ML20140B870

Discusses Potential Critical Path Issues for Design Certification Review for AP600.Forwards List of Specific Fire Zones in Noncompliance w/SECY-90-016

ML20140B870
Person / Time
Site:	05200003
Issue date:	06/03/1997
From:	Slosson M NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
SECY-90-016-C, SECY-90-16-C, NUDOCS 9706060367
Download: ML20140B870 (5)

Text

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• June 3, 1997 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230

SUBJECT:

FIRE PROTECTION POSITIONS RELATED TO THE AP600' REACTOR DESIGN In a letter dated December 6,1996, the Nuclear Regulatory Commission (NRC) sent Westinghouse a list of potential critical path issues for the design certification review for the AP600. One of the issues, Key Issue #12, involves the acceptability of the Westinghouse approach to fire protection.

In its letter dated May 5,1997, the staff issued 5 technical positions on

• this subject. On the basis of its review of the AP600 Standard Safety Analysis Report, the staff has developed an additional technical position on smoke control for the AP600 design. In addition, to clarify Technical Position 2 (which was identified in the May 5,1997 letter), enclosed is a list of specific fire zones in the containment where compliance with SECY-90-016, " Evolutionary Light Water Reactor Certification Issues and the Relationship to Current Regulatory Requirements," January 12, 1990, has not been demonstrated. The staff discussed these matters with Westinghouse during a May 20, 1997, meeting. <

i If the staff develops additional fire protection issues during its review, it will discuss them with Westinghouse and will prepare additional position papers, as needed. If you have any questions regarding this matter, you can contact Thomas Kenyon at (301) 415-1120.

Sincerely, original signed by:  ;

Marylee M. Slosson, Acting Director h ogggg b 00$03 Division of Reactor Program Management A PDR Office of Nuclear Reactor Regulation Docket No.52-003

Enclosure:

As stated

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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 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 Mr. Cindy L. Haag Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager LMR and SBWR Programs Mr. S. M. Modro GE Nuclear Energy Nuclear Systems Analysis Technologies 175 Curtner Avenue, M/C 165 Lockheed Idaho Technologies Company San Jose, CA 95125 Post Office Box 1625 Idaho Falls, ID 83415 Mr. Robert H. Buchholz GE Nuclear Energy '

Mr. Sterling Franks 175 Curtner Avenue, MC-781 U.S. Department of Energy San Jose, CA 95125  ;

NE-50 i 19901 Germantown Road Barton Z. Cowan, Esq.  ;

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

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l Germantown, MD 20874

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!' TECMICAL POSITION ON FIRE PROTECTION i ISSUES RELATED TO THE DESIGN 0F THE  !

} WESTINGH0USE AP600 LIGHT WATER REACTOR i

l~ In its letter dated May 5,1997, the staff issued 5 technical positions on l 4

fire protection for the AP600. On the basis of its review of the AP600

Standard Safety Analysis Report,-the staff has developed the following  ;

additional technical position on smoke control.

' II. Technical Positions (cont.) i t

j' 6. SMOKE CONTROL l

} The fire protection review criteria for the advanced light water reactors  ;

j (ALWRs) provided in SECY-90-016, " Evolutionary Light Water Reactor Certifica- j

tion Issues and the Relationship to Current Regulatory Requirements," Janu- '

! ary 12, 1990, specifies that ALWR designers should ensure that smoke and hot gases do not migrate into other fire areas to the extent that they could i adversely affect safe-shutdown capabilities, including operator actions.

Position C.5.f of Branch Technical Position (BTP) 9.5-1 specifies that: J j (1) the-products of combustion and the means by which they will be removed

from each fire area be established, and that consideration be given to the ,

l installation of automatic suppression systems to limit smoke and heat genera- I j tion; (2) the normal plant ventilation system may be used to vent smoke and )

j gases to an outside area that will not affect safety related areas, if capable  !

and available; (3) separate smoke and heat vents should be provided in areas  !

! where the potential exists for heavy smoke conditions; and (4) stairwells ,

j should be designed to minimize smoke infiltration during a fire. The BTP 1 references NFPA 204 for additional guidance on smoke control. I 1

NFPA 804, " Standard for Fire Protection for Advanced Light Water Reactor Electric Generating Plants," published by the National Fire Protection Association (NFPA), specifies that smoke removal be provided for nuclear safety-related areas of the plant. An exception is provided from the require-

- ment for fixed ventilation systems for the removal of smoke if the plant is provided with complete automatic sprinkler protection. NFPA 804 references NFPA 92A, " Recommended Practice for Smoke Control Systems," and NFPA 204M,

" Guide for Smoke and Heat Venting," for additional information regarding smoke removal.

