L-2007-150, Submittal of Core Operating Limits Report: Difference between revisions

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{{#Wiki_filter:FPL September 27, 2007 L-2007-150 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-00001 Re: Turkey Point Unit 3 Docket No. 50-250 Core Operating Limits Report In accordance with Technical Specification 6.9.1.7, the attached Core Operating Limits Report is provided for Turkey Point Unit 3. These curves are applicable for Unit 3 Cycle 23.Should there be any questions, please contact James Connolly, Licensing Manager, at 305-246-6632.William Jdf;rsot.,V Site Vice President Turkey Point Nuclear Plant Attacluhent cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company Attachment to L-2007-150 Page 1 of 3 CORE OPERATING LIMITS REPORT -UNIT 3 CYCLE 23 The Technical Specifications (TS) affected by this report are: 3.1.3.2 Analog Rod Position Indication System 3.1.3.6 Control Rod Insertion Limits 3.2.1 Axial Flux Difference (AFD)3.2.2 Heat Flux Hot Channel Factor -FQ(Z)3.2.3 Nuclear Enthalpy Rise Hot Channel Factor -FAH The Control Rod Insertion Limits, AFD, FQ(Z), K(Z), and FAH have been developed using the NRC approved methodology specified in TS 6.9.1.7.TS 3.1.3.2 Analog Rod Position Indication System The All Rods Out position for all Shutdown Banks and Control Banks is defined to be 228 steps withdrawn.
{{#Wiki_filter:FPL September 27, 2007 L-2007-150 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-00001 Re:       Turkey Point Unit 3 Docket No. 50-250 Core Operating Limits Report In accordance with Technical Specification 6.9.1.7, the attached Core Operating Limits Report is provided for Turkey Point Unit 3. These curves are applicable for Unit 3 Cycle 23.
TS 3.1.3.6 Control Rod Insertion Limits The control rod banks shall be limited in physical insertion as shown on Figure 1 for All Rods Out = 228 steps withdrawn.
Should there be any questions, please contact James Connolly, Licensing Manager, at 305-246-6632.
TS 3.2.1 Axial Flux Difference The AFD limits are provided on Figure 2.TS 3.2.2 Heat Flux Hot Channel Factor -FQ(Z)[FQL= 2.5 0 K(Z) = 1.0 for 0 ft. < Z < 12 ft. where Z = core height.TS 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor RTP FAH =1.70 PFAH = 0.3  
William Jdf;rsot.,V Site Vice President Turkey Point Nuclear Plant Attacluhent cc:       Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company
!I Attachment to L-2007-150 Page 2 of 3 Turkey Figure 1 Point Unit 3 -Cycle 23 Rod Insertion Limits vs Thermal Power'U CL.2-0.0 a., 230 220 210 200 190 180 170 160 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0 AKU = 228 Steps Withdrawn, Overlap= 100 Steps:63.5, 28)_5.4i.221 _ _ _ __(. 00,1n1), Barnk C SBpnk D 0 10 20 30 40 50 60 Percent Reactor Power 70 80 90 100 Attachment to L-2007-150 Page 3 of 3 Axial Flux Figure 2 Difference as a Function of Rated Thermal Power Turkev Point Unit 3 -Cycle 23 120 100 Lu 0 (L-J I-0 CL 80 60 40 (-1q,100)
 
(+7,100)UNACCEPTABLE UISACCEPTA BLE OPERATION OPERATIO N (-30,50) OPERAC ON (+2 ,50)20 0-50-40-30-20-10 0 10 Axial Flux Difference
Attachment to L-2007-150 Page 1 of 3 CORE OPERATING LIMITS REPORT - UNIT 3 CYCLE 23 The Technical Specifications (TS) affected by this report are:
(%)20 30 40 50}}
3.1.3.2       Analog Rod Position Indication System 3.1.3.6       Control Rod Insertion Limits 3.2.1         Axial Flux Difference (AFD) 3.2.2         Heat Flux Hot Channel Factor - FQ(Z) 3.2.3         Nuclear Enthalpy Rise Hot Channel Factor - FAH The Control Rod Insertion Limits, AFD, FQ(Z), K(Z), and FAH have been developed using the NRC approved methodology specified in TS 6.9.1.7.
TS 3.1.3.2     Analog Rod Position Indication System The All Rods Out position for all Shutdown Banks and Control Banks is defined to be 228 steps withdrawn.
TS 3.1.3.6     Control Rod Insertion Limits The control rod banks shall be limited in physical insertion as shown on Figure 1 for All Rods Out = 228 steps withdrawn.
TS 3.2.1       Axial Flux Difference The AFD limits are provided on Figure 2.
TS 3.2.2       Heat Flux Hot Channel Factor - FQ(Z)
[FQL= 2 .5 0 K(Z) = 1.0 for 0 ft. < Z < 12 ft. where Z = core height.
TS 3.2.3       Nuclear Enthalpy Rise Hot Channel Factor RTP FAH =1.70 PFAH = 0.3
 
