LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 7.10-1 Through 7.10-3

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 7.10-1 Through 7.10-3

ML17046A436
Person / Time
Site:	Salem
Issue date:	01/30/2017
From:	Public Service Enterprise Group
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17046A230	List: LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.8-1 Through 3.8-56 LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 6.3-1A Through 6.3-4 LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 9.1-1 Through 9.1-9 LR-N17-0034, Redacted Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 5.5-1 Through 5.5-7 LR-N17-0034, Redacted-Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.2, Nearby Industrial, Transportation, and Military Facilities LR-N17-0034, Redacted-Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 3.6, Figure 3.6-1 Through Figure 3.6-30 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 15.3A, Generic Small Break Analysis LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3.6A, Description of Backdraft Damper LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3.9A, Bolted Connections for Linear Component Support LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 7A, Program Element Descriptions Resulting from the Implementation of the May 6, 1983 Order LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 15, Figures 15.4-2 to 15.4-111 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 15, Section 15.5, Anticipated Transients Without Scram LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 17, Figures 17.2-1 to 17.2-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.2-1 to 4.2-25 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.3-1 to 4.3-35 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4-1 to 4.4-17 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4.1 to 4.4-66d LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.5-1 to 4.5-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Section 4.5, Reload Analyses LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 4.3.1 to 4.3-61 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 5.4.1 to 5.4-14 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.2-1 to 4.2-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.3-1 to 4.3-11 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.4-1 to 4.4-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.5-1 to 4.5-2 (Deleted) LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.1-1 to 5.1-13 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.2-1 to 5.2-24 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.1 to 5.1-8 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.2.1 to 5.2-75 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.3.1 to 5.3-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Table 5.1-1, System Design and Operating Parameters LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Tables 5.2-1 to 5.2-42 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 14.6-1 Through 14.6-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.1-1 Through 15.1-9 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.2-1 Through 15.2-46 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.3-1 Through 15.3-68 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.7.1 Through 3.7-13 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.9-1 Through 3.9-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3A-1 Through 3A-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 7.6-1 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 8.2-1 (Intentionally Deleted) and Figure 8.2-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.2-1 to 10.2-4 Intentionally Deleted LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.3-1A Sheets 1 Through 6 of 6 Intentionally Deleted to 10.3-3, Sheets 1 & 2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.4-1 Sheets 1 & 2 of 2, Intentionally Deleted to 10.4-19 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.2-1A Sheets 1 Through 5 of 5 to 11.2-1B Intentionally Deleted LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.3-1A & B, Sheets 1, 2 & 3 of 3, Intentionally Deleted. Refer to Plant Drawings 205240 & 205340 in Dcrms LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.4-1 to 11.4-9 ... further results
References
LR-N17-0034
Download: ML17046A436 (5)

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• 1. 2. 3. 4. s. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18

• 19. 20. 21. 22. 23. 24. 25. 26. 27. 28. 29. 30. 31. 32. 33. 34. 35. 36. 37. 38

• TABLE 7.10-l SAFETY PARAMETER DISPLAY SYSTEM PARAMETERS Neutron Flux -source, Power, Intermediate Ranges, and Start-up rate Control Rod Positions Plant Vent Flow RCS Cold Leg Water Temperature RCS Hot Leg Water Temperature RCS Pressure Core Exit Temperature Coolant Level in Reactor Degrees of Subcooling Containment Sump Water Level Containment Pressure (Wide and Narrow Range) Containment Isolation Valve Position (excluding check valves) Containment Area Radiation Containment Hydrogen Concentration Containment Effluent Radioactivity (Noble Gases} from Identified Release Points RHR System Flow RHR Heat Exchanger Outlet Temperature Accumulator Tank Level and Pressure Accumulator Isolation Valve Position Boric Acid Charging Flow Charging Pumps Discharge Flow Safety Injection Pumps Discharge Flow Refueling Water Storage Tank Level Reactor coolant Pump Status (AMPS) Primary System Safety/Relief Valve Position Pressurizer Level Pressurizer Heater Status {AMPS) Pressurizer Relief Tank Level Pressurizer Relief Tank Temperature Pressurizer Relief Tank Pressure Steam Generator Level Steam Generator Pressure Main Steam Flow Main Feedwater Flow Auxiliary Feedwater Flow Auxiliary Feedwater Storage Tank Level Containment Spray Flow Additive Rate Heat Removal by the Containment Fan Coil Units (CFCU's) (CFCU Outlet Flow and CFCU Running) 1 of 2 SGS-UFSAR Revision 14 December 29, 1995

