ML20138F129

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Forwards RAI on AP600 Advanced Reactor Design in Ecgb Review Area Re Westinghouse SSAR
ML20138F129
Person / Time
Site: 05200003
Issue date: 05/01/1997
From: Diane Jackson
NRC (Affiliation Not Assigned)
To: Liparulo N
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9705050270
Download: ML20138F129 (3)


Text

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May 1, 1997 f

Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division 1

Westinghouse Electric Corporation P.O. Box 355 i-Pittsburgh, Pennsylvania 15230

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION (RAI) ON THE AP600 ADVANCED REACTOR DESIGN IN THE CIVIL ENGINEERING AND GEOSCIENCES BRANCH (ECGB), REVIEW AREA

Dear Mr. Lilarulo:

The Nuclear Regulatory Commission ECGB staff has determined that it needs additional snformation in order to complete its review of the Westinghouse AP600 advanced reactor design.

Enclosed is RAI #220.106 - 220.110 regarding the passive containment cooling system tank and tank liner.

1 If you have any questions regarding this matter, you may contact me at (301) 415-8548.

Sincerely, I

I original signed by:

Diane T. Jackson, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003

Enclosure:

As stated cc w/ enclosure:

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Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director i

Advanced Plant Safety & Licensing Advanced Reactor Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 Eye Street, N.W.

P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Ms. Cindy L. Haag Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 4

Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager LMR and SBWR Programs Mr. M. D. Beaumont GE Nuclear Energy Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 Westinghouse Electric Corporation San Jose, CA 95125 4

One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz Suite 350 GE Nuclear Energy Rockville, hD 20852 175 Curtner Avenue, MC-781 San Jose, CA 95125 Mr. Sterling Franks U.S. Department of Energy Barton Z. Cowan, Esq.

NE-50 Eckert Seamans Cherin & Mellott 19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear Systems Analysis Technologies PWR Design Certification Lockheed Idaho Technologies Company Electric Power Research Institute Post Office Box 1625 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303 Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 19901 Germantown Road 19901 Germantown Road Germantown, MD 20874 Germantown, MD 20874

REQUESTS FOR ADDITIONAL INFORMATION CIVIL ENGINEERING AND GEOSCIENCES BRANCH WESTINGHOUSE AP600 SSAR From the review of Section 3.8.4 of the AP600 SSAR (up to and including Revision 11), the Civil Engineering and Geosciences Branch identified a number of concerns related to the design of the passive containment cooling system (PCS) tank and tank liner. These concerns are described as follows:

RAI #220.106:

In SSAR Subsection 3.8.4.1.1, Westinghouse states that the conical roof supports the passive containment cooling system (PCS) tank, which is con-structed with a stainless steel liner on reinforced concrete walls. However, there is no description of the tank liner (e.g., configuration of the liner, thickness of the liner, interface between the liner and reinforced concrete walls, collection of leakage past the liner, and figures for design details of the liner). Westinghouse needs to include a description of the tank liner in the SSAR. Additionally, Westinghouse needs to include the configuration of the tank liner and the welding requirements in the SSAR figures.

RAI #220.107:

Westinghouse needs to provide a description of the procedures for the design and analysis of the tank liner in the SSAR.

RAI #220.108:

In SSAR Subsection 3.8.4.4.1, Westinghouse provides a only brief description of the design approach for the PCS tank. Additionally, the ANSYS and GTSTRUDL models were not prov.ided in the SSAR. Westinghouse needs to expand its description of the PCS tank design approach and include a description of the models in the SSAR.

RAI #220.109:

Operating experience with steel-lined water tanks indicate that the likelihood of water leakage cannot be ruled out. Considering a sixty year design life and significant exposure to weather, special provisions for preventing degradation of the reinforced concrete tank structure should be provided in the SSAR including the limitation of tensile stress in the reinforcing bars.

Also, consideration should be given to incorporate the recommendations for the design of reinforced concrete overhead tanks by American Water Works Associa-tion.

Please explain if Westinghouse considered these items and how they were addressed.

If not, explain why Westinghouse believes the items are not necessary.

RAI #220.110:

In Westinghouse's submittal dated March 26, 1997, the fire tank located inside the PCS tank is shown in the markup of SSAR Figure 3.7.2-12.

However, no description of this tank was provided in SSAR Section 3.8.4.

Westinghouse needs to include a description of the fire tank in SSAR Section 3.8.4.

Enclosure