ML13322A034
| ML13322A034 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/31/1988 |
| From: | Motamed M Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13322A032 | List: |
| References | |
| NUDOCS 8811010440 | |
| Download: ML13322A034 (54) | |
Text
EVALUATION OF AN IMPROVED SAFETY INJECTION SYSTEM WITH RETRAN-02/MOD 4 SONGS 1 ApprovaI Author C44 eSto26 March 1988 10 ioCK 0)5 00 Q2
-154P6 154 6j
THERMAL HYDRAULICS
- 1. 2&3 - T/H-82-01 Mark Sands An Introducion to the Use of VIPRE
- 3. 2 - T/H-83-02 Yine-Ping Ting Retran Analysis of SONGS 2 Low Power Natural Circulation Test
- 4. 2 - T/H-83-03 Charles Sayles MMS Analysis of SONGS 2 Loss of Feedwater Flow and Turbine Trip Transients
- 5. 2 - T/H-84-01 Yine-Ping Ting RETRAN Analysis of San Onofre Unit 2 Turbine Trip from 100% Power Part I: RETRAN Model, Results, and Discussions Part II:
RETRAN Plant Control Systems Modeling
- 6. 2&3 - T/H-84-02 Yine-Ping Ting Special RETRAN Studies Performed in Conjunction with the SONGS 2 100%
Turbine Trip Analysis
- 7. 2&3-T/H-84-03 Glenn A. Ducat Startup: A CLIST For Processing SU Computer Data
- 9. 2&3-T/H-85-01 Yine P. Ting RETRAN Analysis of San Onofre Units.2/3 Steam Generator Tube Rupture
- 10.
2&3-T/H-85-02 Yine P. Ting RETRAN Analysis of San Onofre Units 2/3 Loss of Feedwater Transient
THERMAL HYDRAULICS (Cont.)
- 11. 243-T/H-85-03 Yine P. Ting Thermal Hydraulic Analysis of SONGS 2/3 Spent Fuel Storage Rack
- 12. 2&3-T/H-85zO4 Yine P. Ting A Status Review of SONGS 2/3 RETRANO2 Model Development
- 13. 2&3-T/H-85-05 Henri J. Fenech Fuel Failure Prediction by the Convolution Method
- 14. 2&3-T/H-85-06 Yine P. Ting RETRAN Analysis of SONGS 2/3 Total Loss of Forced Circulation at Full Power
- 15. 2 -
T/H-85-07 Yine P. Ting Determination of SONGS 2 RCS Flowrate with VIPRE Code
- 16. 1 -
T/H-86-01 Yine P. Ting RETRAN Analysis of SONGS 1 11/21/85 Water Hammer Event
- 17. 2 -
T/H-86-02 Yine P. Ting RETRAN Analysis of SONGS 2 Double-ended Steam Line Break at Full Power
- 18. 1 -
T/H-86-03 Majid Motamed (0519j)
Time to Boil-Off Steam Generator Following a.Total Loss of Feedwater SONGS 1
.19. 2 -
T/H-87-01 Majid Motamed (0852j)
Time to Boil-Off Steam Generator Following:
- 1. Total Loss of Feedwater (TLOFW)
- 2. TLOFW and Station Blackout SONGS 2
- 20. 2&3-T/H-87-02 Majid Motamed (0879j)
Methodology and Analysis of LPSI Fluid Flow Under Seismic Acceleration SONGS 2/3
- 21. 1 -
T/H-87-03 Yine P. Ting RETRAN Analysis of SONGS 1 LONF Event with a Concurrent Loss of Steam Flow/
Feed Flow Mismatch Reactor Trip
THERMAL HYDRAULICS (Cont.)
- 22.
1 -
T/H-87-04 Yine P. Ting RETRAN Analysis of SONGS 1 Loss of Feedwater ATWS Event
- 23.
