ML20151W252

Discusses Redirection of Previously Proprietary Matl Into Public.Encls 1 & 2 Originally Submitted with Westinghouse Ltr NSD-NRC-96-4848 (ANO 9610240050.) Proprietary Markings Removed

ML20151W252
Person / Time
Site:	05200003
Issue date:	09/11/1998
From:	Huffman B NRC (Affiliation Not Assigned)
To:	Ted Carter NRC (Affiliation Not Assigned)
References
NUDOCS 9809150241
Download: ML20151W252 (10)

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52 4 September 11,1998 TO: Tajuan Carter FROM:

Bill HuffmaQM I

SUBJECT:

Redirection of Previously Proprietary Materialinto the Public The information provided in Enclosures 1 and 2 of this memo were originally submitted with Westinghouse letter NSD-NRC-96-4848 dated October 16,1996 and were identified as proprietary (See Accession #9610240058). Westinghouse letter DCP/NRC1420 dated ,

August 19,1998, (Enclosure 3), (Accession #9808260221), states that the information in  !

Enclosures 1 & 2 is no longer considered proprietary.

Therefore, I have removed the Westinghouse proprietary markings from Enclosures 1& 2 so that l it can be placed into the public files.

1 Please place Enclosures 1 & 2 onto the AP600 docket and public microfiche and update  !

NUDOCS to reflect this change.

If you have any questions please call me at 301-415-1141.

l Enclosure 1: Fission Product Transport Calculations from Westinghouse Letter NSD- I NRC-96-4848 dated October 16,1996 (Proprietary markings removed) j Enclosure 2: RAI Information from Westinghouse Letter NSD-NRC-96-4848 dated j October 16,1996 (Proprietary markings removed) l Enclosure 3: Westinghouse letter DCP/NRC1420 dated August 19,1998 cc w/o enclosures: TRQuay JSebrosky / l l

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I- PDR ADOCK 05200003 I i PDR ( i

- Enclosure I to Westinghouse Letter NSD-NRC-96-4848 October 16,1996 i

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l ENCLOSURE 1 l

ORNL Requested Information for Fission Product Transport Calculations Data as requested for the AP600 Containment pH Assessment by Mr. C.F. Weber of Oak Ridge National Laboratory during August 29 - 30,1994 meetings on AP600 Design Basis Source Terms was previously transmitted to the NRC in Westinghouse letter NTD-NRC '

4308, dated September 23,1994. This transient information was taken from the MAAP4 analysis for case 3BE. base (as presented in Appendix L of the AP600 Probabilistic Risk Assessment (PRA) Report, Revision 1). l The following transient information is the updated data from Revision 8 of the AP600 PRA.

This data is taken from the MAAP4 analysis for Case 3BE-2 as presented in Chapter 34 (subsection 34.4.1.2) of the PRA, Revision 8, report.

1. Configuration Information j 1

The MAAP4 model schematic drawing is presented in Figure 44-1 of the Chapter 44 of 1 Revision 8 of the AP600 PRA, and is included in this enclosure. The MAAP4 containment I modelis divided into 9 nodes inside the pressure boundary and 2 nodes outside the pressure l

l boundary which model the passive containment cooling system (PCS) annulus and auxiliary  :

building. The containment geometry is defined in the

• AUXILIARY BUILDING section of l WCAP-14729. The 9 nodes inside the containment represent.

