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Category:Calculation
MONTHYEARML18299A1182018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.304, Revision 3, Fatigue Crack Growth Evaluation, October 12, 2018 ML18299A1172018-10-12012 October 2018 Framatome Calculation No. 32-9280712, Rev. 002, Tp CRDM Lower Joint Environmentally Assisted Fatigue Dated October 12, 2018 (Non-Proprietary) L-2014-044, Offsite Dose Calculation Manual for Gaseous and Liquid Effluents, Revision 202013-12-19019 December 2013 Offsite Dose Calculation Manual for Gaseous and Liquid Effluents, Revision 20 L-2008-130, Supplement to 2007 Annual Radioactive Effluent Release Report2008-05-30030 May 2008 Supplement to 2007 Annual Radioactive Effluent Release Report ML0608600782006-03-13013 March 2006 Attachment 3 Calculation PTN-BFJR-06-001 Phase 3 SDP for Turkey Point B AFW Pump Failure ML18227B7861978-01-0303 January 1978 Letter Transmitting Procedure for Evaluation of Maximum Setpoint Overshoot Heat Input Transient & Supplement to July 1977 Report of Pressure Mitigating Systems, Transient Analysis Results ML18227B0151977-01-0303 January 1977 Submit Revised ECCS Calculations Supplemental Information Performed Using Rated Power Level of 2200 Mwt to Improve Clarity ML18227C9041977-01-0303 January 1977 Letter Transmitting Copy of Revised ECCS Calculations Report Forwarded on 12/30/1976 with Several Revised Pages to Improve Clarity L-76-438, Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt1976-12-30030 December 1976 Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt 2018-10-12
[Table view] Category:Graphics incl Charts and Tables
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 ML22054A1382022-02-16016 February 2022 February 24, 2022 ITS Public Meeting Material - Florida Power and Light L-2021-138, GL 2004-02 Debris Transport Calculation Non-Conservatism2021-07-15015 July 2021 GL 2004-02 Debris Transport Calculation Non-Conservatism ML19221B5832019-07-25025 July 2019 Biological Opinion for Turkey Point Nuclear Plant Units 3 and 4 License Renewal L-2019-020, Subsequent License Renewal Application Environmental Report Environmental Authorizations Updated Information2019-01-23023 January 2019 Subsequent License Renewal Application Environmental Report Environmental Authorizations Updated Information ML18187A0282018-07-23023 July 2018 Numeric Nutrient Criteria Violations ML18187A0322018-07-23023 July 2018 Water Gradient Charts 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 ML15054A0372015-02-23023 February 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Fire PRA Facts and Observations for Turkey Point Nuclear Generating Stations, Units 3 and 4 ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 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 L-2005-141, 10 CFR 50.55a Request for Mechanical Clamping Device Used as Piping Pressure Boundary2005-06-20020 June 2005 10 CFR 50.55a Request for Mechanical Clamping Device Used as Piping Pressure Boundary ML0501202612005-01-12012 January 2005 December Monthly Report on the Status of Open TIAs Assigned to NRR ML0434802422004-12-29029 December 2004 November Monthly Report on the Status of Open TIAs Assigned to NRR ML18227B2811978-09-27027 September 1978 Submit Appendix a, Revised ECCS Analysis L-78-297, Supplemental Information on Request to Amend Facility Operating Licenses Additional Information1978-09-13013 September 1978 Supplemental Information on Request to Amend Facility Operating Licenses Additional Information L-78-271, 08/16/1978 Letter Thermal & Hydraulic Safety Limits1978-08-16016 August 1978 08/16/1978 Letter Thermal & Hydraulic Safety Limits L-78-264, 08/09/1978 Letter Order for Amendment to Facility Operating Licenses DPR-31 & DPR-411978-08-0909 August 1978 08/09/1978 Letter Order for Amendment to Facility Operating Licenses DPR-31 & DPR-41 L-78-217, 06/22/1978 Letter Proposed Modifications to Technical Specification Figure 2.1-1, Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation1978-06-22022 June 1978 06/22/1978 Letter Proposed Modifications to Technical Specification Figure 2.1-1, Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation ML18227B7861978-01-0303 January 1978 Letter Transmitting Procedure for Evaluation of Maximum Setpoint Overshoot Heat Input Transient & Supplement to July 1977 Report of Pressure Mitigating Systems, Transient Analysis Results L-77-381, Letter Transmitting Revision 1 to Steam Generator Repair Report Which Was Forwarded on 9/20/19771977-12-20020 December 1977 Letter Transmitting Revision 1 to Steam Generator Repair Report Which Was Forwarded on 9/20/1977 ML18227D2661977-05-10010 May 1977 05/10/1977 Letter Groundwater Monitoring Data Report No. 59 for May 1977 Monitoring Period for E-Series Wells, and Results of Transmissivity Test for Quarter Ending March 1977 L-77-106, 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty1977-04-0404 April 1977 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty ML18227B0141977-02-0202 February 1977 Response to Request for Additional Information on ECCS Reevaluation Supplemental Information ML18227D2911977-01-0707 January 1977 Submit Refueling Information (Cycle 4) Which Will Not Involve Any Unreviewed Safety Questions ML18227D2901977-01-0707 January 1977 Submit Refueling Information (Cycle 4) Which Will Not Involve Any Unreviewed Safety Questions ML18227C9041977-01-0303 January 1977 Letter