View source for NRC-95-4431, Forwards Info Re Distribution of Fission Products in Containment Following loss-of-coolant Accident.Info Provided in Response to Staff Request for Addl Info 470.21

{{Adams
| number = ML20087G665
| issue date = 04/07/1995
| title = Forwards Info Re Distribution of Fission Products in Containment Following loss-of-coolant Accident.Info Provided in Response to Staff Request for Addl Info 470.21
| author name = Liparulo N
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05200003
| license number = 
| contact person = 
| document report number = NTD-NRC-95-4431, NUDOCS 9504140203
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 5
}}

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           . Westinghouse              ~ Energy Systems -                                    Ba 355 Pittstmrgh Pennsytvania 15230-0355        ,
Electric Corporation NTD-NRC-95-4431 DCP/NRC0303 Docket No.: STN-52-003 April 7,1995 -
Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NITENTION:           T. R. QUAY -
SUIUECT:             INFORMATION REQUESTED BY RAI 470.21 REGARDING DISTRIBUTION OF FISSION PRODUCT GROUPS THROUGHOUT A LOCA TRANSIENT SEQUENCE

==Dear Mr. Quay:==

The enclosure to this letter provides information regarding the distribution of fission products in the containment following a postulated Loss-of-Coolant Accident. This information is provided in response to staff's request for additional information 470.21.
The information in the enclosure includes the following:
^
_f. Masses of cesium iodide in each of the eight containment compartments
: 2. Masses of each of 12 fission product groups deposited in any of the six containment compartments where deposition can occur.
The two electronic files containing this infonnation are included on a diskette with Jay Lee's copy.
Please contact Brian A. McIntyre on (412) 374-4334 if you have any questions concerning this transmittal.
bLh5 N. J. Liparuto, Manager
                                           ,C Nuclear Safety Regulatory and Licensing Activities                                                                        q
           /nja Enclosure Attachment                                                                                                                 3 i
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          . ec:    T. J. Kenyon        NRC (w/o Enclosure)
J. Lee              NRC                                                                                             i B. A. McIntyre     Westinghouse (w/o Attachment. Enclosure) mu                        4 ! ('f- C "l 9504140203 950407                 ?                                                              '
PDR     ADOCK 05200003                                                                         i A                        pg                                                                        }

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ATTACHMENT TO LETTER NTD-NRC-95-4431 RAI 470.21 asks for information regarding fission product source rates into the various compartments in the containment and the distribution of the fission product groups throughout a transient sequence.
The areas of concern have been further defined as being the particulate iodine (existing as cesium iodide) in all of the compartments and all particulate groups in any compartment where deposition may occur.
The severe accident Case 3BE, which is a LOCA involving the eight inch direct vessel injection (DVI) line, has been analyzed using the MAAP4 computer code. The code output provides the masses of Csl in each of the containment companments and the masses of all twelve fission product groups in the deposited state in the containment (six of the eight compartments collect deposited particulates).
Plot files containing this data are provided on the enclosed diskette. The files are:
FPl. PLT            Masses of Csl in each containment compartment -
FP2. PLT            Masses of all aerosol groups in the deposited state in containment compartments The data provided in these two plot files include:
MFPRil(i,j,k) = the mass of fission product (kg) i = fission product group;    i=     1       noble gases, inert aerosols 2       Csl 3       TcO2 4       SrO 5       moo 2 6       CsOH 7       Ba0 8       La2 0 3+Pr2 0 3+Nd20 3+Sm203 +Y203 9       CeO 2 10      Sb i1      Te2 12      UO2+NpO 2+PuO2 j = fission product state;    j=      1       Gaseous 2       Aerosol (airborne) 3       Deposited k = containment node          k=     1       Loop Compartment 1 2       Loop Compartment 2 3       CMT/ Accumulator Rooms 4       Reactor Cavity 5       IRWST Compartment 6       Upper Compartment (including refueling canal) 7       Upper Compartment (next to cylinder wall) 8       Upper Compartment (dome) am

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-73 AP600 Case 3BE,    8" DVI Line Break TIME                   MFPRB(1,3,1)         MFPRB(1,3,2)          MFPRB(1,3,3)     MFPRB(1,3,4)
* MFPRB(1,3,5)           !EPRB(1,3,6)         IFPRB(2,3,1)          MFPRB(2,3,2)     MFPRB(2,3,3)
MFPRB(2,3,4)           MFPRB(2,3,5)         WPRB ( 2, 3, 6 )      MFPRB ( 3, 3,1 ) MFPRB(3,3,2)            -
MFPRB(3,3,3)           MFPRB(3,3,4)         MFPRB(3,3,5)          MFPRB(3,3,6)     MFPRB(4,3,1)              +
MFPRB(4,3,2)           MFPRB(4,3,3)         MFPRB(4,3,4)          MFPRB(4,3,5)     MFPRB(4,3,6)
MFPRB(5,3,1)           MFPRB(5,3,2)         MFPRB(5,3,3)          MFPRB(5,3,4)     MFPRB(5,3,5)
MFPRB(5,3,6)           MFPRB(6,3,1)         MFPRB(6,3,2)          MFPRB(6,3,3)     IFPRB(6,3,4)
IFPRB(6,3,5)           MFPRB(6,3,6)         MFPRB (7, 3,1)        MFPRB(7,3,2)     MFPRB(7,3,3)
MFPRB(7,3,4)           MFPRB(7,3,5)         MFPRB (7, 3, 6 )      MFPRB(8,3,1)     IFPRB(8,3,2)
MFPRB(8,3,3)           MFPRB(8,3,4)         MFPRB(8,3,5)          MFPRB(8,3,6)     MFPRB(9,3,1)
MFPRB(9,3,2)           MFPRB(9,3,3)         MFPRR % % 4)          MFPRB(9,3,5)     MFPRB(9,3,6)
MFPRB(10,3,1)          MFPRB(10,3,2)        MFPRB(10,3,3)         MFPRB(10,3,4)    MFPRB(10,3,5)
MFPRB(10,3,6)          MFPRB(11,3,1)        MFPRB(11,3,2)         MFPRB(11,3,3)    MFPRB(11,3,4)
MFPRB(11,3,5)          MFPRB(11,3,6)       'MFPRB(12,3,1)         MFPRB(12,3,2)    MFPRB(12,3,3)
MFPRB(12,3,4)          MFPRB(12,3,5)        'EPRB ( 12, 3, 6 )
SECONDS       KG             KG            KG                 KG         KG       KG            KG -
KG KG KG KG KG KG KG KG KG KG KG KG KG KG KG KG M
KG             KG             KG            KG                 KG         KG       KG            KG            g KG             KG             KG            KG                 KG         KG       KG            KG     O KG             KG              KG           KG                 KG         KG       KG            KG KG             KG             KG            KG                 KG         KG       KG            KG      ,,
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0.000E+00    0.000E+00    0.000E+00  0.000E+00      0.000E+00                                                  b
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0.000E+00    0.000E+00    0.000E+00  0.000E+00      0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.C30E+00 0.000E+00      0.000E+00                                                  3 f*==.

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