Node 1 - Loop Compartment 1 (SG Room 1) )

l Node 2 - Loop Compartment 2 (SG Room 2) i Node 3 - Lower Compartment Node 4 - Reactor Cavity Node 5 - IRWST Node 6 - Refueling Cana' and Center Region of Upper Compartment l Node 7 - Upper Comparmt Region along PCS shell vertical walls Node 8 - Upper Compartment Dome Node 9 - Valve Vault i The nodes are connected by 24 interconnecting flow paths or ' junctions.* The junction characteristics are defined in the

• TOPOLOGY section of WCAP-14729. The following is a list j of the important water flow junctions for the pH analysis (the other junctions are described in l WCAP-14729): l Junction 1 - Reactor Cavity to SG Rooms through Tunnel Junction 4 - SG Room 1 to SG Room 2 through Tunnel

! Juriction 8 - IRWST to Refueling Canal (Overflow)

' Junction 9 - SG Room 1 to Lower Compartment Junction 10- Lower Compartment to Auxiliary Building (Containment Leakage)

[ Note the enclosed drawing incorrectly has this junction originating from the IRWST room) 1 l

Junction 1ti- Refueling Canal to Reactor Cavity (Overflow)

Junction 21- IRWST to SG Rooms (Cavity Flooding System which spills to pH control sumps Junction 22- Valve Vault to Reactor Cavity

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Junction 23- IRWST to Valve Vault (via Drain)

\ The containment heat sink data is supplied in section

• DISTRIBUTED HEAT SINKS and

• LUMPED HEAT SINKS sections of WCAP-14729. There are 39 distributed heat sinks modeled which include walls, floors and wetted and unwetted portions of the PCS shell.

Several dummy heat sinks are included in the model to direct condensate flow from the PCS i shell to the IRWST. The 13 lumped heat sinks represent metal equipment in the containment.

The descriptions of each of the heat sinks is provided in WCAP-14729.

The node, junction and heat sink numbers are used as indices for each variable to identify the node or junction to which each variable applies.

2. Initial Conditions

} The initial conditions for each of the containment transient variables can be found at time zero g on the plot files provided and described in Section 3.

_ 3. Trenslent information Volumes and Areas and Characteristic Lengths - the transient volumes of nodes and the areas and lengths of heat sinks can be found from the configuration information provided in Section 1 along with the nodal water elevations (variable ZWRB(n) in plot files 35 and 36, n =

" the node number). *. Vater volume as a function of water elevation is provided in tabular form in the

• AUXILIARY BUILDING section of WCAP-14729.

The gas and water temperatures (TGRB(n) and TWRB(n), respectively) in each of the nodes are provided in plot file 91.

The inside surface temperatures for each heat sink (THSRB(1,hs), hs= heat sink number) up to heat sink 29 are provided in plot file 91.

The flow rates along each containment flow path, or junction, up to junction 21 are provided in plot file 34. Flow rates for junctions 22,23 and 24 are provided in plot file 91. The direction of the flow (positive or negative) is defined by the upstream and downstream nodes as provided in WCAP-14729. The arrows in Figure 44-1 are not necessarily correct. The flow rates are defined as follows:

WRB(j) = gas flow through junction number j WCCRB(j) = counter-current gas flow through junction WWRB(j) = water flow through junction WWCRB(j)= counter current water flow through junction 2

l The' input flow rates from the RCS to the containment are provided in plot files 33 and 91.

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' Flow form the RCS to the containment is considered to be positive. The flow rates are defined as follows (and are in plot file 33 unless otherwise noted):

! WWBB = water flow from break to containment l HWBB = liquid enthalpy of break l WGBB = gas flow from break to containment HGBB = vapor enthalpy of break ,

WWRV = Stage 1 - 3 ADS water flow (Note Case 3BE-2 assumes no ADS 1-3] l HWPZ = liquid enthalpy of ADS flow WGRV = Stage 1 - 3 ADS gas flow [ Note Case 3BE-2 assumes no ADS 1-3]

HGPZ = vapor enthalpy of ADS flow WWGO(1)= Loop 1 Stage 4 ADS water flow  ;

HWBB= liquid enthalpy of Loop 1 Stage 4 ADS flow  !