. The nuclear safety-related areas of the AP600 are the containment / shield building and.the auxiliary building. Appendix 9A of the Standard Safety Analysis Report (SSAR) states that smoke and hot gases are removed from the containment / shield building'(Fire Area 1000-AF-01), mechanical / piping areas (Fire Areas 1201-AF-04, 1201-AF-05, 1201-AF-06, 1250-AF-01), elevator shafts (Fire Areas 1202-AF-02,1204-AF-03,1205-AF-02), and principal areas (1204-AF-01,1220-AF-02) by portable exhaust fans and flexible ductwork. The Enclosure l

)

- -- =. -. - .... - . _ .- -_ - ~-...- --. _ - - - -

i ,

1 4 . t applicant has not specified, in Appendix 9A of the SSAR, the smoke con-i trol method used for the stairwells in the &uxiliary building (Fire Areas 1201-AF-01, 1202-AF-01, 1202-AF-05, 1204-AF-02, 1205-AF-01). The smoke

removal capability for the remainder of the auxiliary buildings fire areas is >

accomplished using the normal radioactive / nonradioactive ventilation systems provide in the fire area.

i The safety-related areas of the AP600 are not provided with complete automatic sprinkler protection as recommended in BTP 9.5-1, and specified in NFPA 804 to

, support the exception for a fixed ventilation system for smoke removal. i Therefore, the AP600 smoke control capability is not in accordance with Position C.5.f(l) of BTP 9.5-1, or with NFPA 804. The use of portable fans

and flexible hoses for smoke removal does not provide reasonable assurance j that smoke and hot gases will not migrate into other fire areas that could ,

I adversely affect safe-shutdown capabilities. Therefore, these areas do not .

i comply with the criteria specified in SECY-90-016 for. smoke and hot gas j migration.

In addition, stairwells can be a path that allow the migration of smoke and hot gases into other fire areas or zones. As discussed above, the applicant has not specified the smoke control method used for the stairwells in the auxiliary building. Therefore, the smoke control method used for the stair-wells in the auxiliary building should be specified by the applicant in accordance with Position C.S.f.(6) of BTP 9.5-1.

The normal ventilation systems used for smoke control in the auxiliary building have not been evaluated by the applicant against the applicable NFPA '

. standards to determine if they are adequate. Therefore, compliance of the  ;

normal ventilation systems used for smoke control in the auxiliary building  :

with the criteria specified in SECY-90-016 and BTP 9.5-1 cannot be determined. l Westinghouse should provide the results of this evaluation. 1

LIST OF ZONES WITH REDUNDANT SAFE SHUTDOWN COMPONENTS THAT HAVE NOT DEMON-STRATED ONE DIVISION WILL REMAIN FREE OF FIRE DAMAGE (Technical Position 2, " Separation of Redundant Divisions")

To clarify Technical Position 2 (that was identified in a May 5,1997 letter),

the following is a list of fire zones in the containment where compliance with SECY-90-016, " Evolutionary Light Water Reactor Certification Issues and the l Relationship to Current Regulatory Requirements," January 12, 1990, has not been demonstrated.

Fire Zone Number Redundant SSC Zones 1100-AF-11105 1100-AF-11024 1100-AF-ll300A Il00-AF-11300B l 1100-AF-11300B 1100-AF-11500 1100-AF-11303 Il00-AF-ll301 i

1100-AF-11303A 1100-AF-11303B l 1100-AF-11500 1100-AF-11300B, 11301, 11302, 11303A/B 1200-AF-12341 1220-AF-12341 Notes:

1 - 1100-AF-11105 - Location of redundant SSCs not specified in Appendix 9A 2 - Drawing 1010-AF-201B - Indicates all 4 divisions in 1100-AF-11105 l 3 - Use of 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> barriers in zones 1100-AF-113008 & 1100-AF-11303A 4 - Il00-AF-Il300A - 1100-AF-ll207 not listed as redundant in Appendix 9A 5 - 1100-AF-11301 - 1100-AF-11303 not listed as redundant in Appendix 9A 6 - 1100-AF-ll300B - ADS in Zones: Il00-AF-11303/8, Core Makeup in Zones: 1100-AF-ll206, 11207 Accumulator in Zones: 1100-AF-11206,11207 Incontainment RWST in Zones: 1100-AF-11206, 11207, 11208 7 - 1200-AF-12341 - All 4 divisions located in this fire zone