IPE Data Base: Plant design, core damage frequency and containment performance information Page: 3 of 10
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Substantial progress has been made on the IPE Data Base over the last two years and it is largely complete.
Entries into the IPE Data Base from the IPE internal events examination have been finished with all IPEs entered.
FOCUS OF CURRENT DEVELOPMENT
The recent focus of the work on the IPE Data Base has been the development of a user friendly version which is
menu driven and allows the user to ask queries of varying complexity easily, and without the need to become
familiar with particular data base formats or conventions such as those of dBase IV or Microsoft Access. The
user can obtain the information he or she is interested in by quickly moving through a series of on-screen menus
and "clicking" on the appropriate choices. In this way even a first time user can benefit from the large amount
of information stored in the IPE Data Base without the need of a learning period.
The development of this user friendly version is currently (October 1995) incomplete and will undoubtedly
undergo substantial changes before being released next year. However, the following discussion and the
accompanying figures show the direction of the development and indicate the ease with which a user will be able
to manipulate the IPE Data Base. At the same time, what follows also serves to illustrate the kind of information
available in the database and provides examples of some very simple queries.
One of the first menus a user will see will provide a choice of which IPE Data Base files to manipulate as well
as choice of which plants to enquire about. Figure 1 shows the current scheme where the General Plant
Information File has been chosen and some of the possible selection criteria are shown, i.e. plant name, vendor,
reactor type, or containment type. Combinations of these criteria can be used and additional criteria are being
added. Figure 2 shows the result of selecting a single plant by name. Figure 3 shows the result of selecting all
BWRs with Mark I containments. Note that in the latter case the screen indicates that what is shown is the first
of 18 records and the other records can be accessed by "clicking" on the "First," "Previous," "Next," or "Last"
buttons. Subsequent development will allow viewing more than one record at a time.
Figure 4 shows a simple query regarding the information on core damage frequency. The left side of the screen
shows that the query asks for all Westinghouse four loop plants with a CDF greater than 1.E-5. The right side
of the screen indicates there are 20 such plants, with the fifth record shown, i.e. Comanche Peak 1&2. Again
viewing more than one record per screen will be available in the future.
Figure 5 indicates the kind of information available in the Accident Sequence File of the IPE Data Base. A single
plant, St. Lucie 1, has been selected and the screen indicates that the IPE submittal for this plant provided
information on 109 accident sequences, with the fourth sequence shown on the screen. The screen shows the
designation given this sequence in the IPE submittal, the plant damage state (PDS) it was assigned to, the initiator
(S3: a small-small LOCA), and the CDF of the sequence along with the total plant CDF. The screen also
indicates that high pressure recirculation (HPR) and another system, designated ARI in the generic IPE Data Base
nomenclature, have failed and led to core damage in this sequence. The "Notes" field on the right side of the
screen provides additional information. To determine what system corresponds to ARI in this plant the user can
go to the Front Line Systems File and see, as indicated in Figure 6, that ARI for St. Lucie refers to the Shutdown
Cooling System.
If the user wants to see the success strategies used in the St. Lucie IPE for the S3 initiator, the Success Strategy
File for this plant indicates, as shown in Figure 7, that there are four strategies with the first one indicated on the
screen (Record 1 of 4). This strategy relies on high pressure injection (HPI), high pressure recirculation (HPR),
secondary side heat removal (SSMU), and containment heat removal (CPSR). A look at the other strategies,
such as feed and bleed for instance, would show that they all require HPR, and this correlates with the fact that
HPR failure leads to core damage for this initiator, as indicated in the accident sequence shown in Figure 5.
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Lehner, J.; Lin, C.C.; Pratt, W.T.; Su, T. & Danziger, L. IPE Data Base: Plant design, core damage frequency and containment performance information, article, December 31, 1995; Upton, New York. (https://digital.library.unt.edu/ark:/67531/metadc669133/m1/3/: accessed April 23, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.