ML20065L278

Requests That Proprietary Presentation Matls from 940328 & 29 Be Withheld (Ref 10CFR2.790)

ML20065L278
Person / Time
Site:	05200003
Issue date:	03/31/1994
From:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Borchardt R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19304B990	List: ML20065L278 NRC-94-4089, Forwards Proprietary Presentation Matls from 940328 & 29 Meeting on AP600 Containment.Encl Withheld,Per 10CFR9.17(a)(4)
References
AW-94-605, NUDOCS 9404200380
Download: ML20065L278 (43)

Text

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Westinghouse Energy Systems Bu L5 Pittsburgh Pennsylvama 15230 0355 Electric Corporation AW-94-605 March 31,1994 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 A'ITENTION: MR. R. W. BORCHARDT APPLICATION FOR WITIIHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

SUBJECT:

PRESENTATION MATERIALS FROM THE MARCH 28 & 29,1994 MEETING ON THE AP600 CONTAINMENT

Dear Mr. Borchardt:

The application for witSholding is submitted by Westinghouse Electric Corporation (" Westinghouse")

pursuant to the provisim f paragraph fb)(1) of Section 2.790 of the Commission's regulations. It contains commercial strategic information proprietary to Westinghouse and customarily held in confidence.

The proprietary material for which withholding is being requested is identified in the proprietary version of the subject report. in conformance with 10CFR Section 2.790, Affidavit AW-94-605 accompanies this application for withholding setting forth the basis on which the identified proprietary informa' tion may be withheld from public disclosure.

Accordingly, it is respectfully requested that the subject information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the -

Commission's regulations.

Correspondence with respect to this application for withholding or the accompanying affidavit should reference AW-94-605 and should be addressed to the undersigned.

Very truly yours,

/

ba/$'/h N. J. Liparulo, Manager Nuclear Safety And Regulatory Activities

/nja ec: Kesin Bohrer NRC 12HS

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940420o380 940331 3 PDR ADOCK 0520 A

COPYRIGilT NOTICE The reports transmitted herewith each bear a Westinghouse ceq,yright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection not withstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copics beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, D.C. and in kwal public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copics made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.

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i PROPRIETARY INFORMATION NOTICE ,

i Transmitted herewith are proprietary and/or non proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant specific review and approval.

In order to conform to the requirements of 10 CFR 2.7'X) of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information hat, been deleted in the non proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) contained within parentheses located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary  ;

or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Section (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR2.790(b)(1).

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AW-94-M)5 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:

ss COUNTY OF ALLEGHENY:

l Before me, the undersigned authority, personally appeared Brian A. McIntyre, who, being by j me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:

f y. - - - - ,

X ,/~ ~ /'l14 , D Brian A. McIntyre, Manager Advanced Plant Safety & Licensing Sworn to and subscribed before me this c[ day of AI.# / .1994 V

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ru) l Notary Public i eerarce; ,

Roso AtW h-ye, N1ry htAc i MonrcW*o flro. A!ied ony Cbsty l My Cendm Evmte Nw 4,IFfM i MMby,fWytvaruAmoa.conof Notws  ;

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AW-94405 (1) I am Manager, Advanced Plant Safety and Licensing, in the Advanced Technology Business Area, of the Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear powcr plant licensing and rulemaking proceedings, ar.d arn authorized to apply for its withholding on behalf of the Westinghouse Energy Systems Business Unit.

(2) I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse application for withholding accompanying this Affidavit.

(3) I have personal knowledge of the criteria and procedures utilized by the Westinghouse Energy Systems Business Unit in designating information as a trade secret, privileged or as confidential commercial or financial information.

(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withhcid.

(i) The information sought to I,e withheld from public disclosure is owned and has been held in confidence by Westinghouse.

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(ii) The information is of a :ype customarily held in confidence by Westinghouse and not l customarily disclosed to the public. Westinghouse has a rational basis for determining  !

the types of information customarily held in confidence by it and, in that connection, I utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required. l J

Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:

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' AW-94-605 (a) The information reveals the distieguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, rnethod, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.

(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.

(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.

(c) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.

(f) It contains patentable ideas, for which patent protection may be desirable.