2&3-T/H-88-01 Yine P. Ting RETRAN'Analysis of SONGS 2/3 Uncontrolled CEA Withdrawal from Subcritical Conditions with a Complete Closure of ADVs
- 24.
1-T/H-88-02 Majid Motamed RETRAN SBLOCA Model Benchmark (Comparison with WFLASH) 1515j SONGS 1
- 25.
1-T/H-88-03 Majid Motamed Evaluation of An Improved Safety Injection System using RETRAN-02/Mod 4 1546j SONGS 1
TABLE OF CONTENTS SECTION PAGE
- 1. Summary............
1
- 2.
Introduction..
2
- 3. RETRAN Model.....
3
- 4.
Results.
.....5
- 5.
Conclusions..
7
- 6. References......
8
- 7. Figures......
9 Appendix 1......
....47 Appendix 2.....................
49
O1.
SUMMARY
A proposed upgrade to the Safety Injection System of San Onofre Nuclear Generating Station Unit 1 (SONGS 1),is evaluated using the RETRAN-02/Mod 4 computer code.
The upgrade consists of modifications to the charging system to allow high pressure.injection of borated water by the two charging pumps during safety injection and bypass piping around the feedwater pumps. The limiting cold leg SBLOCA was simulated with the RETRAN model of SONGS 1 for the 3 inch, 4 inch, and 6 inch diameter break sizes. In each case the transient was simulated beyond the time of loop seal clearing, core uncovery, core recovery, and the point in time where SI flow exceeded the break.flow.
The proposed upgrade to the SI system was included in this simulation. It was assumed that the hydraulically actuated valves which realign the feedwater pumps to become a part of.the SI system have failed, making the existing SI system inoperable.
The results of the SBLOCA simulation show that the core is adequately protected even with one SI line spilling out of the break. It is concluded that the upgraded Safety Injection System will protect the core in the event of the limiting SBLOCA.
. 2.
INTRODUCTION The Safety Injection System at SONGS 1 is different from most other PWR's since it depends on the main feedwater pumps to realign and inject borated water to the RCS. This involves automatic action of several hydraulically actuated valves.
It is of interest to improve the SI system by reducing its reliance on the operation of these valves. Several upgrade options were considered. Based on SCE's evaluations (1) the recommended alternative consists of modifications to the charging system to allow high pressure injection of borated water by the two charging pumps during safety injection and bypass piping around the feedwater pumps.
The RETRAN model-of SONGS 1 was used to evaluate this upgrade option for system response to a small break LOCA. The detailed model of the loop seal was included in the RETRAN model, since the process of loop seal clearing is very important in a limiting cold leg small break. The simulation was continued beyond the time of loop seal clearing, core uncovery, core recovery, and the point in time where the SI flow exceeds the break flow. As the RCS depressurizes,.breakflow decreases and SI flow increases. After SI flow exceeds break flow the RCS begins to refill. It can be shown that the core is adequately protected prior to the time when SI flow exceeds break flow, then the core will remain covered beyond that time.
. 3.
RETRAN MODEL The RETRAN model of SONGS 1 used in the simulation of a cold leg SBLOCA consists of 48 control volumes and 76 junctions. Figure 1 shows a nodal diagram of the model. Primary Loops A and C are combined into an equivalent loop (right loop), and Loop B with the cold leg break (Junction 265) is modeled as a separate loop (left loop).
