ML20034H790
| ML20034H790 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 02/11/1993 |
| From: | Kelly G Office of Nuclear Reactor Regulation |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17179A859 | List: |
| References | |
| NUDOCS 9303220078 | |
| Download: ML20034H790 (3) | |
Text
!
February 11, 1993 I
NOTE T0:
Chet Poslusny;~1DARi'NRR FROM:
Glenn Kel / SJg, JJ
SUBJECT:
FAX FROM GE DOCUMENTING MODjFICATIONS MADE TO THE ABWR SEISMIC FRAGILITIES FOR SSCs I have enclosed a fax 1 received from Larry Frederick, GE, tbst documents GE's modifications to the fragilities of SSCs modeled in the ABWR PRA-based seismic l
margins analysis.
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Enclosure:
as stated i
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I 9303220078 930309ADOCK 05200001 PDR PDR l
A
FED 10 '93 05::.2Ud1 0 !
. Post-it" brcnd fax transmnul memo 7671 l* os peon 9 h
CiO) JUELL7'
//f/"/WArf)EpxL dec.
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orpt.
enon.
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NENTS/ STRUCTURES FR7.GILITIES i
FYSTEM / COMPONENT MED,CP LOG _STD HCLPF FAIL. PROB.
(A,)
(Be)
(in g)
(Fail /Dem) 1.
Plant Ess. Structures (SI) 2.8
.45
.9D 0.0
-Reactor Building 2.8
.45
.98
-Containment 4.3
.44 1.56
-RPV Pedestal 7.9
.44 2.84
-Control Building 2.8
.45
.98
-Reactor Pressure Vessel 5.3
.33 2.46 2.
Support Systems (PW) a_.__AC Powe_r (ACP) 1.8
.46
.62 1.65-3 X -Diesel Generator 1.81.5
.46.50
.62
- -Transformer (480 V AC) 1.81.1
.46 45
.52
-Motor Control Center
- 1. 8 t.S
.46 50
.62
[
-Cable Tray 3.0
.60
.74
-Relay switch 2.0
.50
.63 A -v v
- t.. A t.
4 6.if
.jf
-A 5
' {* d(A
- b. ELrvice W4ter (S_W1 1.8
.46
.62 9.7E-5 /)
r
%---Tr. ens fe rar r -_
1Ai1
-4 6 ' %
_ 6 2.
2 L/
y D tor-CvuLAelCc.tcr 1.-S.. 's
. 49 '
. 6 2 ) I^'
M
+
N*
fI
% -Pump (Motor Driven) 1.8n.b
.46 45
.62 g
i
-Heat Exchanger 2.01.4
.45.45
.70
-Valve (Motor Operated) 3.0
.60 74
-Check Valve 3.0
.60
.74 K-Room Air Cond. Unit
- 2. 0 4.2.
.50.SD
.63
-Piping 3.0
.60 74 9
-SW Pump Meuse
. -* 2 4't.7 ^>iA'.45
.98
-AC Ducting 3.C 60
.74
-i c.
DC Power (DC_P1 3.3
.46 1.13 7.2E-6 O atteries &
3.3 LG
.46.45 1.13 i
B
- Ittvecter Ckmv 2.2i.1
.46.45
.75 u?fc(7 A
,C.bNT%
3.o w a :2 -
M j
3.
High Press. Core F1pder (UH) 1.8
.46
.62 2.71;-3
%.-Pump (Motor Driven) 1,8 L 6
. 46 iS
.62 l
-Injection Valve (Motor Op) 3.0
.60
.74 3.0
.60
.74 i
-HPCF Pip (ing 7
n.[.lt /
- Ch u k \\/o. v c,
- 3. o
. s. o W
3 4.
Reactor Core Is. Cooling (UR) 2.0
.45
.70 6.oE-2
-Pump (Turbine Driven) 2.0
.45
.70
-Steam Sup. Valve (MO) 3.0
.60
.74
-Discharge Valve (MO) 3.0
.60
.74
-Min Flow Valve (MO) 3.0
.60
.74
-Check Valve 3.0
.60
.74
-RCIC Piping 3.0
.60
.74 E td M qv-k._..
~7 m 2.5,i332 D*
AMyC3 4r n
N. P N3 OS:st1
~
TABLE 191.2-1 (CONTINUED)
MED_CP LOG _STD HCLPF FAIL.FROE (Be)
(in q)
(Fail /Dem) l SYSTEM / COMPONENT (A,)
1.8
.46
.62 3.1E-4 LowPressureCoreF1hder(71) 1.81.6 46.45
.62 S.%-Pump (Motor Driven) 3.0
.60
.74
-Check Valve 3.0
.60
.74
-Injection valve (Mo) 3.0
.60 74
-Discharge Valve (Mo)
.60
.74 3.0 f
-LPCF Piping 45
.70 6.0E-5
- 6. RER Heat Exchanger (HI) 2.0 45 70 2.0
-Heat Exchanger Reactivity control sys. (C) 1.2
.35
.53 1 0E-s 1.2
.35
.53
- 7. -Fuel Assemblies 1.7
.36 74 46 1.33
-CRD Guide Tube 3.9
-CRD Housing 1.9
.36
.32
-Shroud Support 2.0
.50
.63
-Hydraulic Centrol Unit 60
.74 2E-3,1E-1 3.0
- 8. BRVs Close (PC,PC1)
.60
.74 1
3.0
-safety Relier Valve 60 74 6.2E-6 3.0
- 9. Depressuri2ation (Z)
.60 7,
3.0 i
-Safety Relief Valve
- 10. Level & Press. Control (LPL) 3.0
.60
.74 1.0E-2 60 74 3.0
-Safety Relief Valve 3.0
.60
.74 2.45-3 l
.60
.74 3.0
-Safety Relief Valve 46
.62 1.4E-2
- 12. Standby Liq. Cont. Sys. (C4) 1.8
.46 45
.62 1.8 u
.46 45
.62 4 -SLC Tank 1.85 6 f
60
.74
- -SI,C Pump 3.0
-Valve (Motor Operated) 3.0
.60 74
-SLC Piping Condensate Injection (V2) 1.8
.46 62 1.0E-1 J
1.8
.46
.62 l
13.-Pump (Motor Driven) 3.0
.60
.74
-Injection Valve (MO)
.60
.74 3.0
-Piping 1.8
.46 62 1E-3,1E-1 r
- 14. Fire Water Systam (FW)
.45
.79 2.1 46.45
.62
-FW Tank 1.8n.b
)
% -Pump (Diesel Driven) 3.63.o 60.60
.89 l
7' -Injection Valve (Manual)
.60 74 3.0
-FW Piping 3.6
.60
.89
-Valve-(Manual)
HCLPF = A *exP(-2.326*B }
c i
Note:
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