There are sound policy reasons behind the Westinghouse system which include the following:

(a) The use of such information by Westinghouse gives Westinghouse a <

competitive advantage over its competitors, it is, therefore, withheld from disclosure to protect the Westinghouse competitive position.

1 (b) It is information which is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to j sell products and services involving the use of the information.

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l AW-94-605 (c) Use by our competitor would put Westinghouse at a competitive disadvantage 1

by reducing his expenditure of resources at our expense.

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(d) Each component of proprietary information pertinent to a particulai competitive aduntage is potentially as valuable as the htal competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

(c) Unrestricted disclosure would jeopardize the position of prominence of i Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.

i (f) The Westinghouse capacity to invest corporate assets in research and  !

development depends upon the success in obtaining and maintaining a l competitive advantage.

(iii) He information is being transmitted to the Commission in confidence and, under the provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission.

(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.

1 (v) Enclosed is Letter NTD-NRC-94-4089, March 31,1994, being transmitted by Westinghouse Electric Corporation (E letter and Application for Withholding 1

Proprietary Information from Public Disclosure, N. J. Liparuto (E, to .

Mr. R. W. Borchardt, Office of NRR. The proprietary information as submitted for l use by Westinghouse Electric Corporation is in response to questions concerning the AP600 plant and the associated design certification application and is expected to be applicable in other licensee submittals in response to certain NRC requirements for justification of licensing advanced nucicar power plant designs, anx

AW-94-605 l

l l This information is part of that which will enable Westinghouse to:

(a) Demonstrate the design and safety of the AP600 Passive Safety Systems.

(b) Establish applicable verification testing methods.

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I (c) Design Advanced Nuclear Power Plants that meet NRC requirements.

(d) Establish technical and licensing approaches for the AP6(X) that will ultimately result in a certified design.

(e) Assist customers in obtaining NRC approval for future plants.

Further this information has substantial commercial value as follows:

(a) Westinghouse plans to sell the use of sirnilar infotmation to its customers for purposes of meeting NRC requirements for advanced plant licenses.

(b) Westinghouse can sell support and defense of the technology to its customers in the licensing process. j l

l Public disclosure of this proprietary information is likely to cause substantial harm to

.the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar advanced nuclear power designs and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.

l The development of the technology described in part by the information is the result of 1

applying the results of many years of experience in an intensive Westinghouse effort I

( and the expenditure of a considerable sum of money.

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1 AW-94-605  !

I in order for competitors of Westinghouse to duplicate this information, similar ,

1 technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended for developing analytical methods and receiving NRC approval for those methods.

Further the deponent sayeth not.

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ATI'ACIIMENT 1 N11) NRC 94 4089

+g!

AP600 Containment Meeting Meeting with the NRC March 28 and 29,1994 l

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,- p i; AP600 Containment Meeting March-28 and 29,1994 Agenda introduction R. Orr Purpose of meeting Transmittal of design information to NRC consultants SSAR and RAI status for Section 3.8.2 Containment Design Basis Function D. McDermott Containment Severe Accident Function J. Scobel Containment Design Specification R. Orr ,

Containment Structural Design and analysis T.Ahl Analyses of capacity for severe accidents T.Ahl Seismic Margin R. Orr Information for independent analyses y p ,yw , .-

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WESTINGHOUSE AP600 CONTAINMENT VESSEL ,

CONTAINMENT DESIGN AND ANALYSIS PERFORMED BY CBI i

. CBI CONTAINMsNT CONFIGURATION SKETCHES

. MATERIAL PROPERTIES

. CONTAINMENT SHELL - FREE FIELD AND GROSS STRUCTURAL DISCONTINUITIES ANALYSIS

. LOCAL EFFECTS ANALYSIS AT MAJOR l PENETRATIONS AND ATTACHMENTS l l

CONTAINMENT SHELL - FREE FIELD AND GROSS STRUCTURAL DISCONTINUITIES ANALYSIS

. DESIGN CASE - 45 PSIG at 280 DEGREES F.

. SERVICE LEVEL C CASE at 320 DEGREES F.