Since the loop seal clearing process occurs in the SBLOCA's simulation, the detailed geometry and elevations of the loop seal including the crossover leg was included in the RETRAN model. The break sizes considered were 3, 4, and 6 inch diameter cold leg breaks located near the cold leg nozzle of loop B. These breaks cause voiding of large sections of the primary system. The loop flow becomes stagnant, and many volumes such as the reactor vessel upperhead and the pressurizer become completely voided of liquid. A bubble rise model was used in the primary system to model voiding of large sections of the RCS under low flow to fairly stagnant conditions. Control volumes were over-lapped by 0.02 feet to allow the mixture level to pass across volume boundaries. A detailed model of the steam generators including steam separator and recirculation was used to accurately represent the temperature distribution of the coolant in the secondary system. The pressure dependent Safety Injection flow is assumed to be the flow of two charging pumps with the proposed modifications, adjusted for charging pump mini-flow. Figure 2 shows the SI flow vs. pressure assuming one line is spilling, one line is blocked and one line is injecting. It is assumed that the main feedwater pumps have failed to realign to'the SI system. Table 1 states the initial conditions and the assumptions made in this simulation. The RETRAN model of the SONGS 1 SBLOCA was benchmarked against the Westinghouse SBLOCA analysis performed with the WFLASH code for the current SI system of SONGS 1. The benchmark effort is discussed in Reference (2).
.Table 1
Assumptions and Initial Conditions
- 1.
Initial power: 100% (1347 MW t)
- 2.
Break occurs at the cold leg nozzle, loop B cold leg, discharge side of the pump.
- 3. "Reactor trip on the low pressurizer pressure SI signal of 1750 psia with one second delay.
- 5.
Turbine trip on reactor trip signal.
- 7. Auxiliary feedwater is manually actuated with 10 minute delay.
- 8. The initial pressurizer level, hot leg and cold leg temperatures are consistent with the reduced temperature program (see figures).
- 9.
Extended Henrey Fauske critical flow model was used for subcooled break flow, with a discharge coefficient of 1.
- 10.
Moody's critical flow model was used for saturated break flow with a discharge coefficient of 1.
- 11.
All control'systems, especially the steam dump/bypass control system are inoperable.
- 12.
SI flow enters the RCS with a 10 second delay after SIS actuation.
- 13. One SI train is operating with one line injecting, one line spilling, and one line blocked.
- 4. RESULTS Three breaksizes were simulated 3, 4, and 6 inch diameter breaks. Simulation of the SBLOCA for all three break sizes was continued beyond the loop seal clearing, core uncovery/recovery, and beyond the point in time where SI flow exceeded the mass flow rate through the break.
The overall system response for all three break sizes is quite similar. The reactor trip occurs due to low pressurizer pressure SI signal setpoint of 1750 psia. RCS pressure rapidly drops to approximately 1000 psia which is the steam generator safety valves setpoint. RCS pressure remains at 1000 psia until the loop seal clears at the broken loop.
The turbine trips due to reactor trip (SIS) and'the feedwater pumps are also tripped in the process of realigning to the safety injection system. The steam dump and bypass control system is assumed to be unavailable, which causes the steam generator pressure to increase to 1000 psia which is the setpoint of the safety valves with the lower settings.
Steam generator pressure decreases after the loop seal clears and the primary system begins to cool down. The pressurizer and the upperhead void completely and the upper plenum and the reactor vessel downcomer partially void, and the primary loops void at elevations above the hot leg prior to loop seal clearing. Just before the loop seal clears the mixture level in the upper plenum drops to uncover part of the core for a short time.
The mixture level returns above the top of the core when the loop seal clears. The RCS pressure continues to decrease and so does the break flow.
The SI flow increases as the system is depressurizing.
The SI flow,exceeds the breakflow at some point in time, beyond which the mixture level in the upper plenum will continue to increase. In the cases of the 3 inch and 4 inch breaks, RETRAN predicts a second core uncovery which is very brief and is due to the dynamics of the loop flow. The RCP's are tripped on the SI signal.
Figures 3 through 13 show the system response for the 3 inch break, Figures 14 through 24 show the results for the 4 inch break and Figures 25 through 35 are for the 6 inch break.
- 5.
CONCLUSIONS The RETRAN model of SONGS 1 SBLOCA was used to evaluate a proposed upgrade to the Safety Injection System. The upgrade consists of modifications to the charging system to allow high pressure injection by two charging pumps.
