LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 7.2-1 Through 7.2-5

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 7.2-1 Through 7.2-5

ML17046A413
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: ML17046A413 (16)

Text

1. 2. 3. 4. 5. 6. 7. 8. * *

• TABLE 7.2-1 LIST OF REACTOR TRIPS, ENGINEERED SAFETY FEATURES, CONTAINMENT AND STEAM LINE ISOLATION AND AUXILIARY FEEDWATER Reactor Trip Manual High neutron flux (Power Range) Overtemperature !J.T Overpower !J.T Low pressurizer pressure High pressurizer pressure High pressurizer water level Low reactor coolant flow Coincidence Circuitry and Interlocks 1/2, no interlocks 2/4, low setpoint interlocked with P-10 2/4, no interlocks 2/4, no interlocks 2/4, interlocked with P-7 2/4, no interlocks 2/3, interlocked with P-7 2/3 signals per loop, interlocked with P-7, and P-8 1 of 7 Comments High and low settings; manual block and automatic reset of low setting by P-10, Table 7.2-2 Blocked below P-7. Low flow in 1 loop permitted below P-8. SGS-UFSAR Revision 6 February 15, 1987 Reactor Trip 9, Monitored electrical supply to reactor coolant pumps: 9A. Undervoltage 9B. Underfrequeney 9C. Reactor coolant pump breakers 10. Safety injection signal (actuation} SGS-UFSAR TABLE 7.2-1 (Cont} Coincidence Circuitry and Interlocks 1/2 taken twice, interlocked with P-7 1/2 taken twice, interlocked with P-7 Interlocked with P-7 Low pressurizer pressure (2/3) or 2/3 high containment pressure; or 2/3 differential steam line pressure signals of one line compared with the other three lines; or 2/4 high steam flow in coincidence with 2/4 low-low Tavg or 2/4 low steam line pressure; or manual 1/2 (See 7.2 System 2 of 7 Comments 1/2 twice underfrequency signals trip all reactor coolant pwnps and directly actuate reactor trip: interlocked with P-7. (Opening of the coolant pump breakers will also actuate a reactor trip.) Blocked below P-7. Open breaker in 1 loop permitted above P-7. Trips main feedwater pumps. Closes all feedwater control valves, Closes feed-water pump discharge valves and initiates Phase A isolation. Initiates turbine trip. Revision 16 January 31, 1999

