ML20212C493

Forwards Request for Addl Info Relative to Open Items in AP600 Design Certification Review

ML20212C493
Person / Time
Site:	05200003
Issue date:	10/20/1997
From:	Scaletti D NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9710290253
Download: ML20212C493 (4)

Text

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• l October 20, 1997?

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Mr. Nicholas"J. Liparulo, Manager -

N J uclear Safety and Regulatory Analysis 5

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t Nuclear and Advanced Technology Division t

i 1 Westinghouse Electric Corporation" P.O. Box 355--

Pittaburgh, PA - 15230 :

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATIVE TO OPEN ITEMS IN THE L AP600 DESIGN CERTIFICATION REVIEW.

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Dear Mr. Liparulo:

As a result of the staff's continuir g review of the'AP600 design certification application, the Plant

. Systems Branch has prepared the draft safety evaluation report (DSER) of Section 9.3 of the AP600 Standard Safety Analysis Report (SSAR). The OSF.R identifies five open items needing resolution by Westinghouse before the staff can complete its review of SSAR Section 9.3 - The open issues are identified in the enclosure.

lf you have any quertions regarding this request, please contact me at (301) 415-1105.-

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S;ncerely,f ioriginal signed by:

Dino C, Scaletti, Project Manager c Standardization Project Directorate Division of Reactor Program Mans;sment Office of Nuclear Reactor Regulaim Docket No.52-003

Enclosure:

As stated

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DOCUMENT NAME: A:\\OPEN9.3 To receive a copy of this document, indicate in the box: -"C" = Copy without

. attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy

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

Mr. B. A. McIntyre Mr. Russ Bel' Advanced Plant Safety & Licensing Senior Project Manager, Programs Westinghoust Electric Corporation Nuclear Energy Institute Energy Systems Business Ur.it 1776 l Street. NW P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006 3706 Wir. Cindy L. Haag -

Advanced Plant Safety & Licensing

- Ms. Lynn Connor Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Sy:;tems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager Advanced Reactor Programs Mr. Sterling Franks GE Nuclear Energy U.S. Department of Energy 175 Curtner Avenue, MC-754 NE 50 San Jose, CA 95125 19901 Germantown Road Germantown, MD 20874 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Frank A. Ross 175 Curtner Avenue, MC-781 U.S. Department of Energy, NE-42 San Jose, CA 95125 Office of LWR Safety and Technology 19g01 Germantown Road Berton Z. Cowan, Esq.

Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Char'es Thompson, Nuclear Engineer Pittsburgh, PA 15219 AP600 Certification NE-50 Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 H!!! view Avenue Palo Alto, CA 94303

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, OPEN ITEMS

CHAPTER 9 L

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(Partial).

i 410.308F:

Section 9.3.1.4 of the SSAR states that during the initial plant testing prior to reactor statiup, safety systems utilizing instrument att will be tested as part of i

the safety system test to verify fail-safe operation of air operated valves upon sedden loss of instrument air or gradual reduction cf air pressure as described in l _

Regulatory Guide (RG) 1.68.3. During a meeting on December 13,1994 and -

telephone conferences on September 18,1995 and November 5,1996, Westinghouse stated in responso to RAI 410.161 that Section 14.2.9.4.10 of the SSAR will be revised f o include.the preoperational testing of the instrument air -

i subsystem in accordance with RG 1.68.3. However, Section 14.2.9.4.10 of the

- SSAR states that " fail-safe testing of safety related air-operated valves will be j_

performed as part of the baseline inservice testing performed as specified in the testing for each system that contains such valves

• rather than specifying testing in accordance with RG 1.68.3. The Chapter 14 secNns, which discuss the l-testing for systems that contain safety-related air operated valves, indicate that testing the proper operation of the valves is described in Section 3.9.6 of the i.

SSAR. However, Section 3.9.6 does not specify testing the fail-safe operation of safety related air opera td valves for sudden loss of instrument air or gradual reduction of air pressura as described in RG 1.68.3. Therefore, Westinghouse needs to revise Chapter 14 of the SSAR accordingly. This is Open item 9.3.12 (OITS No,244).

