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{{#Wiki_filter:. --._.. ENCLOSURE 1 RWST VORTEX TEST NO. 2 UNIT SALEM NUCLEAR GENERATING STATION A test was performed at the request of the NRC to verify that the Refueling Water Storage Tank (RWST) would not rience any vortexing during the course of events that would follow a Loss of Coolant Accident (LOCA). The test was performed basic;:;*?:';'l-::?z; | {{#Wiki_filter:. -- ._.. | ||
.. following the sequence of actions that would occur after the start of post-LOCA tion, assuming a large Reactor Coolant System pipe break. For purposes of vortex determination, the large break would be the most conservative and the most likely to create texing due to maximum pump demand from the RWST. At all times during the test the various pumps were tored for signs of cavitation and the interior water face of the RWST was visually monitored for vortexing. | ENCLOSURE 1 RWST VORTEX TEST NO. 2 UNIT SALEM NUCLEAR GENERATING STATION A test was performed at the request of the NRC to verify that the Refueling Water Storage Tank (RWST) would not expe-rience any vortexing during the course of events that would follow a Loss of Coolant Accident (LOCA). | ||
The three key points of concern were: (1) just prior to the low level alarm setpoint where two RHR pumps and one tainment Spray pump were terminated, (2) approximately 11 minutes after low level where switchover to recirculation would take and the two Safety Injection pumps were terminated, and (3) where the final Containment Spray pump was terminated, which is at the low-low level alarm point. The visual observations of the RWST water indicated no signs of vortexing and showed a calm surface throughout the test. EAL: jb HA6 I . N µ:i p:; | The test was performed basic;:;*?:';'l-::?z;.. following the sequence of actions that would occur after the start of post-LOCA injec-tion, assuming a large Reactor Coolant System pipe break. | ||
For purposes of vortex determination, the large break would be the most conservative and the most likely to create vor-texing due to maximum pump demand from the RWST. | |||
At all times during the test the various pumps were moni-tored for signs of cavitation and the interior water sur-face of the RWST was visually monitored for vortexing. | |||
The three key points of concern were: (1) just prior to the low level alarm setpoint where two RHR pumps and one Con-tainment Spray pump were terminated, (2) approximately 11 minutes after low level where switchover to recirculation would take ~lace and the two Safety Injection pumps were terminated, and (3) where the final Containment Spray pump was terminated, which is at the low-low level alarm point. | |||
---_I ---_ | The visual observations of the RWST water indicated no signs of vortexing and showed a calm surface throughout the test. | ||
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Latest revision as of 09:52, 3 February 2020
ML18082A149 | |
Person / Time | |
---|---|
Site: | Salem ![]() |
Issue date: | 04/03/1980 |
From: | Public Service Enterprise Group |
To: | |
Shared Package | |
ML18082A148 | List: |
References | |
NUDOCS 8004110475 | |
Download: ML18082A149 (4) | |
Text
. -- ._..
ENCLOSURE 1 RWST VORTEX TEST NO. 2 UNIT SALEM NUCLEAR GENERATING STATION A test was performed at the request of the NRC to verify that the Refueling Water Storage Tank (RWST) would not expe-rience any vortexing during the course of events that would follow a Loss of Coolant Accident (LOCA).
The test was performed basic;:;*?:';'l-::?z;.. following the sequence of actions that would occur after the start of post-LOCA injec-tion, assuming a large Reactor Coolant System pipe break.
For purposes of vortex determination, the large break would be the most conservative and the most likely to create vor-texing due to maximum pump demand from the RWST.
At all times during the test the various pumps were moni-tored for signs of cavitation and the interior water sur-face of the RWST was visually monitored for vortexing.
The three key points of concern were: (1) just prior to the low level alarm setpoint where two RHR pumps and one Con-tainment Spray pump were terminated, (2) approximately 11 minutes after low level where switchover to recirculation would take ~lace and the two Safety Injection pumps were terminated, and (3) where the final Containment Spray pump was terminated, which is at the low-low level alarm point.
The visual observations of the RWST water indicated no signs of vortexing and showed a calm surface throughout the test.
EAL: jb HA6
I. *1 I
\
1 N
µ:i p:;
ti) 0 I
..:I r-1 u
z " ,, I
µ:i I
D~T A\L 3
~
BLL. OF. MA1ERlAL 2
3G 8
10 4
<O
'2.
-\
lG
- I
}
St:CTION A-A D~T~\L '2 _
~\
N
"-co
. ~
~
~
I E~lSf. 7
,, , J;>L 4'1L4ic~
I I w~ = I .. /
/.
- ~-----1 1. .
~~~-~--:i.":"::)~"~~~-~...__~-~ -~*~-~-~- --~~~--'t ---
~~~- SE:E
..--.--L--...-.:
~Q:) - - -_I---_ - -1*+---t - ll-~~M!Jl. ;-A.3-T* I I oe-r:~s' I 4'-rb---*--- . . .. . I ~
I I
+ *--. . ---4'-~
-~ . ******---------
REO~ILL tllST. ,1;"d> . NOTE: ALL STr?UCJURAL STtt.L JO P!>E HoLES ro ?"~ 1TrP.l s.s.ASTM 6£ADE' A>Z40 l"'(PE 3o4
-~ ~
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