ML20151C978: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 6
| page count = 6
| project = TAC:60973, TAC:67767, TAC:67768, TAC:67803
| stage = RAI
}}
}}



Latest revision as of 05:25, 11 December 2021

Forwards Request for Addl Info Re Topical Rept WCAP-10988, COBRA-NC,Analysis for Main Steam Line Break in Ice Condenser Containment. Response Requested within 45 Days from Ltr Date
ML20151C978
Person / Time
Site: Mcguire, Catawba, McGuire, 05000000
Issue date: 04/07/1988
From: Jabbour K
Office of Nuclear Reactor Regulation
To: Tucker H
DUKE POWER CO.
References
IEIN-84-90, TAC-60973, TAC-67767, TAC-67768, TAC-67803, NUDOCS 8804130309
Download: ML20151C978 (6)


Text

_ _ _ _ - -

. April 7,1988 Docket Nos.: 50-413/414 DISTRIBUTION:

and 50-369/370 [DoctetFjJey~ K. Jabbour hkC PDR D. Hood Local PDR E. Jordan Mr. H. B. Tucker, Vice President PDll-3 Reading 0GC-WF Nuclear Production Departnent Catawba Reading J. Partlow Duke Power Company McGuire Reading ACRS(10) 422 South Church Street S. Varga C. Li Charlotte, North Carolina 28242 G. Lainas J. Wermiel M. Rood J. Craig

Dear Mr. Tucker:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON WCAP-10988, HAIN STEAM LINE BREAK IN ICE CONDENSER PLANTS - CATAWBA AND MCGUIRE NUCi. EAR STATIONS, UNITS 1 AND 2 (TACS 60973/67803 and 67767/67768)

Westinghouse Topical Report WCAP-10988, "COBRA-NC, Analysis for a Main Steam-line Break in the Catawba Unit 1 ' Ice Condenser Containment," was submitted to support modification of the LOTIC-3 computer code. The LOTIC-3 code was used by Westinghouse to reanalyze the ice condenser containment thermal response following a main steam line break (M3LB) with superheated steam releases as described in IE Information Notice No. 84-90, "Main Steam Line Break Effect on Environmental Qualification of Equipment." As a part of NRC staff review, Argonne National Laboratory (ANL) is currently performing an independent confirmatory analysis of a MSLB in the ice condenser containment.

Responses to the enclosed request for additional information are requ' 2d in order to allow ANL to complete its confirmatory analysis. '

t The concern regarding containment temperature following superheated steam releases was addressed and identified as an unresolved issue in the Catawba l SER and SSERs 2, 4, 5 and 6. The McGuire plant is also affected due to the design )

j similarity of the ice condenser containments in Catawba and McGuire. '

Your responses to the enclosure are requested within 45 days from the date of this letter. Pleasecontactmeat(301)492-1496, or D. Hood at (301) 492-1442, if you have questions regarding the enclosure or are unable to meet the requested response date.

The reporting and/or recordkeeping requirements contained in this letter affect fewer that 10 respondents; therefore, OMB clearance is not required under P.L.

96 51.

Sincerely, l

Original signed by:

l Kahtan N. Jabbour, Project Manager l$k41$0$$$!O00369 Project Directorate 11-3 p PDR Division of Reactor Projects, I/II Enr.losure:

As stated cc: See next page ./

LA:Q) PM:PUII-3 PM:PDII-3 PD:PDII-3 MM65 {-3 KJabbour:pw DHood Acting PD j/ /88 g/}/88 t r / 7/88 y/7/88

  • l Mr. " a i ckert l Duke e mpany Catawba Nuclear .C' "an CC' A.V. Carr, Esq. North Carolina Q .tric Membership Duke Power Ccapany Corp.

