 3.3.1-1 3.4.1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 2 of 13 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 NRC-approved methodologies, including those specified in Technical Specification 5.6.5.

2.1 SHUTDOWN MARGIN - MODES 1 AND 2 (with keff21.0) (Technical Requirement 13.1. l )

2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent AWk.

2.2 SHUTDOWN MARGIN - MODES 2 (with keff< 1.01, 3, 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (ken< 1.0), 3 and 4 - The SHU-TDOWN MARGIN shall be greater than or equal to 1.77 percent AWk.

2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent Auk.

2.3 Moderator Ternperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOUAROIHZP-MTC shall be less than or equal to +0.7 x 1o4 Ak/kI0F for power levels up to 70 percent RTP with a linear ramp to 0 Ak/W°F at 100 percent RTP.

The EOUAROIRTP-MTC shall be less negative than -4.3 x 10-4 Ak/W°F.

2.3.2 The MTC Surveillance limits are:

The 300 ppmlAROlRTP-MTC should be less negative than or equal to -3.65 x 10" Ak/W°F.

The 100 ppmlAROlRTP-MTC should be less negative than

-4.0 x 1o4 AWWOF.

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

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 3 of 13 2.4 Shutdown Bank lnsertion 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 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.

2.6 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3.2.1) 2.6.1 FQ(Z)I - FT

  • K(Z) for P > 0.5 P

FT FQ(Z) 5 -* K(Z) for P 20.5 0.5 THERMAL POWER where: P =

RATEDTHERMAL POWER 2.6.3 K(Z) is provided in Figure 2.

FoRTP* K(Z) 2.6.4 FQ(Z)I for P > 0.5 P

  • W(Z)

F:~

  • K(Z)

F z < for P I 0.5 Q( ) - 0.5

  • W(Z) 2.6.5 W(Z) values are provided in Table 4.

2.6.6 The FQ(Z) penalty factors are provided in Table 1.

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 4 of 13 2.7 Nuclear Enthalpv Rise Hot Channel Factor - F: (Specification 3.2.2)

THERMALPOWER where: P =

RATED THERMAL POWER 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 3.

2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm.'

2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1.1) 2.10.1 In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 4.

2.1 1 Reactor Trip Svstem lnstrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System lnstrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) setpoint parameter values for TS Table 3.3.1-1 are listed in COLR Tables 2 and 3.

1 This concentration bounds the condition of keff--< 0.95 (all rods in less the most reactive rod) and subcriticality (aJ rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B" depletion.

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 5 of 13 2.12 RCS DNB Parameters for Pressurizer Pressure, RCS Averaae Temperature, and RCS Total Flow Rate (Specification 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure 2 2209 psig;
b. RCS average temperature I580.3OF; and
c. The minimum RCS total flow rate shall be 2 263,400 GPM when usirrg the precision heat balance method and 2 264,200 GPM when using the elbow tap method.

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 6 of 13 Table 1 FQ(Z)Penalty Factor Cycle FdZ)

Burnup Penalty (MWDIMTU) Factor 4849 1.020 5053 1.021 5258 1.022 5462 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) starting from the burnup at which the FQ(Z)was determined.
2. Linear interpolation is adequate for intermediate cycle burnups.
3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 7 of 13 Table 2 Reactor Trip System Instrumentation Overtemperature AT (OTAT)

Setpoint Parameter Values Tr 1577.2"F Pr = 2235 psig 2 30 sec T2< 4 sec T4= 0 sec T5 I6 sec T6 I6 sec fl(AI) = -2.48 (23 + (qt - qb)) when (qt - qb) 5 -23Oh RTP 0% of RTP when -23% RTP c (qt -qb) I 15% RTP 2.05 ((qt - qb) - 15) -

when (qt qb) > 15% RTP

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 8 of 13 Table 3 Reactor Trip System Instrumentation Overpower AT (OPAT)

Setpoint Parameter Values b=1.10 Kg = 0.02PF for increasing Tav, Kg = 0.00109/°F when T > T" Kg = Ol°F for decreasing Tavg Kg = Ol°F when T I T" z 3 2 10 sec z4 = 0 sec zg I6 sec z6 s 6 sec f2(A1) = 0% RTP for all dl

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 9 of 13 Table 4 RAOC W(Z)

Top mmd bottom 5 mxW pdnb cxduded per Tccbnkal Spccllk.tbn 8321. I

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 10 of 13 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 0 -

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.O Fraction of RATED THERMAL POWER Fully Withdrawn shall be the condition where control rods are at a position within the interval 2 225 and 1 231 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-to-tip distance of 128 steps.

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 11 of 13 Figure 2 K(Z) Normalized FQ(Z)as a Function of Core Height I

Core H e i ~ h[ft.)

t K(Z) 0.000 1.ooo 6.000 1.OOO 12.000 1.ooo I

I Fa = 2.50 I

0 2 4 6 8 10 12 Core Height (feet)

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 12 of 13 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC I

(-12,100) (+9,100)

I 1

- UNACCEPTABLE 1 UNACCEPTABLE -

OPERATION OPERATION l1 r

ACCEPTABLE I OPERATION f \

(-30,50) (+24, 50)

I

-60 -50 40 -30 -20 -10 0 10 20 30 40 50 60 Axial Flux Difference (Delta I) %

COLR for FNP Unit 2 Cycle 18 Revision 1 Page 13 of 13 Figure 4 Reactor Core Safety Limits

( U 2235 psig )

+1985 psig 560 0.0 0.2 0.4 0.6 0.8 1O

. 1.2 Power (Fraction of RATED THERMAL POWER)

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