ML20098D299
| ML20098D299 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 05/21/1992 |
| From: | Raftery R GENERAL ELECTRIC CO. |
| To: | Fox J GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 9205280185 | |
| Download: ML20098D299 (21) | |
Text
~
M Y 21 '92 @s%#rVYMttLc 1R3G J
- Y7t2 M 46[
REGULATORY AND ANALYSIS SERVICES San Jose. California RELIABILITY ENGINEERING SERVICES cc:
J. D. Duncan May 21,1992 A. E. Rogers S. Visweswaran
.To:
J. d. Fox
'From:
R. P. Raftery
Subject:
' Requantification of ABWR Level 1 PRA Attached is a draft summary of ABWR Level 1 PRA updated results transmitted to the NRC (Glenn. Kelly).
core damage fr q uency by initiating event and accident class, the event i
and a brief summary of changes and v
trees used to produce these valuestadditions S.inde to the Leve1~1 P The table reolaces Table 19D.4+1 and the trees replace figures 19D.4-1A 4
through 19D.415 of Chapter 190.4 of the SSAR.
copies of Tables 19.3.1 and 190.3-1 indicating modifications made initiating event frequencies.
the PRA models to comply with SER Staff correction S 2 which required a value of 0.1 for the 10RV initiating event frequency.
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F 1
GENERAL ELECTRIC-COMPANY PROPRIETARY INFORMA 05/21/92 4
SUMMARY
OF CHANGES INCORNRATED IN REQUAN Since initially subn.itting the ABWR Level 1 PRA in 1989, GE has made To the extent nunber of changes and improvements in the ABWR design.
f possible; these have been incorpormied into the current requantific In addition, sotte adjustments have been made in arsumed test and maintenance unavailabilities to support Technical Specificati the Level-1 PRA.
--flexibility.
In order to develop the detailed information required by-the Staff, requartification was performed by evaluating each sequente for eac Consequently, the tree to obtain a comprehensive tabulation of cutsets. even The detailed so that only like systems are represented by a sing 190.4 15.
illustrated in revised event tree Figures 190.4-1 through The following list summarizes modifications made to the updated PRA (excluding the addition of ECCS system design detail as it evo have impact en overall core damage freque9cy as well as its distrib accident class:
A drywell high pressure signal bypass timer w o
Autematic SLCS initiation logic was incorporated in ATWS secuen c
to reflect the current design.
Automatic ADS inhibit logic was incorporated in ATWS sequen o
reflect the current-design, Initiating event; frequencies w9re adjusted to accommodate requirement of a value of 0.1=fer the 10RV initiating event o
(Resolution'of Staff SER open item S-2) frequency.
HPCFB. HPCFC, RHRA, RHRB, and RHR o
Scificatien flexibility.
percent to support Technical'S:
(Resolution of Staff SER open item C-4)
Control-and instrumentatinn equipment and o
much addf tional design information is now available.
Hodifim ans reflect dependency of manua In addition, '
L breakdown of components and common cause failures.
failure rates of components within the en DRAFT COPY FEOM ach-gn35g Cb21-92 04:04 PM
- g
MY 21 '92 02:06H1 G E NUCLEAR R.DG J 1 20/22 GENERAL. ELECTRIC COMPANY PROPRIETARY INFORMATIO equipment failures with the self test feature, with the remsining detected through quarterly surveillance testing, 5% being ion capability was incorporated for A hard-wired manual initi backup to the moltiplexing network, o
HPCFB, providing a diverse; Impact of random HVAC f ailure was explicitly included in the requantification, based on the the premise that div o
Loss or control supporting the ECCS equipment of that division.
room HVAC as an initi ting event was also investigated and results are being reported separately in the GE response to Staff SER open item 0 2 which evaluates impact of support system failures on plant trips.
i l
l DRAFT COPY p;;
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4
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+
Seaeral Sectne Cumpsey 23A6tooAs -
MM PRO?RIETARY "NFORMATION n,v 4 o.m i
$3agiard Plant TABLE 19.31 INrflATING EVENT FREQUENCIES Freauecey Per Reactor Year Teitiatina Event
^
1.0 Manual Shadown.
p(0,fg Isolation / loss of Feedsarer
_O.04
. MSIV Oosure '
J.9fa05 Less of Condenser Vacuum O 01' Press. Reg./ Bypass Valves C'osed '
,0M'd, tid Loss of Feedwater -
gO.4,$
- Non lsolazion Ewnt (Trip with bypass)
~
9#6, /8 Isadvsstent (Stuck) Open Relief Vahe -
0.50
--Iass of Offsite Power 0.0579.
less than30 minutes -
0.0246 30 Mientes to 2 Hours 0.0158
- 2 to 8 Houra 0.0017 Greater than 8 liours -
0.0012 SmallLOCA 2
(Liquid Brcak <0.00 5 ft ).
(Sta.am Bruk <03 ft 0.00067 Medium LOrg 4
2
. (LiquidBreak 0.005*5 ft to 03 ft )
0.00021 Large LOCA
~
u,,
-2 (Li,uid Break 03 ft or greater) y (Steam Brr.ak 03 ft or greater)'
l' 2
19315 AsetMnwat d
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FROM 4ce-925ggg7; 35-21-s:
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em i ceneret seanc campezy ABM
- PROPRIETARY IhTORMATION 23A610cAS
- 1..
Standard Plant om u
.I Table 19D.31-Initiating Event Frequencies rutigiggvent
. Etcquency Per Reactor Yeg a
.0 Manual Chutdown
[C</8 Isolaticn/ Lou of Feedwater 0.04 MSIV Closure 1.oss of Condenser Vacuum A#4 46 Preu, Reg /B)pau Valves Cte '
O.01 9W0*00
=
Lou of Feedwater Non. Isolation Event (Trip with bypan)
[#,4A Inadvertent (Stuck) Open Relief Valve
[d</8 0.10 Lou of Offsite Power Less than 30 Minutes 0.0579 30 Minutes to 2 Hours 0.0246 0.01!
2 to 8 Hours Greater than 8 Hours 0.0017 Small LOCA -
O.0012 (Uquid Break <0.00545 fth (Steam Break <03 ft')
9.
0.00067 Medium LOCA 2
(Uquid Break 0.00545 ft to03 h )
0.00021
?arge LOCA 2
(Uquid Break 03 ft or greater) 2 (Steam Break 03 ft or greater).
19D.34 -
Amadment 4
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05-2t-90 04:04 ?M F;;
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