422 South Church Street 3400 Sumner Boulevard i Charlotte, North Carolina 28242 P.O. Box 27306 1 Raleigh, North Carolina 27611

J. Michael McGarry, III, Esq.
Bishop, Liberman, Cook, Purcell Saluda River Electric Cooperative, ,

and Reynolds Inc. -

I 1200 Seventeenth Street, N.W. P.O. 80x 929  :

Wasitington, D. C. 20036 Laurens, South Carolina 29360 i North Carolina MPA-1 Senior Resident inspector i Suite 600 Route 2, Box 179N '

3100 Smoketree Ct. York, South Carolina 29745 P.O. Bcx 29513 l Raleigh, North Carolina 27626-0513 Regional Administrator, Pegion II U.S. Nuclear Regulatory Comission, 1 S. S. Kilborn 101 Marietta Street, hW, Suite 2900 i Area Manager, Mid-South Area Atlanta, Georgia 30323 ESSD Projects Westinghouse Electric Corp. Mr. Heyward G. Shealy, Chief MNC West Tower - Day 239 Bureau of Radiological Health P.O. Box 355 South Carolina Department of Health Pittsburgh, Pennsylvania 15230 and Environmental Control l 2600 Bull Street l County Manager of York County Columbia, South Carolina 29201 1 York County Courthouse  ;

York South Carolina 29745 Karen E. Long j Assistant Attorney General 1 Richard P. Wilson, Esq. N.C. Department of Justice Assistant Attorney General P.O. Box 629 S.C. Attorney General's Office Raleigh, North Carolina 27602 .

P.O. Box 11549 I Columbia, South Carolina 29211 Spence Perry, Esquire I General Counsel Piedmont Municipal Power Agency Federal Emergency Managenent Agency 100 Memorial Drive Room 840 Greer, South Carolina 29651 500 C Street Washington, D. C. 20472 Mr. Michael Hirsch Federal Emergency Management Agency Office of the General Counsel Room 840 500 C Street, S.W.

Washington, D. C. 20472 I Brian P. Cassidy, Regional Counsel Federal Emergency llanagement Agency, l

Region 1 l J. W. McCornach POCH Boston, Massachusetts 02109 1

. . - . . - . . . ._ . - _ _ __ _ =..-.

Mr. H. B. Tucker Duke Power Company McGuire Nuclear Station cc:

Mr. A.V. Carr, Esq. Dr. John it. Barry Duke Power Company Department of Environnental Health P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 County Manager cf Mecklenburg County Mr. Dayne H. Brown, Chief 720 East fourth Street Radiation Protection Branch Charlotte, North Carolina 28202 Division of Facility Services Dcpartment of Human Resources 701 Barbour Drive Mr. Robert Gill Raleigh, North Carolina 27603-2008 Duke Power Company Nuclear Production Department P. O. Box 33189 Charlotte, Ncrth Carolina 28242 J. Michael McGarry, III, Esq.

Bishop, Liberman, Ccok, Purcell and Reynolds 1200 Seventeenth Street, N.W.

Washington, D. C. 20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Commissien Route 4, Box 529 Hunterville, North Carolina 28078 Regional Administrator, Regicn II U.S. Nur. lear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 S. S. Kilborn Area Manager, Mid-South Area ESSD Projects Westinghouse Electric Corporation MHC West Tower - Bay 239 P. O. Box 355 Pi+tsburgh, Pennsylvania 15230

Enclosure REQUEST EOR ADDITIONAL INFORMATION i FOR THE REVIEW OF TOPICAL REPORT WCAP-10988, HAIN STEAM LINE BREAK IN ICE CONDENSER CONTAINMENTS PLANT SYSTEMS BRANCH Argonne National Laboratory (ANL) is performing an independent confirmatory analysis for the staff using the computer code COMMIX to calculate the resulting condition of a main steam line break in ice condenser containments. In WCAP-10988, Westinghouse used two mod 215, COBRA-NC/MODEL 2 and COBRA-NC/Mo di 3, to predict the temperature in the lower compartment of the ice condenser containment. The COBRA-NC/Model 3 uses a finer mesh model. In the preliminary calculatier.s, COMMIX will model the CATAWBA lower compartment with the same mesh sizes used in the COBRA-NC/Model 3 calculation. Provide the following information correspon-ding to COBRA-NC/Model 3 in order to permit ANL to perform the above analysis.

1. The values of or and 40 in generating the computational cells as shown in Fig. 2.10.

Page 15:"The interior of the lower containment is divided into three radini rings and eight sectors." provide the specific values of the radial (ar) and circumferential (AO) dimensions for each cell.