. SEVERE ACCIDENT CAPACITY ASSESSMENT at 70 DEGREES F

. STRESS EVALUATION DUE TO REPRESENTATIVE THERMAL GRADIENTS

. BUCKLING ANALYSIS AT SEVERE ACCIDENT PRESSURE

. SEISMIC MODELING 1

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3. DE$1GN OF STRUCTURE 3, COMPONINT1, fQUIPMENT AND $Y8 TIM 8 Reviolon: 1 Effecttve: 01/13/94 Table 3.8.21 Load Combinations and Service Limits l'or Containment Vessel Load combination and servios limM l Load Desctlption Test Design A A C C C D A C I

Dead D x x x x x x x x x x i IJve L x x x x x x x x x x I l

Wind W z SSE E, x x x Tornado W g x i Test preuere Pt I Test temperstars Tg Operating pressure Po x Normal resedom R. x x x x x Normal thennal To x x x x x Design pressere Pa x x x x Esternal pressure (2.5 paid) p, x External preneurs (3.0 peM) T, a Accent theriaa! T, x x x x Aa=8 thermal rextione A, x x x x AccMest pips ruections Yr x ht hnpheeseems Y j x Pipe hopect Tai x Noens:

1. 5=vice lhet levels are per AsME-MI.

2. Whee any loed redeces the edect of otherloads, that load shad be taken as uro, unless k can be demonstrated that abe loed b ahveye pisesed er occurs simulteneously with the eda loads.

3.8 29 1

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STRE SS- STRAI M CURVE ( UMI AXI AL )

Assume elastic - perfectly blashc rnatcrial pro erties.

Ignoring stro.in-hardening is consefeitre..

-3 Yield sl rain, 6y 'l 60000 = 2 0339 x 10 in/in..

E 2.cs . g x l o 6 h

6'y : g-DATA PolNT 60000. . _ _ _

2. 3 C

2.

~

b d

3 E e _

l 0 I C 2.o339eio'3 0 015 strain ; 6 C in/in)

FIC,. 3- 2. : STRESS- STRAIN C.URVE FOR AWALYSIS NOT E .

Effectitre siress a.f dolo. point 3 has been modified by

'BOSORS' program internally in order to obtain a minimum tangent (nodtrlus of 0 001 E : 29 500 >si. (4'eff d d M o.

point 3 uSed in BOSoRS' is 603S2: 60000 + 2q500 [,0 015 -

o 002.o339].) This is normalltj done to Mn rotre the rate of contm.vgence. This 'negu9ible' strain hardsnincy J\\ not huc any significant effect cm the resuns.

SUBJECT OFFICE AEFERENCE NO SOCKLl% CAPAclTY EVALUATIOM 8 nog.-A REVISION q g 337 TASK #3, CBI phase 3 STuoy AP4co, tale sTtMs+1ouse "Q' V7]IED aire 04rE MADESY VERIFIED BY BY oarE oire SHT ,_ fF .__

j f 2/17/91 f./it f u ,

Nated ta USA GO 644 avg 4?

1

r AP600 CONTAINMENT VESSEL 260

• .. .l

,- .y

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240

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s' f s'  :

220 5 E  :

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L E y' V 200 -- "A N A 1 r .

T r I I O 180 --  ;

y 1 .-

-:- SPHI M 160 ~~

---

-- - ST HT M

• F T I 140 --  ;

(,s 120 --

..s- a 100 l l E l l l 15000 -t0000 5000 0 5000 10000 15000 20000 25000 MEMBRANE STRESS . PSI FIGURE 2: CONTAINMENT VESSEL RESPONSE TO INTERNAL DESIGN PRESSURE OF 45 PSIG

- MEMBRANE STRESSES ( SPHI = MERIDIONAL. STHT = CIRCUMFERENTIAL )

SUBJECT O F FIC E aEFEQENCE NO AEviSICN TA S K # 19 Cf 2- 2 , .

@ NOE-A 902.657 V ADE SY N ERi5 i EO BY M ADE BY VE A+EO By 2. $ - { $

A P/o 00 ) W EST) MGH OUSE /2.SE 1')A SHT Oc _

DATE CATE DATE CATE 57;5142- (/2./9 t

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FIGURE 20 MEMBRANE PRINC. STRESS O!F. ALONG MERIDIAN -- Q: SI-S2. 6: SI-S3. X: S2-S3 9026$7 AP600 WESTINGHOUSE. PR: INTERNAL PRESSURE OF 4S PSI 9/19/91 MAXIMA 21718. 18644. -22723. PSI ,