The break sizes considered were 3 inch, 4 inch, and 6 inch breaks at the cold leg nozzle of loop B. The simulation was continued to beyond a point in time where the SI flow exceeded the break mass flow rate. Results showed that certain sections of the primary system voided, the loop seal cleared, and the core was uncovered for a short time.. However, the coolant mixture level quickly returned to above the top of the core. After reaching the point in time when SI flow exceeds break flow, the mixture level in the reactor vessel will begin to increase and the system will continue to depressurize.
It is concluded that in the event the feedwater pumps fail to realign to the SI system following a limiting cold leg SBLOCA, the SI system with the proposed upgrade will adequately protect the core during-the ensuing depressurization event.
- 6. REFERENCES
- 1. Letter from G. J. Stawniczy to J. L. Rainsberry, "Safety Injection Upgrade Alternatives, SONGS 1," November 16, 1987
- 2.
Motamed, M.,
"RETRAN SBLOCA Model Benchmark (Comparison with WFLASH),
SONGS 1," 1-T/H-88-02, March 1988
, "1./
.i f150 Figure 1 RETRAN Model Nodal nianram
uL.
RCS PRESSURE (PSIA) 0a 0
0 0
00000 0
00 O >Z0 m T~U) 0
-... 1 CD 0
O CA
-1 C)i
)'
mmZ C-o C) 0 M
0 0 0
- 0.
I.
a l.
I.
O0
FIGURES FOR 3 INCH BREAK Figure 3 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK NORMAUZED REACTOR POWER 1.000 0.900 0.800 w
3r 0.700 0
0.600 a 0.500 4
0.400 0.300 0 Z 0.200 0.100 0.000 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 4 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK RCS PRESSURE 2500 2000 On 6
1500 w
in 1000 500 0
0 100 200 300 400 500 600 700 TIME (SEC)
Figure 5 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK PRESSURIZER MIXTURE LEVEL 25 20 15 10 5
0 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 6 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK STEAM GENERATOR PRESSURE 1200 U) 800 400 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 7 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK RX VESSEL DOWNCOMER MIXTURE LEVEL 25
~25 20--2 15
.I J10 0
0 100 200 300 400 500 600 700 TIME (SEC)
Figure 8 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK RX VESSEL UPPER HEAD MIXTURE LEVEL 0
w I-.
01 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 9 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK MIXTURE LEVEL FROM TOP OF CORE 10 8 6 W4 LL.
W top of core 80 W -2
-8
- 10*
0 100 200 300 400 500 600 700 TIME (SEC)
Figure 10 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK LOOP SEAL MIXTURE LEVEL 25 o-20 w
L.
i15 w
Li 10 0
0 100 200 300 400 500 600 700 TIME (SEC)
Figure 11 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK BREAK FLOW AND SI FLOW S1200.12O BREAK FLOW SI FLOW 800 mm 4 00 Or....
0 100 200 300 400 500 600 700 TIME (SEC)
Figure 12 SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK HOT LEG TEMPERATURE 800 700 S600 J
500 400 3 0 0 200 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 13.
SONGS1 SBLOCA WITH SI UPGRADE 3 INCH BREAK COLD LEG TEMPERATURE 800 La..
a 600 500 400
-300 200 0
100 200 300 400 500 600 700 TIME (SEC)
FIGURES FOR 4 INCH BREAK Figure 14 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK NORMAUZED REACTOR POWER 1i ll()ooc*
1.0.0 0.9.001 30.700 0
0.600 0.500 T0.40I
~0.300 0 z 0.2 0 0 00100 0.000 1*a a
0 100 200 300 400 500 600 700 TIME (SEC)
Figure 15 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK RCS PRESSURE 2500 2000 1500 1000 w 500 a
0 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 16 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK PRESSURIZER MIXTURE LEVEL 25 20 -2 Li
~15
...J 0
0 100 200 300 400 500 600 700 TIME (SEC)
Figure 17 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK STEAM GENERATOR PRESSURE 1 200.