2. Describe how the hydraulic diameters listed in Table 5.2 were calculateo.

Page 75:"Nominal areas and wetted paraceters were normally based on the size of the subchannelt as shown in the plane views for each section.  ;

Area and wetted parameter multipliers were then applied for each axial i elevatfon to account for equipment and structural changes."

Were the actual flow area and the wetter parameter for calculating the hydraulic diameter at each cell obtained from the above statement?

Are the area and wetted parameter multipliers only applicable in the axial direction for each computational cell? If not, there should be three

  • j hydraulic diameters calculated from three sets of flow area and wetted  ;

parameter for a particular cell since the flow is three-dimensional. How

did COBRA-NC resolve this problem?
3. The actual flow area between cells.

In COMMIX, the volume porosity and surface permeability are introduced in the formulation of gova!rning equations. The volume porosity and surface permeability are defined as Volume porosity = Volume occupied by fluid in a control volume Total control surface Surface permeability = Area allowed for fluid flow through a control surface Total control surface The volume porosity for each cell in the COBRA-NC aodel is provided in Table 5.2, while the surface permeability is not available in the report, altnough the area multipliers and flow restricted area have been mentioned on page 75.

9 l

Provide the actual flow area between cells for every cell in Section A, Sec-tion B, and vessel enclosures of Section C of the COBRA-NC/Model 3.

4. The loss coefficients and other drag coefficients used in computing the pressure drop between cells.

1 On page 75:"Flow area restrictions were conservatively modeled  ;

using sharp edge orif t::e loss coefficients, which would reduce the l flow between cells. Nominal flow areas were used for computing velocities."  !

l What is the restricted area between cells? Is it related to the surface '

permeability as described in Item 3? Which correlation was used in calcu-lating the loss coefficient? If the correlation is based on the area i ratio and Reynolds number, what is the other area used besides the orifice area and how was the Reynolds number computed? Provide the loss coefficients

., and othsr drag coefficients used in the COBRA-NC/Model 3.

5. The location and dimension of the 8 foot high pipe tunnel underneath the spent fuel storage area.

On page 5:"An 8 ft. high pipe tunnel runa underneath the spent fuel ctorage region so that there fs flow communication around the full 360*

at this level."

Which cells are c9nnected to the pipe tunnel in the COBRA-NC model?

6. Material properties of heat conductors. l What values of thermal conductivity, heat capacity, and density of the heat conductors described in Table 5.1 are used in the COBRA-NC calcu-1ation?

Is the thermal resistance of paint on concrete and steel surfaces being '. l considered? If yes, what is the thickness of paint used in the calcula-  !

tion and what is the material property? l

7. The tabulated mass. flowrate through the ice f.ondenser door as a function of time at each sector. l The COBRA-NC/Model 3 results show the ice condenser door vapor velocitie2 I in Figs. 6.57 through 6.59 for doors 32a, 326, and 32c. Where are these three doors located? Tabulate the mass flow rate through the doors,
8. The numerical values of the calculated drain mass flowrate and distribu-tion in COBRA-NC/Model 3.

(1) The calculated drain mass flowrate as shown in Figs. 6.61 and 6.62 on page 171 are difficult to read. Provide values of the drain flowrate as a function of time for Model 3.

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(2) How were drain flows distributed for the finer mesh channels in Model 3? Is the average value being used for the three subchannels?

If not, describe how it is used and provide the drain flow droplet l and film injection factors similar to Tables 4.3 through 4.15 for  :

Model 3. l l

Correction or revision of the report.

9.

We have found some errors in the report; for example: l (1) Figure 2.10 and Fig. 5.4 are tlie same. There is no figure that descri5es the grid layout of Section B for the COBRA-NC/Model 2 in the report, while all data listed in Tables 5.2 and 5.3 is for

- Model 2.

(2) On page 162, the physical structure ire the middle figure is different from the other two.

(3) The description of the ice condenser doors in the last paragraph of  :

page 134 is not consistent with Fig. 6.22.  !

l Confirm the accuracy of the values in Tables 4.3 through 4.15 and Tables 5.1 through 5.3. The COMMIX code will use the current information as input.

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