1 SUBJECT OFFICE REFERENCE NO A5rnE LEVEL c PRESSURE O NOE-A REVISION 90%57 1 MA E SY VERIFIED BY MAoE BY VERIFIED BY j-36 TASK # I > CBI PHASE 3 5T001 gjt .rja sNr or-APGoo, WESTINGHOUSE oarE oarE oarE oarE 900/91 Mlu1M

. . . . . . , , . -....e.-

B1!CKLINGLSTElliSS EVALUATION AT THE BOTTOM T. L. (EL. 104' 1 1/2)

THE LOAD COMBINATION. 'D + L SSE' RESULTS INTO MERIDIONAL COMPRESSION AND TANGENTIAL SHEAR. (SET 1: c, = 2.7 KSI AND ig0 = 0.4 KSl; SET 2: og = .1.7 KSI AND T 90 = 1.1 KSI)

BUCKLING EVALUATION IS PERFORMED USING ASME Ill CODE CASE N 284 (PROPOSED REVISION). ALLOWABLES: coa = 5.5 KSI AND T90a = 6.0 KSI.

MAXIMUM VALUE OF THE INTERACTION EQUATION FOR COMBINED ' AXIAL COMPRESSION + SHEAR'IS 0.5 (SET 1 CONTROLS), THE ALLOWABLE VALUE IS 1.0.

IN THE KNUCKLE THE LOAD COMBINATION 'Pd + Ta' = 'Pd' RESULTS INTO MERIDIONAL TENSION AND CIRCUMFERENTIAL COMPRESSION. (DUE TO Pda: c9 = 11.0 KSI AND 00 = -

10.5 KSl; DUE TO Tab: 0 9 = 0.0 AND 00 = 0.1 KSI, NOTE THAT STRESSES DUE TO Ta ARE VERY SMALL)

BUCKLING EVALUATION IS PERFORMED BY BOSOR5 ANALYSIS USING INTERNAL PRESSURE ONLY AND A FACOR OF SAFETY FROM ASME Ill CODE CASE N 284.

THEORETICAL BUCKLING INTERNAL PRESSURE IS 174 PSIG. USING A FACTOR OF SAFTY OF 2.0, THE ALLOWABLE DES!GN PRESSURE IS 87 PSIG. ACTUAL DESIGN PRESSURE IS 45 PSIG.

aDESIGN PRESSURE OF 45 PSIG (INTERNAL).

bACCIDENT THERMAL (SHELL BELOW EL. 132'3,70 F AND SHELL ABOVE EL.

132' 3 AND STIFFENERS, 40*F, AND CRANE GIRDER AT 50 F). ,

SUNECT OFFICE REFERENCENO.

^

STRESS EVALUATION AT THE MAJOR NOE A REVISION 902657 STRUCTURAL DISCONTINUITIES FOR WDE BY VERIFIED BY MADE BY VERIFIED BY sHT OF THE DESIGN LOADS DATE DATE DATE DATE AP600. WESTINGHOUSE m esioccenoon x seooqsoon

, l l

STRESS COMPONENTS AND STRESS INTENSITY EVALUATION AT THE BASE 1 l

(EL.100' 0) l Pd DE6tGN PRESSURE OF 45 PSIG (INTERNAL)

Ta ACCIDENT THERMAL (SHELL BELOW EL. 100' 0,70*F AND SHELL ABOVE EL.100' 0, 280*F)

NOTE: STRESSES DUE TO D, L, AND SSE ARE NOT REPORTED HERE AS THEY ARE NOT EXPECTED TO BE CRITICAL FOR BUCKLING IN COMPARISON WITH THE STRESSES DUE TO Ta.

LOAD LOCATION TYPE 09 a0 10 9

1 6.2 1.9 0 Pd 0 = 0* AND 90' M 10.8 3.3 0 0 27.9 8.4 0 1 67.2 -16.8 0 Ta 0 = 0* AND 90 M 0.3 36.9 0 0 66.7 57.0 0 at on 0 = 0* AND 90 M 10.8 3.3 0 10.8 33a Pd I/O 27.9 8.4 0 27.9 80b M 11.1 33.6 0 44.7 80b,c Pd + 0 = 0* AND 90 Ta i/O 61.0 18.7 0 79.7 80b al.S TIMES Smc FOR 'PL' OR 'PL + Pb'.

b3.0 TIMES Sm1 FOR 'PL + Pb + 0'.

cBUCKLING EVALUATION IS NOT YET COMPLETE.