WGGO(1)= Loop 1 Stage 4 ADS gas flow HGBB= vapor enthalpy of Loop 1 Stage 4 ADS flow WWGO(2)= Loop 2 Stage 4 ADS water flow (Plot file 91)

HWUB = liquid enthalpy of Loop 2 Stage 4 ADS flow (Plot file 91) l WGGO(2)= Loop 2 Stage 4 ADS gas flow (Plot file 91)

HGUB = vapor enthalpy of Loop 2 Stage 4 ADS flow (Plot file 91)

WWGO(3)= IRWST injection flow to the reactor vessel (before switchover to recirculation) and recirculation flow to the reactor vessel (after switchover to recirculation)

There is no filtration credited in the AP600 containment system.

The steam condensation rate in each node is provided on plot file 91 as variable WCDTRB(n),

where n = node number. These rates are not conveniently available for each heat sink.

4. Sources Fission product sources enter the containment as defined by the NRC physically based source term (NUREG-1465).

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5. Summary of Attached Plot Files l The following plot files are provided on diskette:

3BE-2.d33 - Break Flow and RCS to Containment Interface Data l 3BE-2.d34 - Containment Junctions Flow Data 3BE 2.d35 - Containment T&H Data (Lower Compartments) 3BE 2.d36 - Containment T&H Data (Upper Compartments) 3BE 2.d91 - Heat Sink Temperatures, plus junctions 22,23 and 24 data, plus Loop 2 ADS Stage 4 data, plus condensation rates 3

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j The' files are provided in an ASCll format, compressed file created using the PKZIP l

commercially available software for DOS. The files are self-extracting executable (so you l don't need PKUNZIP) to expand them. To expand the files, copy the file from the disk to a i directory and type '3bedata' at the command line while in the directory. The files will need approximately 4 megabytes of space.

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Reference:

WCAP 14729, AP600 MAAP4 Parameter File and Input Deck for Probabilistic Risk Assessment, Westinghouse Proprietary, transmitted to NRC in Westinghouse letter NSD-NRC-96-4828, September 30,1996.

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44. MAAP4 Code Descript1:a and AP600 Modeling s

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MD Node 1 = SG Compt i Node 7 = Upper Compt Outer Volume Node 2 = SG Compt 2 Node 8 = Upper Compt Dome l Node 3 = Lower Compartment l Node 9 = Valve Vault Node 4 = Reactor Cavity . l Node 10 = PCS Dome NMe 5 = IRWST Room l Node 11 = PCS Annulus Node 6 = Upper Compt Inner Volume Node 12 = Environment

+ Refueling Canal Figure 44-1 AP600 MAAP4 Containment Model Nulallration i

Revision: 8 September 30,1996 3 Westiflgh0038 .

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• Enclosure 2 to Westinghouse Letter NSD-NRC-96-4848  !

l October 16, 1996 l l

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ENCLOSURE 2 RAI Information RAI 470.21 requested 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.

Updated data from case 3BE-2 (of Chapter 34 of the Revision 8 AP600 PRA) is included here, l replacing data previously transmitted in attact, ment to NTD NRC-95-4431, dated April 7,1995.

Case 3BE-2 is a LOCA involving the direct vessel injection (DVI) line, and has been analyzed  ;

using the MAAP4 computer code. The code output provides the masses of Csl in each of the l containment compartments and the masses of all twelve fission product groups in the l deposited state in the containment. Plot files containing this data are provided on the enclosed diskette. The files are:

3BE-2.fp1 Masses of Cslin each containment compartment i 3BE-2.fp2 Masses of all aerosol groups in the deposited state in containment I compartments The data provided in these two plot files include:

MFPRB(i,j,k) = the mass of fission product (kg) i = fission product group; i = 1 noble gases, inert aerosols 2 Csl 3 TeO2 l 4 SrO 5 moo, 6 CsOH 7 BaO 8 La,0 3+Pr 0 3+Nd2O3 +Sm2 03 +Y203 9 CeO, 10 Sb 11 Te 2 12 UO,+ NpO,+PuO 2 1

j = fission product state; j = 1 Gaseous 2 Aerosol (airbome) l 3 Deposited l

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k = containment node; k = 1 Loop Compartment 1 (SG Room 1) 2 Loop Compartment 2 (SG Room 2) 3 Lower Compadment 4 Reactor Cavity 5 IRWST 6 Refueling Canal and Center Region of Upper Compadment 7 Upper Compartment Region along PCS Shell Vertical Walls 8 Upper Compadment Dome 9 Valve Vault I

