LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 15.2-1 Through 15.2-3
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TABLE 15.2-1 TIME SEQUENCE OF EVENTS FOR CONDITION II EVENTS Accident Uncontrolled RCCA Withdrawal from a Subcritical Condition ;*:.:.. :hdrawa2. at SGS-UFSAR Event Initiation of uncontrolled rod withdrawal { 7. 5 x lo-s aK/sec reactivity insertion rate from 10-9 of nominal power) Power range high neutron flux low setpoint reached Peak nuclear power occurs Rods begin to drop Peak heat flux occurs Peak average clad temperature occurs DNBR occurs Peak average fuel Lemperature occurs Initiation o: uncontrolled RCCA withdrawal at maximum insertion rate 1 of 8 Time {sec) 0.0 10.4 10.6 10.9 12.7 13.5 12.7 14.2 Revision 18 April 26, 2000 I 1-1 I --... Accident 1. Case A 2. Case B Cilution TABLE 15.2-1 {Cont) Event -4 {7.5 x 10 AK/sec) Power range high neutron flux high trip point reached Rods begin to drop Minimum DNBR occurs Initiation of uncontrolled RCCA withdrawal at a small reactivity insertion rate (3.0 x 10-S AK/sec} Overtemperature AT reactor trip signal initiated Rods begin to drop Minimum DNBR occurs l. during begins isol3tes source SGS-UFSAR of dilution; minimum margin to criticality occurs Di.!.ution begins Operator isolates source of dilution: mir.imum margin to criticality occurs 2 of 8 Time 0 6.6 7.1 7.4 0 472.3 473.8 474.1 0 >1800 0 >900 I I I I I I Revision 18 April 26, 2000 ...
Accident 2. Dilution during full power operation a. b. Automatic reactor control Manual reactor control ..... __ .:.oops ope:-a:.:;1g; ::wo s:;s-u:sAR TABLE 15.2-1 {Cont} Event Dilution begins 1.3 percent shutdown margin lost Dilution begins Overtemperature dT reactor trip signal initiated Rods begin to drop 1.3 percent is lost (if dilution continues after trip) Coastdown begins Low-flow reactor trip Rods begin :o drop DNBR occurs 3 of 8 Time 0 >900 0 89 91 >900 0 1.6 2.6 3.9 Revision 18 April 26, 2000 I I I I Loss of External Electrical Load 1. With pressurizer control {BOL) SGS-UFSAR TABLE 15.2-1 (Cont) Loss of electrical load Initiation of steam release from steam generator safety valves Overtemperature reactor trip signal initiated Rods begin to drop Minimum DNBR occurs 4 of 8 Time 0 7.4 10.4 11.9 13.1 Revision 24 May 11, 2009 I I I I Accident 2, Without pressurizer control (Primary Pressure Case) 3. With pressurizer control (Secondary Pressure Case) SGS-UFSAR TABLE 15.2-1 (Cont) Event Loss of electrical load High pressurizer pressure reactor trip point reached Rods begin to drop Initiation of steam release from steam generator safety valves Peak RCS pressure occurs Loss of electrical load Initiation of steam release from steam generator safety valves Overtemperature delta T reactor signal initiated Rods begin to drop Peak secondary pressure occurs 5 of 8 Time 0 6.5 8.5 9.7 9.9 0 5.0 9.5 11.0 15.6 Revision 24 May 11, 2009 Accident Loss of normal feedwater Loss of Power to the Station Auxiliaries SGS-UFSAR TABLE 15.2-1 (Cont) Low-low steam generator water level reactor trip Rods begin to drop Peak water level in pressurizer occurs All steam generators begin to receive auxiliary feed from motor-driven pumps Low-low steam generator water level reactor Rods begin to drop Reactor coolant pumps begin to coast Peak pressurizer water level occurs All steam generators begin to receive auxiliary feed from motor-driven pumps 6 of 8 Time 47.0 49.0 52.5 132.0 47.0 49.0 51.0 52.5 132.0 Revision 24 May 11, 2009 Accident Excessive feedwater at full load (single loop) Excessive feedwater at full load (multi-loop) SGS-UFSAR TABLE 15.2-1 (Cont) Event One feedwater control valve and one feedwater bypass valve fail fully open Overpower Delta-T setpoint reached Rods begin to drop Minimum DNBR occurs High-high steam generator water level setpoint reached Feedwater flow isolated due to high-high steam generator water level Four feedwater control valves and four feedwater bypass valves fail fully open Overpower Delta-T setpoint reached Rods begin to drop Minimum DNBR occurs High-high steam generator water level setpoint reached Feedwater flow isolated due to high-high steam generator water level 6a of 8 Time (sec) 0.0 18.7 20.3 21.0 36.6 68.6 0 18.4 19.9 20.6 61.4 93.4 Revision 29 January 30, 2017
,..<'* /l-'.-' \.-.*-* .. \,, __ .... r I ' Accident Excessive Load Increase 1. 2. 3. ' ... Manual Reactor Control (BOL) Manual Reactor Control (EOL) Automatic ?.ea ::tor (BOL) Au:oma:ic Co:-.t.rol SGS-UFSAR TABLE 15.2-1 {Cent) Event 10% step load increase Peak pressurizer pressure Minimum DNBR occurs Peak nuclear power occurs 10% step load increase Peak pressurizer pressure occurs Peak power occurs Minimum DNBR occurs 10% step load increase Peak pressurizer pressure occurs DNBR occurs Peak nuclear power occurs step load increase Peak pressurizer pressure occurs Peak nuclear power occurs Minimum DNBR occurs 7 of 8 Time 0.0 0.1 5.1 165.0 0.0 0.1 48.2 117.0 0.0 9.0 43.0 43.3 0.0 12.7 20.7 58.0 Revision 18 April 26, 2000 t' . -(. *.* r . . '\. .1;.:.;_ ;. Accident Accidental Depressurization of the Reactor Coolant System TABLE 15.2-1 (Cent) Event Inadvertent opening of one RCS safety valve Overtemperature reactor trip setpoint reached Rod motion begins Minimum DNBR occurs 7a of 8 Time o.o 35.0 36.5 37.0 Revision 18 April 26, 2000 Accident Spurious Operation of the SIS at Power NOTE: TABLE 15.2-1 (Cont) Event Charging pumps begin injecting borated water (reactor/turbine trip on SI signal) Pressurizer becomes water-solid{2) Time by which PORV must be open to prevent water relief through the PSVs (2) Manual procedures to terminate the event are completed (1) DNBR does not decrease below its initial value. Time 0.0 579.3 616.3 :S2700.0 (2) Results are given for Unit 1 and the Unit 2 results are similar 8 of 8 SGS-UFSAR Revision 24 May 11, 2009
TABLE 15.2-2 This Table Intentionally Deleted 1 of 1 SGS-UFSAR Revision 15 June 12, 1996 Reactor Power Percent Full Power 4.0 3.5 3.0 2.5 2.0 1.5 1.0 SGS-UFSAR TABLE 15.2-3 NATURAL CIRCULATION FLOW 1 of 1 Reactor Coolant Flow Percent Nominal Flow 5.32 5.06 4. 79 4.44 4.16 3.78 3.28 Revision 6 February 15,