OFFICE REFERENCE NO.

SUBJECT STRESS EVALUATION AT THE MAJOR A NOE A REV60N 902657 MADE BY VERIFIED BY MADE BY VERIFIED BY STRUCTURAL DISCONTINUITIES FOR SHT OF THE DESIGN LOADS DATE DATE DATE DATE AP600. WESTINGHOUSE ewsswcen ocessa wenn

l

3. OtsleN OF 87RUCTUtts, COMPCNINT5, IQUIPMENT AND 8YSTYMS ReWelon: 1 EWecftve: 01/13/94 ,

Tobis 3.g.2 2 1

Containment Vessel Pressure Capabilities Contab-me EeJuant Pressure Capetd!ky at AanMeet Temperstart Deter =h Severt Acd. Mishnam Spedfled dent Capacitym yi,ye Cyllader 125 psig @ 144 peig (l) l Ellpecidal Head 10d psig @ 146 psig @ gn -p.c b . *.t -

22 foot equipmens haoch 117 pais @ # I'

• 196 psig Q '

16 foot equipment hatch 96 psig @ 161 psig (T)

Perseasel aMocks# >163 peig @) %54 a >300 paq h Tert 4 p . r. i l (1) The beck!!ag espedty of the enipsoidal heed is taken as sarty pettent of the creical buddlag pressure calculated by the 9050R 5 aca linser analyses. Evaliettoms of the other elesness are according to AsbG servics Level C and knclude une of Code Case N284 (7) The estirmated maxhauen pressure espebSiry is based on skumum spedned natstial properties.

(3) The capecides of the personnel alriock art estheated been test results.

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902657: SUCKLING OF TOP HEAD 12/17/91 8 DEFORME0 STRUCTURE LOAD ST8'P 42. LOAD = 1.738E+02 PRESTRESS PSI &

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FIGi. 3-6 : (3050Rs) Pts 30cxuN6 DISPLAfiMENTS umit AT -Rf75.8 PS16.

SusascT OFFICE REFERENCE NO.

O NOE-A BUCKLING.GAPACJTY EVALUATION mevislON 902657 TAfK #3,(.81 PHASE 3 STUDY " "

APG00, lA)ESTINGHOUSE

%'g " "[' 'l "" * " sstDok_

ca rs cara ears car

=. 12/nl41 l s/it/u l Q4 44 A AW %F

i STRESS COMPONENTS AND STRESS INTENSITY EVALUATION AT THE TOP T. L.

(EL. 218'-81/2)

Pd DESIGN PR' ESSURE OF 45 PSIG (INTERNAL)

Ta ACCIDENT THERMAL 'SHELL BELOW EL. 132' 3. 70^F AND SHELL ABOVE EL.132' 3 AND STIFFENERS, 40 F, AND CRANE GIRDER AT 50*F)

ASSUMPTION: STRESSES DUE TO D, L. AND SSE ARE SMALL.

LOAD LOCATION TYPE o,- 00 190 1 11.2 5.8 0 Pd 0 = 0 AND 90 M 10.8 5.6 0 0 10.4 5.5 0 1 0.1 0.2 0 Ta 0 = 0 AND 90* M 0.0 0.1 0 0 0.1 0.1 0 01 ea Pd 0 = 0 AND 90 M 10.8 5.6 0 10.8 33a I/O 11.2 5.8 0 11.2 80b Pd + 0 = 0 AND 90' M 10.8 5.5 0 10.8 80b Ta i/O 11.1 5.6 0 11.1 80b a1.5 TIMES Smc FOR 'PL' OR 'PL + Pb'.

b3.0 TIMES Sm1 FOR 'PL + Pb + O'.

SUELJECT OFFICE REFERENCE NO.

