ML20057B359

Requests Addl Info in Order to Complete Review of Design Certification Testing for AP600

ML20057B359
Person / Time
Site:	05200003
Issue date:	08/27/1993
From:	Kenyon T Office of Nuclear Reactor Regulation
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9309210237
Download: ML20057B359 (4)

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• August 27, 1993 Docket No.52-003 1

r Mr. Nicholas J. Liparulo Nuclear Safety and Regulatory Activities Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE AP600 As a result of its review of the design certification testing for the AP600, the staff has determined that it needs additional information in order to complete its review. The additional information is needed regarding the Oregon State University (0SU) test facility and its operating procedures (Q952.2-Q952.ll).

Enclosed are the staff's questions.

Please respond to this request within 90 days of the date of receipt of this letter.

You have requested that portions of the information submitted in the June 1992 application for design certification be exempt from mandatory public disclo-sure. 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 submit-

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ted information is being withheld from public disclosure pending the staff's final determination. The staff concludes that this RAI does not contain those

~l portions of the information for which exemption is sought.

However, the 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 disclo-sure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission's Public Document Room.

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'The numbers in parentheses designate the tracking numbers assigned to the questions.

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PDR

l Mr. Nicholas J. Liparulo

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August 27, 1993 This RAI affects nine or fewer respondents, and therefore, is not subject to review by the Office of Management and Budget under P.L.96-511.

If you have any questions regarding this matter, you can contact me at (301) 504-1120.

1 Sincerely, (Original signed by) o Thomas J. Kenyon, Project Manager Standardization Project Directorate Associate Director for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page DISTRIBUTION:

• Central File PDST R/F TMurley/FMiraglia DCrutchfield

• PDR RBorchardt TEssig TKenyon RHasselberg TGody, Jr., EDO JMoore, 15818 MSiemien, 15B18 PShea Alevin, 8E23 MRubin, 8E23 RJones, 8E23 HScott, NLN 353 ACRS (ll) w/o encl.

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(A)SC:PDST:ADAR NAME:

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08/d/93 08/d/93 08d[/93 08/13/93 DATE:

0FFICIAL RECORD COPY:

DDCUMENT NAME: OSU.RAI t

4 Mr. Nicholas J. Liparulo Westinghouse Electric Corporation Docket No.52-003 AP600 cc:

Mr. B. A. McIntyre Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. John C. Butler Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike Suite 350 Rockville, Maryland 20852 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C.

20585 Mr. S. M. Modro EG&G Idaho Inc.

Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.

Room 8002 Washington, D.C.

20503 Mr. Frank A. Ross U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874 l

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e REQUEST FOR ADDITIONAL INFORMATION ON THE WESTINGHOUSE AP600 DESIGN 952.2 Provide drawings and/or design details of the sparger for the automatic depressurization system (ADS) that is submerged in the incontainment refueling water storage (IRWST) tank.

952.3 Are the pipes and components of the facility insulated or heat-traced?

If so, provide design <ietails.

952.4 Is the data provided in Table 5.6, " Scaling Analysis for the OSU AP600 Low Pressure Integral System Test," provided during a December 9, 1992 presentation, still an accurate estimate of the anticipated initial conditions? What procedure will be followed to establish these condi-tions? What would the core power be?

Table 5.6 provided the following data as the starting conditions for a depressurization transient:

Primary Coolant Pressure 400 psia Average Primary Coolant Temperature 440*F Secondary Pressure 350 psia Secondary Steam Temperature 430*F Main Steam PORV Setpoint 440 psia Accumulator Pressure 272.4 psia i

952.5 When will the primary pumps be shut off relative to the time that the break is opened?

952.6 What are the conditions at which the bypass flow from the downcomer to the upper head will be adjusted to be 1% of the total flow? What will the total flow be? What will the system pressure and temperature be?

Will the core heater rods be on, and, if so, at what power?

952.7 It is the staff's understanding that the fluids leaving the primary system will be collected. The liquid will be routed to a sump and the vapor will be measured so that an equivalent mass of liquid can be added to the IRWST. Will there also be a system that pressurizes the IRWST and the outlet of the break and 4th stage ADS?

If so, what i

algorithm will be used to calculate the necessary pressure, and what mechanism will be used to implement the pressure adjustments?

952.8 How will the pressurizer heaters be controlled? What is their power?

Will they ever be on during any proposed transient?

952.9 What is the pressure setting on the safety valves (s) at the top of the pressurizer?

j 952.10 How will the steam generator levels be controlled at steady state initial conditions and during a transient? What will the feedwater temperature be? How will its flow rate be controlled? How will the steam flow be controlled?

952.11 How will the core power be controlled during a transient?

Enclosure