Transmitting Copy of Revised ECCS Calculations Report Forwarded on 12/30/1976 with Several Revised Pages to Improve Clarity L-76-438, Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt1976-12-30030 December 1976 Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt L-77-434, Answers to Question Nos. 2 and 7 and Revised Answers to Questions 8 and 9 Pertaining to the Steam Generators Tube Integrity Supplemental Information1976-12-30030 December 1976 Answers to Question Nos. 2 and 7 and Revised Answers to Questions 8 and 9 Pertaining to the Steam Generators Tube Integrity Supplemental Information L-76-225, Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a Tech Spec, Concerning Cask Handling1976-06-24024 June 1976 Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a Tech Spec, Concerning Cask Handling L-76-201, Letter Submits Proposed Amendment to Facility Operating License with Supplemental Information Submitted as Appendix B of Spent Fuel Storage Facility Modification Safety Analysis Report1976-05-25025 May 1976 Letter Submits Proposed Amendment to Facility Operating License with Supplemental Information Submitted as Appendix B of Spent Fuel Storage Facility Modification Safety Analysis Report L-76-199, Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ...1976-05-21021 May 1976 Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ... ML18227A9811975-09-30030 September 1975 Submit Appendix Nos. a, B, C, D, E, F, G, H, I, J. L-75-246, Responding to Letter of 5/15/75, Letter Furnishing Analyses & Other Relevant Info to Determine Potential for Occurrence & Potential Consequences of Secondary System Fluid Flow Instability (Water Hammer)1975-07-0303 July 1975 Responding to Letter of 5/15/75, Letter Furnishing Analyses & Other Relevant Info to Determine Potential for Occurrence & Potential Consequences of Secondary System Fluid Flow Instability (Water Hammer) ML18227A4671975-03-21021 March 1975 Letter Reporting Abnormal Occurrence No. 251-75-4 of Lateral Restraints for Spent Fuel Racks Broken, in Unit 4 on 3/12/1975 ML18227D1101975-02-0707 February 1975 Letter Re Description of Cycle 2 Reload Fuel 2024-03-13
[Table view] Category:Letter
MONTHYEARL-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report IR 05000250/20240102024-05-0101 May 2024 Design Basis Assurance Inspection Programs Inspection Report 05000250/2024010 and 05000251/2024010 and Notice of Violation L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 ML24087A1992024-04-0505 April 2024 Achp Section 106 Letter Re Notice of Availability of the Final Environmental Impact Statement for Turkey Point Units 3 & 4 Subsequent License Renewal Application ML24096A2142024-04-0505 April 2024 Ltr. to David Hill, Principal Chief, the Muscogee (Creek) Nation, Re., Section 106 Letters for Turkey Point ML24096A2162024-04-0505 April 2024 Ltr. to Marcellus Osceola, Chairman, Seminole Tribe of Florida, Re., Section 106 Letters for Turkey Point ML24087A1982024-04-0505 April 2024 Notice of Availability of the Final Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML24096A2152024-04-0505 April 2024 Ltr. to Lewis Johnson, Principal Chief, Seminole Nation of Oklahoma, Re., Section 106 Letters for Turkey Point ML24096A2182024-04-0505 April 2024 Ltr. to Stephanie Bryan, Tribal Chair, Poarch Band of Creek Indians, Re., Section 106 Letters for Turkey Point ML24087A2002024-04-0505 April 2024 Letter to Miami-Dade County Office of Historic Preservation Re Section 106 on Turkey Point Units 3 & 4 EIS ML24087A2012024-04-0505 April 2024 Letter to Talbert Cypress, Miccosukee Tribe of Indians of Florida; Re., Section 106 Letters for Turkey Point ML24072A2832024-04-0101 April 2024 Ltr to Dianne Strand-Notice of Avail.-Final Site-Specific Supp. 5a, 2nd Renewal to the GEIS for License Renewal L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda ML24073A1712024-03-26026 March 2024 Correction of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML24072A2382024-03-20020 March 2024 Review of the Fall 2023 Steam Generator Tube Inspections During Refueling Outage No. 33 L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-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 ML24064A1642024-03-11011 March 2024 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 IR 05000250/20244202024-03-11011 March 2024 – Security Baseline Inspection Report 05000250/2024420 and 05000251/2024420 - Final ML24058A1182024-03-0101 March 2024 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 L-2024-014, Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report IR 05000250/20230062024-02-28028 February 2024 Annual Assessment Letter for Turkey Point Units 3 & 4 - Report 05000250/2023006 and 05000251/2023006 L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation ML24051A1442024-02-20020 February 2024 NRC Response to Turkey Point Appeal of Initial Disputed Item 05000250,251-2024-01 2024-08-05
[Table view] |
Text
DOCKET NUMBER NRC FORM 195
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50 251 FILE NUMBER NRC DISTRIBUTION FDR PART 50 DOCKET MATERIAL TO: V. STELLO, JR. FROM: FLORDIA POWER & LIGHT CO. DATE OF DOCUMENT MIAMI, FLORDIA 1/3/77 R.E. UHRIG DATE RECEIVED 1/10/77 OLETTE R '0 NOTOR IZ E D PROP INPUT FORM NUMBER OF COPIES RECEIVED IHI ORIGINAL lHUNC LASS IF I E D OCOA 40 DESCRIPTION ENCLOSURE LTR. RE. THEIR 12/30/76 SUBMITTAL..... RESULTS OF THE REVISED ECCS CALCULATIONS SUPPLFM~AL INFORMATION,......