11. Turbine-generator trip 12. Low-low steam generator water level 13. Intermediate range neutron flux 14. Source range neutron flux 15. High flux rate trips (Note 2) SGS-UFSAR TABLE 7.2-1 (Cont) Description-Protective Action For Interlocks) . 2/3 low auto stop oil pressure (interlocked with P-9) or all stop valves closed 2/3, per loop 1/2, manual block permitted by P-10 1/2, manual block permitted by P-6, interlocked with P-10 2/4, no interlocks 3 of 7 Comments (Anticipatory trip of the reactor. No credit taken in accident analysis.) Manual block and automatic reset Manual block and automatic reset Positive and negative high flux rate trips provided Revision 25 October 26, 2010 Reactor Trip 16. Containment pressure (Note 1) 17. High containment activity Engineered Safeguards Systems Actuation 18. Safety injection signal (S) 19. Containment spray signal (P) 20. WaOH addition SGS-UfSAR TABLE 7.2-1 {Cont.) Coincidence Circuitry and Interlocks Coincidence of 2/3 containment high pressure or 1/2 manual Coincidence of 2/4 containment Hi-Hi pressure or 2/2 manual High activity signal, from either air particulate detector or radiogas detector, or 1/2 manual Se9 Item 10 See second part of item 16 Containment Spray Actuation Signal 4 of 7 Comments Actuates all non-essential process lines containment isolation trip valves-ation A Actuates all remaining trip valves (except those required for operation of engineered safeguard systems) containment purge supply, exhaust ducts and all others necessary to isolate containment atmosphere Revision 11 October 16, 1998 Reactor Trip Steam Lines Isolation Actuation 21. Steam flow Containment pressure (Note 1) 22. Manual (per steam line) Auxiliary Actuation 23. Turbine driven pump SGS-UFSAR TABLE 7.2-1 (Cont.) Coincidence Circuitry and Interlocks High steam line flow in 2 out of 4 lines coincident with either low-low T in 2 out of 4 loops or low in 2 out of 4 lines 2/4 Hi-Hi containment pressure 1/1 per steam line Coincidence of 2/3 low-low level in any two steam generators; undervoltage l/2 twice on RCP busses; or manual (local and remote} 5 of 7 Comments 2/3 high level in steam generator trips main feedwater pumps Revision 17 October 16, 1998 Reactor Trip 24. Motor drive pumps Main Feedwater Isolation 25. Close main feedwater control valves (fast closure) and feedwater bypass valves and feedwater inlet stop valves TABLE 7.2-1 (Cont.) Coincidence Circuitry and Interlocks 2/3 iow level in any steam gen-erator: or trip of both main feedwater pumps, or safeguards sequence signal, or blackout sequence signal, or manual (local and remotel Actuated by: 1. Safety injection (See No. 10) 2. 2/3 Hi-Hi level in steam generator 3. Low actloneered T and reactor trip avg NOTE 1: Definition of "S", "T", and "P" signals: Initiated by: "S" Safety injection signal *'T" Safety injection signal 6 of 7 SGS-UfSAR Comments Safeguards automatic loading signal blocks manual start Action Actuates safety injection Actuates containment isolation Phase A (All non-essential process lines) Revision 17 October 16, 1998 TABLE 7.2-1 (Cont) "P" 2/4 Hi-Hi Containment Pressure Activates containment spray, steam lines isolation and Phase B containment isolation (remaining process lines) NOTE 2: Salem NRC License Amendment 278-261 (Salem 1 and 2 respectively) approved the removal of the Negative Flux Rate Trip. This function was initially disabled by setting the setpoint to a greater value than the Maximum Negative Rate expected (per design change package (DCP) 80094424). The Negative Flux Rate Trip circuitry has been physically removed for Unit 1 and 2 per DCPs 80097106 and 80099680). 7 of 7 SGS-UFSAR Revision 26 May 21, 2012

• P-7

• P-8 P-9 P-10

• SGS-UFSAR Rea,ctor trip 1/2 Neutron flux (intermediate range) above setpoint 2/2 Neutron flux (intermediate range) below setpoint 3/4 Neutron flux {power range) below setpoint (from P-10) and 2/2 turbine* steamline inlet pressure below setpoint {from P-13) 3/4 Neutron flux (power range) below setpoint 2/4 Neutron flux (power range) above setpoint 2/4 Neutron flux (power range) above setpoint TABLE 7.2-2 INTERLOCK CIRCUITS Function Actuates tu*rbine trip Close main feedwater valves on Tavg below set point Prevents opening of main feedwater valves which were closed by safety injection or high steam generator water level Prevents or defeats the automatic block of steam dump control via load rejection controller (enables plant trip controller) Allows manual block of source range reactor trip Defeats the block of source range reactor trip Blocks reactor trip on: Low flow or reactor coolant pumpbreakers open in more than one loop, undervoltage, underfrequency, pressurizer low pressure, and pressurizer high level Blocks reactor trip on low flow in a single loop Prevents or defeats the automatic block of reactor trip on turbine trip 50% of rated thermal power Allows manual block of power range (low setpoint) reactor trip trip 1 of 4 Revision 21 December 61 2004 I

• Designation *

• SGS-UFSAR TABLE 7.2-2 (Cont) Derivation Function Allows manual block of intermediate range reactor trip and intermediate range rod stops (C-1) Blocks source range reactor trip (backup for P-6) la of 4 Revision 9 July 22, 1989 P-10 cont. P-11 P-12 P-13 P-14 SGS-UFSAR TABLE 7.2-2 (Cont.) 3/4 Neutron flux (power range) below setpoint 2/3 Pressurizer pressure below 2/3 Pressurizer pressure above set point below 3/4 Tavg above 2/2 Turbine steamline inlet pressure below setpoint 2/3 Hi-Hi steam generator level above setpoint on any steam generator Defeats the b:ock of power range (low setpoint) reactor Defeats the block of intermediate range reactor trip and im:ermediate range rod stops (C-1) to P-7 Allows manual block of safety ection actuation on low zer pressure coincident with low pressurizer level signal Defeats manual block of ection actuation Actuates ection and isolation on high steamline flow. Allows manual block of safety injection actuation on high steam line flow Blocks steam dump to all valves Allows manual of steam dump block for the cooldown valves only Defeats the manual block of ection actuation on steam line flow Defeats the manual dump block I::1put to P-7 ofsteam all feedwater pumps, isolates feedwater, and trips turbine 2 of 4 Revision 25 October 26/ 2010 Designation

