ML20198S200

Forwards Open Items Associated w/AP600 SER Section 3.4.1 Water Level (Flood) Design

ML20198S200
Person / Time
Site:	05200003
Issue date:	12/09/1997
From:	Joseph Sebrosky NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9801260106
Download: ML20198S200 (5)

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December 9, 1997 s

Mr. Nicholas J. Liparuto, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanood Technology Division

't;nr.g:m Eiectric Corporation P.o.SoxSss Plumburgh, PA 15230 SUSJECT: OPEN ITEMS ASSOCLATED WITH AP900 SAFETY EVALUATION REPORT (SER)

SECTION 3.4.1

• WATER LEVEL (FLOOD) DESION"

Dear Mr. Uparulo:

The Pierd Systems tranch has provided the subject SER to the projects staff. However, the SER contained some open items. These open Nems have been extracted from the SER and can be found in the enclosure to this letter.

You have requested that portions of the information submitted in the June 1992, application for design cerWfication be exempt from mandatory putdic disclosure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.7g0, that porWon of the submitted informat8on is being withheld from public disclosure pending the staffs final determination. The staff concludes that these follow on questions do not contain those sortions of the information for which exemption is sought However, the staff win withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westing-house the opportunity to verify the staffs conclusions. If, after that time, you do not request that all or portions o the information in the enclosures be withheld from public disclosure in accor-r dance with 10 CFR 2.7g0, this letter will be placed in the Nuclear Regulatory Commission Public Document Room.

if you have any questions regarding this matter, you may contact me at (301) 4151132.

Sincerely, original signed by:

Joseph M. Sobrosky, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003

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Enclosure:

As stated l

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.JEdd0 Eh k See next page DOCUMENT NAME: A:SPLS.,,341.RAI To receive a espy of this dooument, Indicate in the box: "C" = Cyy/a-without attachm "E" = Copy with attachment / enclosure "N" = No copy -

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NAME JMSebrosky se. )LC CCarpenter i TR6dy DATE 12/R/g7 lT 12iB /g7 12/4/g7-OFFICIAL RECORD COPY 4

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- I Mr. Nicholas J. Liparvio Docket No. 52 003 Westinghouse Electric Corporation AP600 l

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Mr. B. A. McIntyre Ms. Cindy L. Haag Advanced Phnt safety & Lloonsing Advanced Plant Safety & Lloonsing l

Westinghouse Electric Corporation Westinghouse Electric Corporation Energy Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230 Enclosure to be distnbuted to the following addressees after the result of the proprietary evaluation is l

roosived from Westinghouse:

Mr. Russ Bell Ms. Lynn Connor Senior Project Manager, Programs DOC Search Associates Nuclear Energy Institute Post Office Box 34 -

1776 l Street, NW Cabm John, MD 20818 l

Suite 300 Washington, DC 20006 3706 Mr. Robert H. Buchholz GE Nuclear Energy Dr. Craig D. Sawyer, Manager 175 Curtner Avenue, MC 781 Advanced Reactor Programs San Jose, CA 95125 OE Nuclear Energy 175 Curtner Avenue, MC 754 Mr. Storting Franks l

San Jose, CA 95125 U.S. Department of Energy r

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Barton Z. Cowan, Esq.

19901 Germantown Road Eckert Seamans Cherin & Mellott Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 1521g Mr. Charles Thompson, Nuclear Engineer r'

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 9

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d plBTRIBUTION: Letter to Mr, Nmholas J. Liparulo dated: December 9, 1997

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Open items Associated SER Section 3.4.1 The staff acknowledges that some of the following issues have been discusted previously on enriier occasions. However, repetition appears necessary given the need for further clarity and the possible incorporation of earlier RAl response text in the AP600 SSAR. Open items follow.

410.381F Discuss the approach taken in the AP600 design to protect regulatory treatment of non safety-related systems (RTNSS) and defense in depth (DID) systems from intomal and extemal floods. (OI 3.4.12) 410.382F Clarify in the standard safety analysis report (SSAR) that the combined license (COL) will identify flood hazards beyond those postulated in the design and will provide protective features for safety-related and applicable RTNSS and DID systems. (Ol 3.4.13) 410.383F Provide information to show that the AP600 design conforms with the guidelines of position C.2 of Regulatory Guide (RG)1.1.02 regarding Technical Specifications (TS) and emergency operating procedure needed to utilize position C.2 of RG 1.59. (013.4.1-4) 410.384F ine response to RAI question 410.202 states that duct penetrations into the CVS and PXS compartments are designed to prevent flooding of these rooms from the maintenance floor. Howis this done? (013.4.15) 410.385F Identify what safety related, RTNSS, and DID systems are in each of the following areas within the auxiliary building: non-radiologically controlled area (NRCA), the mechanical equipment area, the non-Class 1E electrical equipment area, the Class 1E electrical equipment area, radiologically controlled area (RCA).

(OI 3.4.16) 410.386F Are there penetrations through the walls separating the NRCA and the RCA?

(OI 3.4.17) 410.387F Provide a discussion on backflow protection from flouding in buildings adjacent to those housing safety related, RTNSS, and DlD systems. (Ol 3.4.18) 410.388F Discuss where the various sumps pump flood water to, and discuss the backflow protection for the sumps. (013.4.19) 410.389F The response to RAl question 410.202 states that safety related equipment is located in the upper levels (UL) of the vertical pipe chase. Since this pipe chase is also used as a drainage pathway, is the safety-related equipment in the pipe chase vulnerable to damage from water? Also, identify the equipment on Level 2 in the RCA and in the pipe chase. The responses to RAI questions 410.11 and 410.93 discuss how equipment in the NRCA is protected from wetting. Similar discussions should be provided regarding protection from spray wetting for components in containment and in the RCA. (013.4.1 10) l Enclosure l

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410.390F The response to RAl question 410.44 states that some doorways between the auxiliary building and adjacent buildings are double doors and are not watertight.

Flood water from agacent areas is directed away from or is otherwise prevented from entering the auxiliary buildmg. How is this done? (013.4.1 11) 410.391F The response to RAI question 410.44 states that there are no below-grade tunnels connecting the containment and auxiliary building to any other buildings.

What systems route water to the redweste building? In what buildings are these sys' ems housed, and what protection features are in place to protect safety-related, RTNSS and DID systems from flooding from a failure in these systems?

(013.4.1 12) 410.392F Clarify in the SSAR that the protective features (waterproofing, etc.) ccnstitute the

" hardened protection" approach defined in RG 1.59. (OI 3.4.1 13) 410.393F As appropriato, rets,nst s to the following RAls should be incorporated into the SSAR: 410.4, 40.!,, 410.7, 410.30, 410.38, 410.40, 410.44 410.46, 410.50, 410.201,410.202 (OI3.4.1 14) 410.394F Clarify why the AP600 design does not utilize watertight doors for flood protection.

(Ol 3.4.1 15) 410.395F SSAR section 3.4.1.2.2.2 states that the auxiliary building contains RCA and NRCA which are physically separated by 2 and 3 foot structural walls and floor slabs. Explain how the 2 and 3 foot structural walls prevent flooding and/or fire propagation across area boundaries. (013.4.1 16) w

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