ML20140J014

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Forwards RAI 460.27 Re W AP600 SSAR Rept Section II
ML20140J014
Person / Time
Site: 05200003
Issue date: 05/09/1997
From: Diane Jackson
NRC (Affiliation Not Assigned)
To: Liparulo N
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9705130358
Download: ML20140J014 (3)


Text

s May 9, 1997 1

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

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE AP600 ADVANCED REACTOR DESIGN REGARDING THE SOLID RADI0 ACTIVE WASTE SYSTEM

Dear Mr. Liparulo:

The Nuclear Regulatory Commission staff has determined that it needs addi-tional information in order to continue its review of the Westinghouse AP600 advanced reactor design. The enclosure is RAlf 460.27 regarding standard safety analysis report Section 11.

Because of the design changes in AP600 solid waste system, the Plant Systems Branch needs additional information to re-review the issue of onsite waste storage capacity. This issue was found acceptable in the draft safety evaluation report (DSER). However, the basis for the acceptance in the DSER is not valid in the revised design.

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

Sincerely, original signed by.

Diane T. Jackson, Project Manager Standardization Project Directorate Division of Reactor Program Management j

Office of Nuclear Reactor Regulation Docket No.52-003

Enclosure:

As stated cc w/ enclosure:

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'FICIAL RECORD COPY 9705130358 970509

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

Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 i

Energy Systems Business Unit Cabin John, MD 20818 Box 355 i

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 One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz Suite 350 GE Nuclear Energy Rockville, MD 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

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REQUESTS FOR ADDITIONAL INFORMATION PLANT SYSTEM BRANCH i

WESTINGHOUSE AP600 SSAR SECTION 11 i

i In Section 11.4 of the DSER, the staff reviewed the AP600 solid waste system regarding the amount of shipment and onsite storage capacity and found it acceptable. However, Westinghouse changed the design after the DSER was

' issued, and the onsite storage spaces identified in the DSER do not exist any l

more. The bases for the DSER finding is no longer valid.

In order to re-i review the storage capacity for solid waste, the staff requests the following j

information:

4 1

460.27 In a telecon of April 8,1997, Westinghouse stated that:

in the revised design, two spent resin tanks and nine spent filter tubes in i

the auxiliary building, and a packaged waste storage room in the i

radwaste building are designed for onsite storage.

The remaining i

solid waste is expected to be shipped offsite.

If this is correct, the staff finds the information in Section 11.4 of the SSAR to be incomplete. For example, the number of spent filter tubes and their storage capacity, and the expectation for the COL applicant to provide sufficient shipment capability by a mobile systems are not i

specified in the SSAR.

a.

Revise the SSAR to address the above staff concern.

l b.

Using the data in SSAR Table 11.4-1, Westinghouse is requested i

to demonstrate that the AP600 has sufficient storage capacity to allow time for short-lived radionuclides to decay prior to shipping in accordance with the regulatory guidance in the standard review plan (SRP) Section 11.4, Paragraphs.II.6 l

and III.4, and BTP ETSB 11-3 Position B.III.

c.

1. In SSAR Table 11.4-1, the amount of " expected" generation i

and " expected" shipped solid waste are significantly lower than that of " maximum" generation and " maximum" shipped solid waste.

Clarify whether the designed process and i

storage capacity are based on the " expected" amount or on L

the " maximum" amount.

I If the design storage capacity is based on the expected amount:

2.

explain how the AP600 will handle the waste that is beyond what is expected, and 3.

compare the values given in the SSAR for the volumes and radionuclide content of solid waste to be shipped offsite with data from operating plants of similar size, i

4 f

4 Enclosure 3

4 4

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