F 410.309F:

In accordance with NUREG-1275, instrument air quality meets the

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manufacturofs standards for pneumatic equipment supplied as a part of the l

plant. The intake filters for the instrument air subsystem prevent particulates 10 microns and larger from entering the air supply to the compressors. The

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- instrument air receivers function as storage devices for the compressed air,-

Each dryer assembly consists of a coalescing profilter, two. desiccant air dryer j_

towers, and a particulate afterfilter. The coalescing profilter removes oit j

aerosols and moisture droplets. The desiccant air dryers maintain the i

instrument air at a dowpoint of-33.3*C (-28'F) at operating line pressure. The ~

ir:strument air subsystem provides high quality instrument air as specified in the ANSI /ISA S-7.3 standard. However, the reference to " ANSI /ISA 5-7,3"in Section 9.3.1.1.2 of the SSAR is a typographical error that should be changed to

" ANSI /ISA S7.3." in addition, Figure 9.3.1-1 (Sheet 1 of 3) of the SSAR refers to

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air dryer packages 'MG-02A" and "MS-02B" as " Service Air Dryer Packages' but they should be identified as" Instrument Air Dryer Packages.* Westinghouse i

needs to revise the SSAR accordingly. This is Open item 9.3.13.

i 410.310F:

The main steam isol. Con valves (MSIVs) and the main feedwater isolation

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_ valves (MFIVs) are safety-related valves that use compressed nitrogen stored within the valve operators as the motive force to close the valves. Nitrogen f

makeup for these valves (if needed) is provided from portable high-pressure nitrogen bottles using temporary connections on the valves < During a meeting on December 13,1994 and telephone conferences on September 18,1995 and i

November 5,1996, Westinghouse stated in response to RAI 410.243 that Note 21 on Figure 10.3.2-1 of the SSAR specified that the MSIVs and MFIVs are

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pneumatic-hydraulically actuated with a sealed Nitrogen accumulator that -

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o-A e.- provides the stored energy to close the valve. However, Figure 10.3.21 only has Note 21 next to the MSIVs and not next to the MFIVs. Westinghouse needs-to revise Figure 10.3.21 to add Note 21 next to the MFIVs. This is Open item 9.3.2-1 (OITS No,243).

410.311F The WRS collects radictotive, borated, chemical, and detergent liquid wastes at atmospheric pressere from equipment and floor drainage of the radioactive portions of the auxiliary building, the annex building, the radweste building, and the containment building. These radioactive liquid wastes are routed to either the auxiliary building sump, the containment sump, or the reactor coolant drain tank. The contents of the sumps and the drain tank are,aumped to the liquid radweste system (WLS) for processing. The WRS system description, components, and flow diagrams are provided in Sections 9.3.C and 11.2, Tables 9.3.5-1,11.2-2 and 11.2-4, and Figures 9.3.5-1,11.2-1 and 11.2 2 of the SSAR, respectively. However, the reference to " Table 11.2.1-2"in Section 9.3.5.2.2 of the SSAR is a typographical error that should be changed to "T6le 11.2-2." This is Open item 9.3.5-2.

410.312F:

During a meeting on January 25 and 26,1995, Westinghouse stated in response to RAi 410.168 that the third paragraph in Revision 1 of Section 9.3.5,1.1 of the SSAR would be revised to clarify that safety-related systems, structures, or components would not be damaged as a result of equ;pment and floor drain component failure from a Safe Shutdown Earthquake (SSE). However, Westinghouse revised SSAR Section 9.3.5.1.1 by removing the entire paragraph rather than revising the paragraphc As a result, the staff cannot conclude that-the design presented in the SSAR complies with Regulatory Positions C.1 and C.2 of RG 1.29 and that the EFDS complies with the requirements of GDC-2, with respect to the capability to withstand the effects of earthquakes. This is Open item 9.3.5-3 (OITS No. 248).

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