ML20135D961

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Forwards AP600 External Reactor Vessel Cooling RAI for June 1992 Application for Design Certification.Portion of Info Being Withheld from Public Disclosure Pending Staff Final Determination
ML20135D961
Person / Time
Site: 05200003
Issue date: 02/24/1997
From: Joseph Sebrosky
NRC (Affiliation Not Assigned)
To: Liparulo N
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9703060151
Download: ML20135D961 (4)


Text

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February 24, 1997 h

i Mr. Nicholas J. Liparule, Manager Nuclear Safety and Regulatory Analysis.

i Nuclear and Advanced Technology Division Westinghouse' Electric Corporation P.O. Box 355 Pittsburgh, PA-15230

SUBJECT:

FOLLOWON QUESTIONS REGARDING EXTERNAL REACTOR VESSEL' COOLING FOR THE AP600 l-

Dear Mr. Liparulo:

I

~As a result of its review of the June 1992 ap 11 cation for design certifica-1 tion of the AP600, the staff has determine J.tiat it needs additional informa-tion.

Specifically, the enclosure to this letter contains requests for additional information concerning external reactor vessel cooling for the

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AP600.

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You have requested that. portions of the information submitted in the

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' June 1992, application for design certification be exempt from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements of.10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's final determination. The staff concludes that these followon ques-tions do not contain those' portions of the information for which exemption is sought'. However,.thel staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify"the. staff's\\ conclusions.

If, after that time, you do not request that all;or' portions of,the information in the enclosures be withheld.from:public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the'N, RC.Public Document, Room.

,,3 If you-have' any questioris regarding this matter, you may contact me at-(301),415-1132. '

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. Sincerely,

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original signed b Joseph M. Sebrosky,y: Project Manager s

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h. Standardization Project Directorate Division of Reactor Program Management t

u Office of Nuclear Reactor Regulation

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Docket.No.52-003 Enclosures As stated cc w/ enclosure:

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,i See next page 050096 D'STtIBUTION:

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02/3/97 b 02/m/97 "FICIAL REC 0F.D COPY 9703060151 970224 PDR ADOCK 05200003 A

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l Mr. Nicholas J. Liparulo Docket No.52-003 i

Westinghouse Electric Corporation AP600 i

l cc: Mr. B. A. McIntyre Ms. Cindy L. Haag Advanced Plant Safety & Licensing Advanced Plant Safety & Licensing Westinghouse Electric Corporation Westinghouse Electric Corporation i

Energy Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230 Mr. M. D. Beaumont Mr. S. M. Modro Nuclear and Advanced Technology Division Nuclear Systems Analysis Technologies Westinghouse Electric Corporation Lockheed Idaho Technologies Company One Montrose Metro Post Office Box 1625 11921 Rockville Pike Idaho Falls, ID 83415 Suite 350 Rockville, MD 20852 Enclosure to be distributed.to the following addressees after the result of the proprietary evaluation is received from Westinghouse:

Mr. Ronald Simard, Director Ms. Lynn Connor Advanced Reactor Programs DOC-Search Associates Nuclear Energy Institute Post Office Box 34 1776 Eye Street, N.W.

Cabin John, MD 20818 Suite 300 Washington, DC 20006-3706 Mr. Robert H. Buchholz GE Nuclear Energy Mr. James E. Quinn, Projects Manager 175 Curtner Avenue, MC-781 LMR and SBWR Programs San Jose, CA 95125 GE Nuclear Energy 175 Curtner Avenue, M/C 165 Mr. Sterling Franks San Jose, CA 95125 U.S. Department of Energy NE-50 Barton Z. Cowan, Esq.

19901 Germantown Road Eckert Seamans Cherin & Mellott Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP600 Certification Mr. Frank A. Ross NE-50 U.S. Department of Energy, NE-42 19901 Germantown Road Office of LWR Safety and Technology Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874 Mr. Ed Rodwell, Manager PWR Design Certification Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303

AP600 EXTERNAL REACTOR VESSEL C0OLING REQUEST FOR ADDITIONAL INFORNATION 480.946 Please rv ~ > estimates of the margins to failure, in a form similar to Figure 7.10 in DOE /ID a, for the following variations on the base case: (1) input parameters set individuJiy to values specified in column 2 below (14 cases), and (2) input parameters set simultaneously to values specified in column 3 below (1 case).

t Value Individual Sensitivity Cases Combined Case Vessel Wall Melting Temperature (K) 1200 1600 1900 Pool Power Density, MW/m' 1.6' Fission Product Decay Heat in Metal Layer (%)

60 10 U.22 Metallic Layer Thickness (m)

Convection Correlation for Downward Heat Transfer Nu,=0.1453Ra*"

Nu,=0.1453h*"

Convection Correlation for Upward Heat Transfer Nu,=5.884Ra*'"'

Nu,=3.825Ra*'"'

0.9 x ULPU Iower Bound' Ex-Vessel Heat Transfer to a Flooded Cavity Upward and Sideward Heat Transfer Within Metal Layer 0.167 x Globe-Dropkin Globe-Dropkin t

Melt Thermal Conductivity (W/m-K) 11.5 7.7 i 3.8*

3.9 Crust Effective Thermal Conductivity (W/m K) 8.6 5.8 i 2.8*

3.0 7

2 m

C

Value Individual Sensitivity Cases Combined Case Melt Density (kg/m')

9000 8300 i 700 5

7600 Metal Layer Emissivity 0.35 Vessel Effective Thermal Conductivity (W/m-K) 42 32 i 105 22 1

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