ML20134Q201
| ML20134Q201 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 02/25/1997 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9702260318 | |
| Download: ML20134Q201 (6) | |
Text
m.-_ _ _ _.
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y February 25, 1997 1
APPLICANT: Westinghouse Electric Corporation PROJECT:
AP600 r
SUBJECT:
SUPMARY OF AP600 TELEPHONE CONFERENCE (TELECON) TO DISCUSS QUES-TIONS ON THE STAFF'S COMPARIS0N OF SCDAP/RELAP AND MAAP ANALYSES On February lo,1997, members of the Nuclear Regulato'ry' Commission (NRC)
~
L staff, its contractor at Idaho National Engineering ~ and'Eny'ironmental Labora-tory (INEEL), and Westinghouse conducted a telecon concerning the staff's
. comparison of a SCDAP/RELAP analysis with MAAP.results;for the AP600 3BE core
- damage sequence. NRC questions on the comparison effort where sent in advance to Westinghouse via NRC letter dated January 28, 1997. ' Westinghouse provided responses to the questions during the telecon wh,1ch a~re summarized in. Attach-ment 1.
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l During.the telecon, Westinghouse noted that the 3BE. TAB ; file would'be hblpful in the INEEL comparison effort.' Westinghouse'committ'ed to< provide the staff a-copy of this file if the staff did not already have it "The st.aff subse,
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quently informed Westinghouse that it did not have this file'and Westinghouse l
stated that it would send the NRC a copy. > ;i }K
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Software used to analyze ex-vessel reactor coolin;g' (EVRC) was discus' sed during the telecon. The staff stated it was interested in obtaining'a copylof the software to perform some sensitivity. studies ~. Attachment 2 is a matr'ix of some of the sensitivities the staff would like to analyze. Westinghouse.
stated that it would look into obtaining a copy of_ the EVRC software for NRC
.use.
m original signe~d by:
William C. Huffman, Project Manager Standardization Project, Directorate i
Division of Reactor' Program Management
-Office of Nuclear Reactor Regulation Docket No.52-003 1
gQM Attachments: As stated cc w/ attachments:
See next page DISTRIB!JTION w/ attachments:
T8ecketM11ei"1 PDST R/F TKenyon l
PUBLIC BHuffman DTJackson JSebrosky RPalla, 0-8 H7 CBerlinger,-0-8 H7 i
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DISTRIBUTION w/o attachments:
SCollins/FMiraglia, 0-12 G18 AThadani, 0-12 G18 RZimmerman, 0-12 G18
.TMartin DMatthews TQuay ACRS (11)
JMoore, 0-15 B18
'4 Dean, 0-17 G21 i
DOCUMENT NAME: A:SCCAP. MAP n
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l NAME WCHuffmdn&r w TRQuay S Q DATE a RY/97 l
970226031e 9f0225 -
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'ICIAL RECORD COPY i
PDR ADOCK 05200003 5
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Westinghouse Electric Corporation Docket No.52-003 cc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 I
Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation 19901 Germantown Road P.O. Boy,355 Germantown, MD 20874 Pittsburgh, PA 15230 1
Mr. Ronald Simard, Director Mr. P. A. McIntyre Advanced Reactor Program Advanced Plant Safety & Licensing Nuclear Energy Institute Westinghouse Electric Corporation 1776 Eye Street, N.W.
Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 4
Ms. Lynn Connor Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 Energy Systems Business Unit Box 355 Mr. James E. Quinn, Projects Manager Pittsburgh, PA 15230 LMR and SBWR Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, M/C 165 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro Mr. Robert H. Buchholz 11921 Rockville Pike GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.
U.S. Department of Energy Eckert Seamans Cherin & Mellott i
NE-50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. S. M. Modro PWR Design Certification Nuclear Systems Analysis Technologies Electric Power Research Institute Lockheed Idaho Technologies Company 3412 Hillview Avenue Post Office Box 1625 Palo Alto, CA 94303 Idaho Falls, ID 83415 l
Mr. Charles Thompson, Nuclear Engineer AP600 Certification NE-F.,
1990i Germantown Road Germantown, MD 20874
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Date:
February 10,1997
Subject:
Phone conversation between INEEL, NRC, and Westinghouse.
l Attendees:
INEEL:
l l
Scott Ghan, Ed Harvego, Darrell Knudson, NRC:
Bill Huffman, Bob Palla l
Westinghouse:
Cindy Haag, Jim Scobel The following questions were presented to Westinghouse by the NRC in a fax prior to this conver-sation.
- 1. Q: Could we get a copy of the cuirent documentation for the MAAP code?
A: NRC has a copy and it is about 12 inches thick. NRC will get us the information if we can 1
specify which sections we need.
- 2. Q: Could we get a copy of version 5 of the input model?
A: WCAP-14729, pg 123 contains a copy of the parameter file and input file.
- 3. Q: Could you_ please provide a diagram or explanation of relationships of the nodes in the core and the core barrel?
A: ne reactor vessel wall consists of 10 axial nodes: 5 for the lower head and 5 for the cylin-der. See subroutine PSHS. He core barrel and the core have 17 axial nodes.
- 4. Q: How does TCBL indexing correlate with TRV indexing? See question 3.
A: For radiation heat transfer from the core barrel to the vessel wall, a core barrel node sees the nearest reactor vessel node. See subroutine PSHS. A view factor of one is assumed.
Emissivity from the core banel is given as input.
l MAAP contains no reflector modeling. De core is assumed to instantaneously relocate.
l MAAP calculations are used to estimate source terms and for insight regarding hydrogen l,
generation and migration.