I
( 40 CYS. RECEIVED).
( =20 PAGES)
DQ NQT REMQVg CRNQWI@DGED PLANT NAME: TURKEY PT. ft 3 & 4 SAFETY FOR ACTION/INFORMATION SAB 1 I1 77 ASSIGNED AD:
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'P C MANA E PROJECT MANAGER~ ~ ~
C ASST 0 "PARRISH- LIC ASST INTERNAL DISTRIBUTION G FILE SYSTEMS SAFETY PLANT SYSTEMS S SAFE
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NRC PDR HEINEMAN TEDESCO I&E 2 SCHROEDER OELD GOSSICK & STAFF '
- ENGINEERING IPPOLI 0 MIPC MACARRY ERNST CASE KNIGHT BALLARD SIHWEIL OPERATING REACTORS SPANGLER RLESS PAWLICK STELLO SITE TECH PROJECT MANAGEMENT REACTOR'AFE OPERATING TECH '- GAMMILL BOYD ROSS EISENHUT STEPP P COLLINS NOVAK HULMAN HOUSTON ROSZTOCZY PETERSON CHECK BUTLE SITE ANALYSIS MELTZ VOLLMER HELTEMES AT& I BUNCH SKOVHOLT SALTZMAN J COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR NAT LAB TIC: REG V.IE ECCJ'6 NSIC: LA PDR ASLB0 CONSULTANTS. J ACRS YS 89hBBf8'/
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+/p naP'LORIDA POWER 5 LIGHT COMPANY January 3, 1977 L-77-1 Office of Nuclear Reactor Regulation Attn: Victor Stello, Jr., Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Stello:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 ECCS Reevaluation
~Su lemental Information On December 30, 1976, (L-76-438), Florida Power a Light Company forwarded the results of the revised ECCS calcu-lations performed using a rated power level of .2200 Mkft:
Several of the pages in our December 30, 1976, trans-mittal have been revised to improve their clarity. A copy of the revised report is forwarded herewith.
Very truly yours, Robert E. Uhrig Vice President REU/GDW/hlc Attachment cc: Norman C. Moseley, Region II Robert Lowenstein, Esq.
P EOP LE... S ER V IN G P EOP LE
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TABLE 1 LARGE BREAK TIME SE UENCE OF EVENTS STEAN GENERATOR 10% TUBE PLUGGING DECL (CD 0.4).
(Sec)
START 0.0 Reactor Trip Signal 0:595 S. I. Signal 0. 67 Acc. Injection 16. 3 End of Bypass 27.52 End of Bio+down 27.66 Bottom of Core Recovery 46. 59 Acc. Empty 61. 02 Pump Injection 25.67
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TABLE 2 LARGE BREAK STEAM GENERATOR 10% TUBE PLUGGING DECL Results (CD 0.4)
Peak Clad Temp..'F 2190.