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t Westinghouse Energy Systems hx 355 Pinsburgh Pennsylvania 15230-0355 Electric Corporation DCP/NRC1420 NSD-NRC-98-5761 Docket No.: 52-003

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August 19,1998 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY

SUBJECT:

RESPONSE TO NRC LETTERS CONCERNING REQUESTS FOR WITHHOLDING INFORMATION

Reference:

1. Letter, Jackson to Liparulo, " Request for withholding information from public disclosure for Westinghouse AP600 design letter of May 15,1995," dated Janua y 22,1996.

2. Letter, Jackson to McIntyre, " Request for withholding information from public disclosure for Westinghouse AP600 design letter of October 28,1996," dated February 19,1997.

3. I etter, McIntyre to Quay, " Nonproprietary versions of material provided by Westinghouse letter NSD-NRC-96-486,4, dated May 16,1997.

4. Letter, Huffman to McIntyre, " Request for withholding information from public disclosure for Westinghouse AP600 design letters," dated July 14, 1998.

5. Letter, McIntyre to Quay, " Response to NRC letter of August 23,1995,

' Request for withholding information in the design certification application for the AP600,'" DCP/NRCl400, dated July 22,1998.

Dear Mr. Quay:

Reference I sets forth the NRC assessment of the Westinghouse claim for treatment of proprietary information submitted by Westinghouse in a letter dated May 15,1995, which letter provided Westinghouse report PCS-T2R-050, "Large Scale Test Data Evaluation, May 1995." The NRC assessment was that with the exception of Figure 1-3, "Large-scale PCS instrumentation Elevations" located on page 18, the material identified as proprietary would be withheld. The staff claimed that the identified figure was available to the public through other Westinghouse reports. In a telephone call with Ms. Jackson on January 29,1996, Westinghouse agreed that the identified figure was not

- prop 4 iary. Ms. Jackson indicated that the identified figure would be placed in the Public Document _

Room. This letter provides written confirmation that the identified figure is not considered proprietary by Westinghouse.

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DCP/NRCl420 l

NSD-NRC-98 5761

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August 19,1998 l l

Reference 2 sets forth the NRC assessment of the Westinghouse claim for treatment of proprietary information submitted by Westinghouse in a letter dated October 28,1996, which letter provided formal documentation of informal correspondence sent to the NRC by Westinghouse for the period September 23,1996 through October 24,1996. He NRC assessment was that the nonproprietary

version of the document was not acceptable. A revised nonproprietary version of the attachment to l Reference 2 was provided in Reference 3. His revised nonproprietary version of the document included summaries of the proprietary material in those few instances where it had been removed.

Reference 4 sets forth the NRC assessme.it of the Westinghouse claim for treatment of proprietary information submitted by Westinghorse in a letter dated October 16,1996, which letter provided fission product transport calculatior.s and fission product source rates for the AP600. The NRC assessment was no information was identified as being proprietary and that no nonproprietary version of the document was provided. The information provided in the Westinghouse letter of October 16, 1996, was similar to that provided in the AP600 probabilistic risk assessment on June 26,1992. The l proprietary information in that report, and subsequent updates, was addressed in Reference 5.

Reference 5 indicates the information related to fission product transport calculations and fission product source rates for the AP600 is no longer considered proprietary and the October 16,1996, letter can be placed in the public document room.

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A l Brian A. McIntyre, Manager Advanced Plant Safety and Licensing Jmi cc: J. W. Roe - NRC/NRR/DRPM J. M. Sebrosky - NRC/NRR/DRPM

? W. C. Huffman - NRC/NRR/DRPM -

li. 'A. Sepp - Westinghouse i

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