• C-1 C-3 C-4 C-5

• C-:-6 C-7 ** SGS-UFSAR TABLE 7.2-2 (Cant) Derivation 1/2 Neutron flux (intermediate range) above setpoint 1/4 Neutron flux (power range) above setpoint 2/4 Over-temperature AT above setpoint 2/4 Overpower AT above setpoint 1/1 Turbine steamline inlet pressure below set point 1/2 .. Turbine steamline inlet pressur:e below set point 1/1 Time derivative (absolute value) of turbine steamline inlet pressure (decrease only) above setpoint Function Blocks automatic and manual control rod withdrawal Blocks automatic and manual control rod withdrawal Blocks automatic and manual control rod withdrawal Actuates turbine runback via load reference Blocks automatic and manual control rod withdrawal Starts turbine runback via load reference Blocks automatic control rod withdrawal Blocks turbine runback via load limit Makes steam dump valves available for either tripping or modulation 3 of 4 Reyision 21 December 6, 2004 I .I

• Designation C-9; C-.20 *

• SGS-UFSAR TABLE 7. (Cont.} Derivation Any Condenser pressure above setpoint or all circulation water pump breakers open 2/2 turbine steamline inlet pressure above setpoint Function Blocks steam dump to condenser Arms AMSAC; below setpoint1 blocks AMSAC (no control grade only) 4 of 4 Revision 21 December 6, 2004

• *

• Al Buf f F FC FI FLTR FS FT FW Hi LRT HI PRT I/I ISOL LC LI L-Low Lo L to LRT Lo PRT L ref L/L LT NC NE NI NM NQ p PC TABLE 7.2-3 LEGEND OF ANALOG SYMBOLS -Alarm -Buffer -Special Function (such as a pressure compensation unit or lead/lag compensation) -Amplifier Flow controller (off-on unless output signal is shown) -Flow Indicator -Filter -Flow Stream -Flow Transmitter -Flow Water -High Level Reactor Trip -High Pressure Reactor Trip -Isolation Current Repeater -Isolation (other than I/I) Level Controller (off-on unless output signal is shown) -Level Indicator -Low Level -Low Level -Low Level Reactor Trip -Low Pressure Reactor Trip -Programmed Reference Level -Lead/Lag -Level Transmitter -Nuclear Flux Controller (Bistable) -Nuclear Detector -Nuclear Flux Indicator -Nuclear Modifier -Nuclear Power Supply -Pressure Pressure Controller (off-on unless output signal is shown) 1 of 2 SGS-UFSAR Revision 6 February 15, 1987

• *

• PI PM p ref PS PT QM R/1 RT RTD s SI sp T TC TE TI TJ TM TP cpU, L d dt I TABLE 7.2-3 (Cont) -Pressure Indicator -Pressure Modifier -Programmed Reference Pressure -Power Supply -Pressure Transmitter -Flux Modifier -Resistance to Current Connector -Reactor Trip -Resistance Temperature Detector -Control Channel Transfer Switch (used to maintain auto channel during test of the protection channel) -Safety Injection -Set Point -Transmitter -Temperature Controller -Temperature Element -Temperature Indicator -Test Signal Insertion Jack -Temperature Modifier -Test Point Out of core upper or lower ion chamber flux signals -Time Rate Change -Sum 2 of 2 SGS-UFSAR Revision 6 February 15, 1987 SGS UFSAR SALEM UNIT 1 THE rNFORMATION CONTAINED IN THIS TABLE WAS RELOCATED TO THE SALEM TECHNICAL REQUIREMENTS MANUAL 1 of 1 Revision 25 October 26, 2010 SGS UFSAR SALEM UNIT 2 THE INFORMATION CONTAINED IN THIS TABLE WAS RELOCATED TO THE SALEM TECHNICAL REQUIREMENTS MANUAL 1 of 1 Revision 25 October 26, 2010