                                                                                                        !I Attachment to L-2007-150 Page 2 of 3 Figure 1 Turkey Point Unit 3 - Cycle 23 Rod Insertion Limits vs Thermal Power 230                         AKU = 228 Steps Withdrawn, Overlap= 100 Steps
:63.5, 28) 220                            _5.4i.221                       _).*
210 200 190 180
_   _     _        __(.                   00,1n1) 170
  'U CL 160 150                      , Barnk C                                               *
.2-140 0.
130 0  120 110 a.,
100 90 80                                                          SBpnk D 70 60 50 40 30 20 10 0
0         10     20       30           40       50             60 70 80       90       100 Percent Reactor Power
 
Attachment to L-2007-150 Page 3 of 3 Figure 2 Axial Flux Difference as Function of Rated Thermal Power a
Turkev Point Unit 3       - Cycle 23 120
(-1q,100)           (+7,100) 100 Lu80 0
(L
-J            UNACCEPTABLE                                                             UISACCEPTA BLE OPERATION                                                                 OPERATIO N 60 I-(-30,50)             OPERAC ON                   (+2 ,50) 0  40 CL 20 0
        -50       -40   -30         -20     -10         0           10       20    30        40  50 Axial Flux Difference (%)}}

Latest revision as of 03:01, 23 November 2019

Submittal of Core Operating Limits Report
ML072840055
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 09/27/2007
From: Jefferson W
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2007-150
Download: ML072840055 (4)
v • d • e


Text

FPL September 27, 2007 L-2007-150 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-00001 Re: Turkey Point Unit 3 Docket No. 50-250 Core Operating Limits Report In accordance with Technical Specification 6.9.1.7, the attached Core Operating Limits Report is provided for Turkey Point Unit 3. These curves are applicable for Unit 3 Cycle 23.

Should there be any questions, please contact James Connolly, Licensing Manager, at 305-246-6632.

William Jdf;rsot.,V Site Vice President Turkey Point Nuclear Plant Attacluhent cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company

Attachment to L-2007-150 Page 1 of 3 CORE OPERATING LIMITS REPORT - UNIT 3 CYCLE 23 The Technical Specifications (TS) affected by this report are:

3.1.3.2 Analog Rod Position Indication System 3.1.3.6 Control Rod Insertion Limits 3.2.1 Axial Flux Difference (AFD) 3.2.2 Heat Flux Hot Channel Factor - FQ(Z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - FAH The Control Rod Insertion Limits, AFD, FQ(Z), K(Z), and FAH have been developed using the NRC approved methodology specified in TS 6.9.1.7.

TS 3.1.3.2 Analog Rod Position Indication System The All Rods Out position for all Shutdown Banks and Control Banks is defined to be 228 steps withdrawn.

TS 3.1.3.6 Control Rod Insertion Limits The control rod banks shall be limited in physical insertion as shown on Figure 1 for All Rods Out = 228 steps withdrawn.

TS 3.2.1 Axial Flux Difference The AFD limits are provided on Figure 2.

TS 3.2.2 Heat Flux Hot Channel Factor - FQ(Z)

[FQL= 2 .5 0 K(Z) = 1.0 for 0 ft. < Z < 12 ft. where Z = core height.

TS 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor RTP FAH =1.70 PFAH = 0.3

!I Attachment to L-2007-150 Page 2 of 3 Figure 1 Turkey Point Unit 3 - Cycle 23 Rod Insertion Limits vs Thermal Power 230 AKU = 228 Steps Withdrawn, Overlap= 100 Steps

63.5, 28) 220 _5.4i.221 _).*

210 200 190 180

_ _ _ __(. 00,1n1) 170

'U CL 160 150 , Barnk C *

.2-140 0.

130 0 120 110 a.,

100 90 80 SBpnk D 70 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power

Attachment to L-2007-150 Page 3 of 3 Figure 2 Axial Flux Difference as Function of Rated Thermal Power a

Turkev Point Unit 3 - Cycle 23 120

(-1q,100) (+7,100) 100 Lu80 0

(L

-J UNACCEPTABLE UISACCEPTA BLE OPERATION OPERATIO N 60 I-(-30,50) OPERAC ON (+2 ,50) 0 40 CL 20 0

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

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