1 I
d The NRC wishes to use this M AAP/SCDAP comparison to establish a level of confidence i
with other MAAP calculations.
- 5. Q: Could you please pmvide a diagram or description that tells the locations of the rows and columns in the model?
4 A: There are 17 axial nodes and 7 radial channels. For the following variables, see documen-tation for the subroutine HEATUP.
ICOLAP = Axial node that contains the top of the slumped core.
ICRUST = Axial node that contains the uppermost layer of the bottom crust.
ITOPCR = Axial node that contains the uppermost layer of the top crust.
ILOWMX = The depth to which natural circulation can penetrate; i.e., the height of core above the top crust.
- 6. Q: What does XTRVII(i) and SIGW(i,j) represent?
A: XTRVII(i) = the thickness of the RV wall at node i after melting.
SIGW(i,j) = wall stress in radial node i, at the jth mesh point.j = 1 is the inside of the ves-sel. See submutine CREEP.
- 7. Q: What does "CCI" represent?
A: Corium Concrete Interaction, j
- 8. Q: In variables MFPRB(x,y,z), x apparently represents the species and z apparently repre-sents the compartment number. Is this tme? What does y represent?
A: MFPRB(x,y,z) = mass of fission products in containment nodes.
x = fission product group y = deposition state - 1 = airborne gas,2 = airborne aerosol,3 = deposited aerosol.
z = compartment index.
The remaining questions were asked, but they were not sent to Westinghouse prior to the tele-phone conversation.
- 1. Q: Primary pressure falls rapidly without plateau at secondary pressure. Please explain briefly.
A: ADS opens and decouples the secondary and primary systems.
- 2. Q: Are ADS stages 1-4 assumed to open simultaneously at 60 s?
A: We are not absolutely cenain, but we believe the ADS actuation timer is assumed to begin at 60 s. The ADS stages then open sequentially according to the timer. We would have to check the LOG file, which records " actions" such as ADS actuation in the calculation.
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- 3. Q: ZWCPS = RCS collapsed liquid level. ZWV = RCS mixture level. What is included in these level calculations? ZWV is sometime less than ZWCPS. Why?
A: We usually don't consider ZWV when looking at system inventory. ZWCPS includes the reactor vessel, hot legs, cold legs, and steam generator tubes. It does not consider the accu-mulators, CMTs, or pressurizer.
- 4. Q: MCMTPS = mass of debris + metal layer. Does this include frozen and molten parts?
A: Yes, it includes everything, including the crust. The subroutine name to look for begins with "lp."
- 5. Q: MCRUMT = mass of debris excluding metal MSSPS = mass of metallayer MXPSU = mass of upper crust MXPSL(i) = mass oflower crust in node i.
Please verify our understanding of these variables. If we add these variables together we do not arrive at MCMTPS. Why?
A: Yes, those are the correct variables. We don't know why they wouldn't add to MCMTPS.
- 6. Q: Is there a way to separate the components of the debris and crust?
A: No. When a relocation occurs, the mass is deposited into a debris mass bin, and the energy is deposited into a debris er.etgy bin. The components are treated as a mixture in the lower head.
- 7. Q: For fission product heating, the following variables are available:
QFPHSF(i), and QQFPPS(j), which represents the power of the deposited and suspended fission products. If I add these together, will I arrive at the total power of the fission prod-ucts released from the fuel?
A: No. Some of the fission products escape through the break. *Ihe output file (which INEEL does not have) states the locations and masses of the fission products. NRC should send us a request for information, and we will send the output file (. tab).
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- 8. Q: Is there a variable that states the power density of the debris bed?
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l A:.No h is nara===rv to manipulate other variables to calculate the power density.
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t column (2 below (15 cases)e1) input parameters set Individually to values sp case:
to values specified in column 3 below (1 case).and (2) input parameters v.h.e pasensent indMdmalSeasmMey Casse Cosmbined Cass Vessel We5 Mehlag Temposeene 90 1300 1600 1900 Peel Peeper Dansky. MW/m' i.e' Flanies Feedues Desey Most la Metal Layer (5) 40 10 Meenale layer hiskaess (e6 0.28 Cesveselam Cervelsenes der Doorsurned Heat Treasier Ng =0.1453Ra* "
Ng = 0.1453Ra* "
Casveseles correlseine der Upweed Heat Tsensier Ng= $.884Rt "
Ng = 3.825ka'
- Ba-Veenal Heat Treasier es a Floeded covky 0.9 U17U leerer Boemd' Upward and Sedeweed Heat Treasist Whhis Metal layer 0.167 a Giohe-U;9 Olohe-r.. "-
Mek normal C "
2._, (w/udQ 11.5 7.7 i 3.r 3.9 Cnss Emmeelve heriaal e- ^
'.',(W/e40 8.6 5.8 i 2.r 3.0 Mak Deadly (kg/m')
9000 8300 i 700' 7*00 Masal layer EmmesMay 0.35 Vossal Emmselve Hermal C- ^ 2., (w/e4Q 42 32 i 10' 22 J
- shift distribution in Figure 7.8 to the right by approximately 0.3 MW/m' 2
- shift distribution in Figure 7.6 to the left by approximately 0.7 m 3
- alternatively, can use 0.7 x best fit of ULPU results with RPV insulation 4
- broader distribution with generally higher values 5
- not currently treated as an uncertain parameter. Alternatively, can set to extreme value which minimizes margin to CHF
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