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MONTHYEARML0524504262005-09-21021 September 2005 License Amendment No. 196, Extension of the Reactor Coolant System Pressure/Temperature Curve Limits Project stage: Other ML0526603212005-09-21021 September 2005 Tech Spec Pages for Amendment No. 196, Extension of the Reactor Coolant System Pressure/Temperature Curve Limits Project stage: Other ML0531200952005-11-23023 November 2005 Letter, Correction to Safety Evaluation for Amendment No. 196 Regarding Extension of Reactor Coolant System Pressure and Temperature Curves Project stage: Approval 2005-11-23
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Category:ACQ-Amendment of Solicitation/Modification of Contract
MONTHYEARML0526603212005-09-21021 September 2005 Tech Spec Pages for Amendment No. 196, Extension of the Reactor Coolant System Pressure/Temperature Curve Limits 2005-09-21
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MONTHYEARML0526603212005-09-21021 September 2005 Tech Spec Pages for Amendment No. 196, Extension of the Reactor Coolant System Pressure/Temperature Curve Limits 2005-09-21
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MONTHYEARL-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML22013A3172022-01-12012 January 2022 Trp 030 - St. Lucie SLRA Breakout Questions_Fuel Oil ML22013A3162022-01-12012 January 2022 Trp 020 - St. Lucie SLRA Breakout Questions_Occw ML22013A3342022-01-11011 January 2022 TRP16 - St. Lucie SLRA Breakout Questions_Pwr Internals ML22013A3072022-01-11011 January 2022 Trp 084 St Lucie SLRA - Ssnial Scclombreakoutq ML22012A3912022-01-11011 January 2022 Scoping and Screening 2.3.3.2 & 2.3.3.4 St. Lucie SLRA - Breakout Questions ML22012A2632022-01-10010 January 2022 Trp 3 - St. Lucie Psl SLRA Breakout Question Reactor Head Closure Stud Bolting ML22010A0972022-01-0707 January 2022 Trp 038 Psl Internal Surfaces Breakout Questions - Allik ML22010A1002022-01-0707 January 2022 Trp 033 Psl Selective Leaching Breakout Questions - Allik ML21356A5772021-12-22022 December 2021 Slar Breakout Questions - Fire Protection Scoping and Screening ML22013A3032021-12-21021 December 2021 Trp 143.2 St Lucie SLRA - Breakout Questions Non-Class 1 Fatigue ML22013A3042021-12-21021 December 2021 Trp 143.3 St Lucie SLRA - Breakout Questions EAF ML22013A3022021-12-21021 December 2021 Trp 143.1 St Lucie SLRA - Breakout Questions Class 1 Fatigue ML22013A3012021-12-21021 December 2021 TRP60 St. Lucie SLRA - Breakout Questions Fatigue Monitoring ML22013A2972021-12-21021 December 2021 Trp 77 St. Lucie SLRA - Breakout Questions Corrosion Structural ML22013A2962021-12-21021 December 2021 Trp 74 St. Lucie SLRA - Breakout Questions ML22013A3052021-12-21021 December 2021 Trp 143.4 St Lucie SLRA - Breakout Questions HELB ML22013A2952021-12-21021 December 2021 Trp 47 St. Lucie SLRA - Breakout Questions ML22013A2942021-12-21021 December 2021 Trp 46 St. Lucie SLRA - Breakout Questions Structures Monitoring ML22013A2922021-12-21021 December 2021 Trp 41 St. Lucie SLRA - Breakout Questions ML22013A2882021-12-21021 December 2021 Trp 23 & 147.8 St. Lucie SLRA - Breakout Questions Cranes AMP-TLAA ML22013A2842021-12-21021 December 2021 Trp 18 St. Lucie SLRA - Breakout Questions Bolting Integrity ML22013A2822021-12-21021 December 2021 SLRA - Breakoutt Questions Corrosion OE ML21354A8372021-12-20020 December 2021 Trp 11 St. Lucie SLRA Breakout Questions ML21351A2382021-12-17017 December 2021 Trp 148.1 St. Lucie SLRA - Breakout Questions for TLAA Section 4.7.1 Rev. 1 ML21351A2412021-12-17017 December 2021 Trp 15 St. Lucie SLRA - Internal Coatings Breakout Questions - Allik ML21351A2392021-12-17017 December 2021 Trp 14 St. Lucie SLRA - Buried Pipe Breakout Questions - Allik.Docx L-2021-137, GL 2004-02 Debris Transport Calculation Non-Conservatism2021-07-23023 July 2021 GL 2004-02 Debris Transport Calculation Non-Conservatism L-2018-067, Units 1 and 2 - Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Units 1 and 2 - Submittal of Joint Plant Access Shared Information Table L-2016-109, Official Service List Changes and Distribution for Safeguards Information and Official Use Only-Security-Related Information2016-05-11011 May 2016 Official Service List Changes and Distribution for Safeguards Information and Official Use Only-Security-Related Information ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15224B4492015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15236A0762015-09-0303 