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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
MONTHYEARML22054A1382022-02-16016 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 ML18227D2901977-01-0707 January 1977 Submit Refueling Information (Cycle 4) Which Will Not Involve Any Unreviewed Safety Questions ML18227D2911977-01-0707 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-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-76-438, 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-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 2022-02-16
[Table view] Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) 2024-02-05
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Text
NRC FSRM 195 I2 76)
U.S. NUCLEAR REGULATORY COMML DO UMBE E NUMBER ari NRC DISTRIBUTION FDR PART 50 DOCKET MATERIAL TO: FROM: DATE OF DOCUMENT Florida Power & Light Company 1/3/78 Mr. George Lear Miami, Florida DATE RECEIVED Robert Ei" Uhrig 1/11/78 ABETTER QNOTORIZEO PROP INPUT FORM NUMBER OF COPIES RECEIVED ORIGINAL UNCLASSIFIED OCOr Y 4/6w DESCRIPTION ENCLOSU RE Atto 1) Procedure for Evaluation of Maximum Setpoint Overshoot Heat Input Transients>>
Att 2) Supplement to the July 1977 Report-Pressure Mitigating Systems, Transient Analysis Results-REACTOR VESSEL OVERPRESSURIZATION DISTRIBUTION PER G, 'SECH '10 21 76 (1-P) (2-P )+(1/4" )
PLANT NAME: Turkey Point Units 3 & 4 o~p~<gp Rim6An guD/C4 1/11/78 RJL FOR ACTION/INFORMATION Ac drift tRd(EVE ~M SAFETY BRANCH CHIEF:
INTERNAL D ISTRI BUTION NRC~PDR GOSSICK & STAFF BOSNAK AI SHAO BAER BUTLER ZECH EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: CaP TIC:
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NRC FORM 196 I2 26)
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Q06 ALB95 5f 5~Ili<t'f f.'(MID FLORIDA POWER & LIGHT COMPANY January 3, 1978 L-78-4 Office of Nuclear Reactor Regulation Attention: Mr. George Lear, Chief Operating Reactors Branch 53
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Division of Operating Reactors Nuclear Regulatory Commission gff I(' Y~
Washington, D.C. 20555
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Dear Mr. Lear:
Re: Turkey Point Units 3 6 4 Docket Nos. 50-250 and 50-251 Over ressure Protection In our October 18, 1977 (L-77-324) submittal on the Overpressure Mitigating System (OMS) for Turkey Point, setpoint selection for the pressurizer power operated relief valves (PORV's) was based upon a July 1977 Westinghouse analysis. The maximum setpoint overshoot for heat input transients was evaluated with a PORV setpoint of 500 psig, the only setpoint considered in the Westinghouse July analysis. A supplement to the July report has been prepared which permits us to evaluate the maximum setpoint overshoot with a PORV setpoint of 415 psig, the setpoint selected for Turkey Point for reactor coolant temperatures below 300 F. The supplement is attached.
The chosen PORV setpoint of 415 psig is 85 psi below the minimum NDT pressure of 500 psig. The maximum,setpoint overshoot for heat input transients evaluated with a PORV setpoint of 415 psig increased from 14 psi at 100 F to 57 psi at 250 F. This is less than the margin to the minimum NDT pressure provided by the selected setpoint and confirms that the setpoint is conserva-tive for heat input, transients. The procedure for evaluating the setpoint overshoot is attached.
Very t ly yours, Robert E. Uhrig Vice President REU/MAS/lah Attachments (2) cc: James P. O'Reilly, Region II 780% f0142 Robert Lowenstein, Esquire PEOPLE.... SERVING PEOPLE
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PROCEDURE FOR EVALUATION OF MAXIMUM SETPOINT OVERSHOOT HEAT INPUT TRANSIENTS Turkey Point Units 3 and 4 parameters RCS Volume 9343 ft. 3 2(FSAR Table 4.1-1)
S.G. Area 44,430 ft. (FSAR Table 4.1-4)
PORV opening time 2.0 sec. (Pre-op test 1000.16)
Selected PORV setpoint 415 psig (below 300 F RCS temp.)
Figure and example numbers refer to the September 1977 supplement to the July 1977 report provided by Westinghouse.
(1) Evaluate the effect of S.G. UA on pressure overshoot (hP)
(Figures 14 thru 20).
Turke Point S.G. Area = 44,430 ft. 2 = .766 Reference S.G. Area 58,000 ft.
Turkey Point UA = .766 Reference UA Relief valve setpoint 400 psig, 3 second opening time:
Figure 14 Figure 15 Vol. 6000 ft. Vol. 13000 ft.
100oF hP = 25 psi hP = 16 psi 180oF hP = 59 psi hP = 51 psi 250oF hP = 93 psi hP =I72 psi Relief valve setpoint 500 psig, 3 second opening time:
Figure 16 Figure 17 Vol. 6000 ft. Vol. 13000 ft.
100 F hP = 23 psi hP = 21 psi 180oF hP = 74 psi hP = 53 psi 250 F hP = 109 psi hP = 91 psi (2) Evaluate the effect of RCS volume on pressure overshoot.
By linear interpolation of results from (1) above (as in supplement example 4);
RCS volume 9343 ft.3; 3 second opening time:
~Tem Set oint 400 si Set oint 500 si 100oF hP = 21 psi hP = 22 psi 180oF hP = 55 psi hP = 64 psi 250oF hP = 83 psi hP = 100 psi
0 ~g (3) Evaluate the effect of relief valve setpoint on pressure overshoot.
By linear interpolation of results from (2) above; Relief valve setpoint 415 psig; RCS volume 9343 ft. 3 three second opening time:
~Tem Pressure Overshoot 100oF bP = 21 psi 180 F hP = 57 psi 250oF hP = 86 psi (4) Evaluate the effect of valve opening time on pressure over-shoot.
Figures 1 6 show pressure overshoot directly proportional to valve opening time.
Therefore, applying all Turkey Point parameters:
~Tem Pressure Overshoot 100oF hP = 14 psi 180oF bP = 38 psi 250oF hP = 57 psi
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