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• 39. 40. 41. 42. TABLE 7.10-1 (Cont) SAFETY PARAMETER DISPLAY SYSTEM PARAMETERS Containment Atmosphere Temperature Letdown Flow Volume Control Tank Level Component Cooling Water Temperature 43. Component Cooling Water Flow 44. High Level Radioactive Liquid Tanks Levels 45. 46. 47. 48. 49. so. 51. 52. 53. 54. 55. 56. 57

• a. Holdup Tanks b. Auxiliary Building Sump Tank c. Waste Monitor Holdup Tank d. Waste Holdup Tanks e. Reactor Coolant Drain Tank Radioactive Gas Hold Up Tank Pressure control Room Emergency Ventilation Damper Position Auxiliary Building Emergency Damper Position Fuel Handling Building Emergency Damper Position Status of Standby Power and Other Emergency Power Sources Important to Safety Control Air Pressure Main Steam Radiation Condenser Availability (Condenser Vacuum and Circulator Amperes) Res Average Loop Temperature Main Steam Isolation Valve Position Reactor Trip Demand Signal from Train "A" Reactor Trip Demand Signal from Train "B" Auxiliary Building Roof Radiation Monitor 2 of 2 SGS-UFSAR Revision 14 December 29, 1995

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• TABLE 7.10-2 COMPARISON OF SAFETY FUNCTIONS WITH NUREG-0737 SUPPLEMENT 1 SAFETY FUNCTION NUREG-0737 SUPPLEMENT 1 Reactivity Control Reactor Core Cooling and Heat Removal from the Primary System Reactor Coolant SGS-UFSAR SAFETY FUNCTION STATUS TREE Shut Down Margin Core Cooling Heat Sink Thermal Shock Coolant Inventory 1 of 2 PARAMETERS 1. Neutron Flux 2

• Reactor Trip 1. Core Exit Temperature 2. Degrees of Subcooling 3. Reactor Coolant Pump Status 4. Reactor Vessel Level 5. Hot Leg Temperature 6. Cold Leg Temperature 7. Steam Generator Level 8. Steam Generator Pressure 9. RHR Flow lO.RCS Pressure ll.Containment Pressure 12.Containment Area Radiation 1. Steam Generator Level 2. Steam Generator Pressure 3. Auxiliary Feedwater Flow 4. Cold Leg Temperature s. Main Feedwater Flow 6. RCS Pressure 7. RCS Cold Leg Water Temperature 8. Pressurizer Level 9. Reactor vessel Level lO.Reactor coolant Pump Status ll.Containment Sump Level 12.Pressurizer Temperature Revision 14 December 29, 1995

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• SAFETY FUNCTION NUREG-0737 SUPPLEMENT 1 Radioactivity Control Containment Conditions SGS-UFSAR TABLE 7.10-2 (cont.) SAFETY FUNCTION STATUS TREE Radiation Monitoring Containment Environment 2 of 2 PARAMETERS 1. Containment Particulate Radiation 2. Plant Vent Particulate Radiation 3. Containment Radiation 4. Main Steam Radiation 5. Roof Monitor 1. Containment sump Water Level 2. Containment Pressure 3. Containment Area Radiation 4. Containment Hydrogen Revision 14 December 29, 1995

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• TABLE 7.10-3 CRITICAL SAFETY FUNCTIONS ASSOCIATED WITH BARRIERS BARRIER 2. 3

• Fuel Matrix and Fuel Clad Reactor Coolant System Pressure Containment Vessel SGS-UFSAR CRITICAL SAFETY FUNCTIONS a. Maintenance of SUBCRITICALITY (minimize energy production in the fuel) b. Maintenance of a CORE COOLING (provide adequate reactor coolant for heat removal from the fuel) c. Maintenance of a HEAT SINK (provide adequate secondary coolant for heat removal from the fuel) d. control of Reactor Coolant INVENTORY (maintain enough reactor coolant for effective heat removal and pressure control) a. Maintenance of a HEAT SINK (provide adequate heat removal from the RCS) b. Maintenance of Reactor Coolant System INTEGRITY (prevent failure of RCS) c. control of Reactor Coolant INVENTORY (prevent flooding and loss of pressure control) d. Maintenance of CONTAINMENT Integrity (prevent failure of containment vessel) 1 of 1 Revision 14 December 29, 1995