12500 Fn 800 0
0 w
U, 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 18 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK RX VESSEL DOWNCOMER MIXTURE LEVEL 25 20
-15 m
5 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 19 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK RX VESSEL UPPER HEAD MIXTURE LEVEL 8
-j4 01 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 20 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK MIXTURE LEVEL FROM TOP OF CORE 10 8
6 w 4 2
0
-2 top of core
-6
-8 10 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 21 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK LOOP SEAL MIXTURE LEVEL 25 o-20 w
a15 w
W 10 0
0 100 200 300 400 500 600
- 700, TIME (SEC)
Figure 22 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK SI FLOW AND BREAK FLOW 2000 00 h1600 -
BREAK FLOW
-SI FLOW
%1200 a800 0400 0
I 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 23 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK HOT LEG TEMPERATURTE 800 700
~600 500 400 300 200 1 0
100 200 300 400 500 600 700 TIME (SEC)
Figure 24 SONGS1 SBLOCA WITH SI UPGRADE 4 INCH BREAK COLD LEG TEMPERATURE 80 cj j I
00 600 400 200 0
100 200 300 400 500 600 700 TIME (SEC)
FIGURES FOR 6 INCH BREAK Figure 25 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK NORMAUZED REACTOR POWER 0.900 0.700 3 0.000 - -
0 0-0.600O L~0.500O S0.400
~0.300 Z 0.200 0.100 0
50 100 150 200 250 300 350 400 TIME (SEC)
Figure 26 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK RCS PRESSURE 2500 2000 61~500 6-d 1 0 0 w
in 1000 500 0
50 100 150 200 250 300 350 400 TIME (SEC)
Figure 27 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK PRESSURIZER MIXTURE LEVEL 25....
e20
-J15 cJ J10 0
0 50 100 150 200 250 300 350 400 TIME (SEC)
Figure 28 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK STEAM GENERATOR PRESSURE 1200.....
F 800 LU Ld 400 O
0 50 100 150 200 250 300 350 400 TIME (SEC)
Figure 29 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK RX VESSEL UPPER HEAD MIXTURE LEVEL 0....I...I..........................I..
J 0
50 100 150 200 250 300 350 400 TIME (SEC)
Figure 30 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK REACTOR VESSEL DOWNCOMER MIXTURE LEVEL 25 20 w
w W10 E5 0
50 100 150 200 250 300 350 400 TIME (SEC)
Figure 31 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK MIXTURE LEVEL FROM TOP OF CORE 10....---.-...
8 6
W 4
2 Fla 0
top of core
-2 S-6
-8
- 10 0
50 100 150 200 250 300 350 400 TIME (SEC)
Figure 32 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK LOOP SEAL MIXTURE LEVEL 25........-......------.-.----.....
15
-J W10 0
0 50 100 150 200 250 300 350 400 TIME (SEC)
Figure 33 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK BREAK FLOW AND SI MASS FLOW RATE 4400.
o4000
.... BREAK FLOW 0
-SI FLOW u 3600 23200
-2800 2400 92000 031600
-1200 800 400 0
0 50 100 150 200 250 300 350 400 TIME (SEC)
Figure 34 SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK HOT LEG TEMPERATURE 800 - -
600 U400 200*
0 50 100 150 200 250 300 350 400 TIME (SEC)
Figur~e SONGS1 SBLOCA WITH SI UPGRADE 6 INCH BREAK COLD LEG TEMPERATURE 8 00 600 400 200 0
50 100 150 200 250 300 350 400 TIME (SEC)
APPENDIX 1 ENHANCED CHARGING/SI BYPASS R ST VOLUME CONTROL TANK N2 FCV-lll2 NDV 1100 C CHARGING TO LOOP A FCV 1115 F1 MOW 100 G-A
mo 110015' HY 85 04 Figure 36 ALTERNATIVE D FRON TO RCS st PunAs ENHANCED CHARGINGISAFETY INJECTION BYPASS
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