September 2015 Enclosure, Revised St Lucie Tables-LQ-W ML15231A4122015-08-21021 August 2015 FPL St. Lucie Capture Summary 2015 ML15231A4172015-08-21021 August 2015 Power Plant Causal Turtles L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2015-03-24024 March 2015 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2014-340, RAI Reply - Fourth Ten-Year Interval Unit 2 Relief Request No. 42014-11-0606 November 2014 RAI Reply - Fourth Ten-Year Interval Unit 2 Relief Request No. 4 L-2013-067, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20122013-02-14014 February 2013 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2012 ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML12073A1512012-03-0606 March 2012 NRR E-mail Capture - St. Lucie Discharge Headwall Project L-2010-096, Extended Power Uprate Data for NRC Confirmatory EPU Analyses2010-06-0404 June 2010 Extended Power Uprate Data for NRC Confirmatory EPU Analyses L-2009-078, Extended Power Uprate Data for NRC Confirmatory EPU Analyses2009-04-0202 April 2009 Extended Power Uprate Data for NRC Confirmatory EPU Analyses L-2008-236, Extended Power Uprate, Data for NRC Confirmatory EPU Analyses2008-10-29029 October 2008 Extended Power Uprate, Data for NRC Confirmatory EPU Analyses L-2008-178, Fourth Ten-Year Interval In-Service-Test Program Submittal RAI Reply to Relief Request PR-042008-08-0505 August 2008 Fourth Ten-Year Interval In-Service-Test Program Submittal RAI Reply to Relief Request PR-04 ML0808506472008-03-19019 March 2008 NDE Report on PSL-1 Pressurizer Nozzles ML0810502642008-03-19019 March 2008 NDE Report, on PSL-1 Pressurizer Nozzles, Attachment 2 L-2008-018, Transmittal of Pressurized Butt Weld Alloy Report, and Mitigation Status and Swol Inspection Results2008-02-21021 February 2008 Transmittal of Pressurized Butt Weld Alloy Report, and Mitigation Status and Swol Inspection Results L-2008-002, Corporate Merger of Decommissioning Trustee2008-01-0303 January 2008 Corporate Merger of Decommissioning Trustee ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0526603212005-09-21021 September 2005 Tech Spec Pages for Amendment No. 196, Extension of the Reactor Coolant System Pressure/Temperature Curve Limits 2024-03-13
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Text
1 00 80 0 60 T __AXlllllIlllllllllmmu Li cc: 40 20 Cooldown u
80 100 120 140 160 180 200 220 Tc - INDICATED REACTOR COOLANTTEMP., F FIGURE 3.1-1b MAXIMUM ALLOWABLE HEATUP AND COOLDOWN RATES, SINGLE HPSI PUMP IN OPERATION (Applicable to 35 EFPY) I ST. LUCIE - UNIT 1 3/4 1-9a Amendment No. 8-, 404,444, 196
FIGURE 3.4-2a ST. LUCIE UNIT I P/T LIMITS, 35 EFPY I HEATUP AND CORE CRITICAL 2500
-ISOTHERMAL::
.TO 50°0F/HR '-
I .
W1_ 01 2000 cn EL L
co =I _
Cl) 111 w
cn I bUU En LOWEST
- SERVICE II N
w -_ TEMPERATURE:
a_ ___ 0 =
c') - 190°F CORE CRITICAL-w I, ~
~IiA cc 0 1000 Mp:~=
0 ALLOWABLE HEATUP RATES
_0 RATE, °F/HR TEMR LIMIT, °F z
ISOTHERMAL 50 AT ALL C') TEMPERATURES 0l snn I-.
I 50° F/HR:
MIN. BOLTUP TE 80° F 0
0 100 200 400 500 TC - INDICATED RCSTEMPERATURE, OF Limiting Material: Lower Shell Axial Welds (Ht. #305424)
Limiting ART Values at 35 EFPY: 1/4T, 191°F 3/4T, 137°F ST. LU(CIE-UNIT 1 ST. UC 3/4 4-23a men ment No. 4,
.mendme6nt No.4-7 28, 84, 444, 2~,~4.404 44,196
FIGURE 3.4-2b ST. LUCIE UNIT I PIT LIMITS, 35 EFPY I COOLDOWN AND INSERVICE TEST 2500 INSERVICE HYDROSTATIC TEST 2000 Li EC CO, cc: 1500 ___ LOWEST EL
___ SERVICE 1000 F/HR TO
___ TEMPERATURE ISOTHERMAL N
__ _ 190 0F cn ci) cc:
0 1000 0
5 z
__ ISOTHERMAL CO) 0 cc 500 20 F/HR.
- 0
= 30 F/HR
-. 0 40 F/HR:
_ 500 FIHR
= 70 F/iHR MIN. BOLTUP TEMPERATURE 80 0 F 100 FAIR 0
0 100 200 300 400 500 TC -INDICATED RCS TEMPERATURE, 0F Limiting Material: Lower Shell Axial Welds (Ht. #305424)
Limiting ART Values at 35 EFPY: 1/4T, 191OF 3/4T, 137-F ST. LU(CIE - UNIT 1 3/4 4-23b Ame ndment No. 47, 28, 84, 404, 444, 196
FIGURE 3.4-3 ST. LUCIE UNIT 1, 35 EFPY MAXIMUM ALLOWABLE COOLDOWN RATES il rS I tt ' t I I I IIi i 100
-RATE, °F/HR _ TEMP.LIMIT, °F1=9 I j
_____ 20 _ _ <125 I
!III iI I f 30 125-145 80 40 50 10075 145-165 165-185 185-195 El I I__ -
i i
11 I
1Ii I I , i=:
I 100 >195 I I I LA 0
60 z
0 Vi 0
-j 0 40 0 _ _ _ _ _
0 I.- -* 9.
20 0
80 100 120 140 160 180 200 TC - INDICATED REACTOR COOLANT TEMPERATURE, OF NOTE: A MAXIMUM COOLDOWN RATE OF 100°F/HR IS ALLOWED AT ANY TEMPERATURE ABOVE 195°F ST. LUCIE - UNIT 1 3/4 4-23c Amendment No. 4-, 28.84.
404, 444, 196