Peak Clad Location Ft. 6.0 Local Zr/H20 Rxn(max)% 11. 922 Local Zr/H20 Location Ft. 6.0 Total Zr/H20 Reaction <<0. 3 Hot Rod Burst Time sec 22. 8 Hot Rod Burst Location Ft. 6.0 Calculation Core Power Mwt 102% of 2200 Peak Linear Power kw/ft 102% of 12. 61 Peaking Factor 2.22 Accumulator Water Volume (ft3 ) 875 (per accumulator)
Fuel region + cycle analyzed ~Cele ~Re ion UNITS 3 and 4
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LARGE BREAK CONTAINMENT DATA (DRY CONTAII61ENT)
NET FREE VOLUME 1.55 x 10 Ft INITIAL CONDITIONS Pressure 14<<7 psia Temperature 90 'F'9 RWST Temperature 'F Service Water Temperature 63 'F Outside Temperature 39 'F SPRAY SYSTEM
.Number of Pumps Operating Runout Flow Rate <<
1450 gpm Actuation Time 26 .secs SAFEGUARDS FAN COOLERS Number of Fan Coolers Operating 3 Minimum Post Accident Initiation Time for Fan Coolers 26 secs
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TABLE 3 'Continued)
LARGE BREAK COiHTAXaiLLENT DATA (DRY CONTAXat~fE'LLlT)
STRUCTURAL ERAT SXNKS Thickness (Xn Area (Ft )
Steel 0.03 31s400 Steel 0. 063 107,158 Steel 0.1 56,371 Steel 0.2 57,185 Steel 0. 24 9,931 Steel 0. 2898 Concrete 24. 0 136,000
, Steel 0.4896 23,677 Steel 0. 6396 6,537 Steel 0.8904 4,915 Steel 1.256 27,802 Steel 1.56 5,307 Steel 2.0 668 Steel 2.75 1268. 7 Steel 5.5 1277.4 Steel 9.0 260. 4 Stainless 0. 14 Concrete 24.0 14,392 Stainless 0.44 768 Stainless 2. 126 3,704 S" ain" ess 0. 007 102, 400 Concrete 24. 0 59)132
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TABLE 4 REFLOOD MASS AND ENERGY RELEASES FOR LIMITING CASE DECLG (C =0.4)'AND 10% STEAM GENERATOR TUBE PLUGGING TIME TOTAL MASS FLOMRATE TOTAL FLORATE (SEC) (LBM/SEC) 10ENERGY BTU/SEC) 46.589 0.0 0.0 48.714 0. 0415 0.0005 54.286 35.50 '.4614 64.436 "'95.65 1. 189
- 77. 136 98. 17 1.. 219 92.136 103. 9 1. 280 107.936 220. 9 1. 603 124.236 263.2 1.678 159.236 274. 8 1.60/
197.536 281. 5 3.. 514
TABLE 5 BROKEN LOOP ACCUMtJLATOR FLOW TO CONTAINMENT FOR LIMITING CASE DECLG (C =0.4) lOX D
STEAM GENERATOR TtJBE PLUGGING TIME SEC) MASS FLOWRATE (LBM/SEC) 0.0 0.0
- 0. 02 2723.5
- 2. 00 2276.0 4.00 1994.9 6.00 1793.1 8.00 1645.5
>0.0 1526. 4 15.0 1302. 5 20.0 1137. 8 25.0 1034. 6
- 30. 0 954. 2 35.0 887. 0
- 38. 9 842. 6
'I l0,833-I 6 8 IO 2 II 6 8 IO 2 6 8 I08 TIME (SECONDS)
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Figure 1 Fluid Quality - DECLG (GD = OA)
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Figure 2 Mass Velocity - DECLG (CD = 0.4)
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Figure 3 Heat Transfer Coefficient - DECLG (CD = 0.4)
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Figure 4 Core Pressure - DECLG (Cp = 0.4)
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Figure 5 Break Flow Rate- DECLG (CD =0.4)
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Figure 6 Core Pressure Drop - DECLG (CD = 0.4)
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Figure 7 Peak Clad Temperature - DECLG'(C = OA)
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Figure 8 Fluid Temperature - DECLG (Cg = 0.4)
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-5000
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-l0000 0 IO 20 30 TIME (SECONDS)
Figure 9 Core Flow - Top and Bottom - DECLG (CD = 0.4)
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Figure 10 Ref lood Transient- DECLG (CD = 0.4)
Core Inlet Velocity
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- 20. 0 00MHCOMER LEVEL 17.5 l5.0
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Figure U Ref lood Transient - DECLG (Cp = OA)
Downcorner and Core M/ater Levels
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Figure 12 Accumulator Flow (8lowdown) --DECLG (CD = 0.4)
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Figure l3, Pumped ECCS Flow (Ref lood) - DECLG (CD = 0.4)
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Containment Pressure - DECLG (CD OA) I
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Figure l5 Core Power Transient I
- DECLG (CD = 0.4)
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-.5x I 0 6 0 IO 20 30 T IME (SECONDS)
'igure 16 Break Energy Released to Containment
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Lll ED 700 CD 600 500
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CQ Lal %00 Ch ED CD 300 LIJ 200 l
ID CD IOO 0
0 l00 200 300 TIME (SECONDS)
Figure 17; Containment Wall Condensing Heat Transfer Coefficient
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