L-2006-247, Core Operating Limits Report
ML063420117 | |
Person / Time | |
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Site: | Turkey Point |
Issue date: | 11/27/2006 |
From: | Jones T Florida Power & Light Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
L-2006-247 | |
Download: ML063420117 (4) | |
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Category:Letter type:L
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L-2007-129, Emergency Response Data System (ERDS) Maintenance2007-08-20020 August 2007 Emergency Response Data System (ERDS) Maintenance L-2007-095, CFR 50.59 Summary Report, Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering June 13, 2005 Through December 9, 20062007-06-0808 June 2007 CFR 50.59 Summary Report, Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering June 13, 2005 Through December 9, 2006 L-2006-247, Core Operating Limits Report2006-11-27027 November 2006 Core Operating Limits Report L-2006-241, Significance Determination Regarding a Loss of Power to Operating Residual Heat Removal Pump - Additional Information Regarding Gothic Analysis2006-10-17017 October 2006 Significance Determination Regarding a Loss of Power to Operating Residual Heat Removal Pump - Additional Information Regarding Gothic Analysis L-2006-180, Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire2006-07-31031 July 2006 Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire L-2006-131, Wastewater Permit Number FL0001562, Request for Minor Revision Notification2006-05-22022 May 2006 Wastewater Permit Number FL0001562, Request for Minor Revision Notification ML0614301742006-05-0505 May 2006 Biological Opinion Regarding the American Crocodile at Turkey Point L-2006-088, Core Operating Limits Report2006-03-29029 March 2006 Core Operating Limits Report ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0503803942004-03-0505 March 2004 E-mail from P. Fillion to C. Payne - Turkey Point Report Input ML0503803832004-02-0606 February 2004 E-mail from P. Fillion to C. Payne, K. O'Donohue - Evaluation of Valves - Revision ML0503803752004-02-0404 February 2004 E-mail from P. Fillion to C. Payne, K. O'Donohue - Analysis of Two Valves ML0504703632003-09-0909 September 2003 9/9/03 Turkey Point Condition Report 03-1330-1 L-2003-068, Order (EA-03-009) Relaxation Request, Examination Coverage of Reactor Pressure Vessel Head Penetration Nozzles - Supplemental Data2003-03-14014 March 2003 Order (EA-03-009) Relaxation Request, Examination Coverage of Reactor Pressure Vessel Head Penetration Nozzles - Supplemental Data 2023-08-21 |
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0 FPL NOV 2 7 2006 L-2006-247 10 CFR 50.36 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: Turkey Point Unit 4 Docket No. 50-251 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 4. These curves are applicable for Unit 4 Cycle 23.
Should there be any questions, please contact James Connolly, Licensing Manager, at 305-246-6632.
Very truly yours, Ter . ionesý Site Vice President Turkey Point Nuclear Plant OIH Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 74oi)i an FPL Group company
Attachment to L-2006-247 Page 1 of 3 CORE OPERATING LIMITS REPORT - UNIT 4 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 230 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 = 230 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)
QIFL = 2.50 K(Z) = 1.0 for 0 ft.
- Z < 12 ft. where Z = core height.
TS 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor RT FS?'= 1.70 PFA&H = 0.3
S Attachment to L-2006-247 Page 2 of 3 Figure 1 Turkey Point Unit 4 - Cycle 23 Rod Insertion Limits vs Thermal Power In ARO = 230 Steps Withdrawn, Overlap = 102 Steps 21 2C C
1Ei 30 0
4- 10--
a.
I) 4-Ii, C
.2 0*-,K(..05)
Io----------------------
0-I C - --- '__az 4-110 - -. . .. ... .. . ..
'ft 0
- - I a.
0 1001-- " (1 5, - .. . ,./ i 11 0
Rl--90]---Lli-B* nk D 70 60 50 40 30 - -......
-I00 (I
20 10 0
0 10 20 30 40 50 60 70 80 90 100 Percent Reactor Power
Attachment to L-2006-247 Page 3 of 3 Figure 2 Axial Flux Difference as a Function of Rated Thermal Power 120 Turkey Point Unit 4 - Cycle 23
- (-1,100)(+7,100) 100 80 UNACCEPTABLE UACCEPTABLE a
LU OPERATION OPERATIO w 60 3-ACCEPTABLE-(-30,50) OPERAI ION (2,0 40 U-20 0
-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (%)