STRESS EVALUATION AT THE MAJOR A NOE A REVEON 902657 STRUCTURAL DISCONTINUITIES FOR MADE BY VERIFIED BY MADE BY VERIFIED BY THE DESIGN LOADS sHT OF AP600, WESTINGHOUSE DATE DATE DATE DATE etosi mcpun ==u mcoma l

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6 6_

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i LOCAL EFFECTS AT MAJOR PENETRATIONS AND l ATTACHMENTS

. CRANE GIRDER

. PERSONNEL AIRLOCK l

. EQUIPMENT HATCHES i

MAIN STEAM AND FEEDWATER PENETRATIONS ROOF CONSTRUCTION SUPPORTS I1 l

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SEISMIC MODELING SEVERE ACCIDENT CASE - DETERMINE CAPACITY .,

LONGHAND CALCULATIONS BASED ON TENSILE STRESSES REACHING YlELD  ;

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NITACllMENT 3 ,

N'll).NRC-94-4089 p

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O A3600 _

s PASSIVE CONTAINMENT COOLING SYSTEM JANUARY 20,1994 DAN MCDERMOTT ON PCSt 2094 AP6 Janust 21,1W4

L AP600 0

PASSIVE CONTAINMENT COOLING SYSTEM DESIGN BASIS Limit peak containment pressure to less than 45 psig design pressure for design basis events (large LOCA, steamline break)

Reduce containment pressure to 1/2 peak pressure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Cooling water supplied for 3 days with no operator action or outside assistance, provisions for simple actions to replenish water supply within 3 i days-As a goal, limit containment pressure to <45 psig for an indefinite time, even if no action is taken to replenish water supply o

DJM PCSt 2094 AP6)anumy 21,1994

O AP600 PASSIVE CONTAINMENT COOLING SYSTEM DESIGN BASIS Automatically actuated Once actuated, operation shall not be dependent on electrical power, continuous operation of mechanical components Meets single failure criteria for design basis e"ents ,

System reliability consistent with plant CMF and SRF criteria OAA PCS12094 M'6 January 2 t.1994

O AP600 PCS - SIMPLIFIED S< ETCH

! DiMDERALIZED

~

PCI

~~ ~~

AIR SYST M Valve Gauery

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CRA!N DRAIM D M PCS12U94 AP6 Jewsy I9. I854

O A3600 PASSIVE CONTAINMENT COOLING SYSTEM SYSTEM FEATURES .

- Containment wetting for evaporative cooling Water storage tank Integrated into the Shield Building 400,000 gallons useable volume Gravity Drain Parallel Fail Open Isolation Valves Leakage Detection Water distribution bucket (30" Diameter)

Water distribution features Two Acceptable Configurations Distribution Arms Weir Water Distributers (Coverage 90% to 35%)

Annulus Drains Long Term makeup water (Beyond 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

USA PC512085 4 AP6 Jewiry70.1994

c l

gl A3600 l i

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@ l PASSIVE CONTAINMENT COOLING SYSTEM WATER DISTRIBUTION Containment dome olan view

/

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L $ .

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s 03 61P Maren 13. t992

O A3600 CONTAINMENT COOLING SCENARIOS Loss of Coolant Accident Steam Line Break Passive Residual Heat Removal Transients

- Negative Pressure Transients l

l DA4 PCSt2094 AP6 January 19.1994 m _ _ _ _ _ _ ___ . _ _ _

& s AP600 CONTAINMENT COOLING SCENARIOS LOSS OF COOLANT ACCIDENT Containment Pressure for DECLG 8

pe S ~_

s 5

2 5 8 ~-

l _

m M

o . , , . .... i . . . . .... i

. . . . . . .;r ......gj,....,,,g3 l rune (sec) l l

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l l

l - _ _ _ _ _ _ _ _ - - - _ - _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _

AP600 i CONTA \ \/IE\~~ COOLING SCENARIOS ,

LOSS OF COOLANT ACCIDENT - TEMPERATURE PROFILES l i

Containment Shell Temperature Profiles for Cold Leg Break j

Dome Spring Line Operating Deckl Time Wet Dry Wet Dry Wet Dry ,

b O

100. I , i O

., 700. I i O l 1300. I I O

l 1900. I O

3100. I O

7600. I i O l 19600. I O

l 31600. I O

86400. I O

l Notes: I w/pbenolic coating inside  ;

I . Inside shell  :

0 - Outside she31 l

l DJM PCS12094 AP6. Matt.n 28,1994 l

O AP600 CONTAINMENT COOLING SCENARIOS STEAM LINE BREAK Containment Pressure,1.388 ft2 DER SLB,30% Power 8

s 1 3

n ? i e

b -

~

? 8 _

• f l Time (sec) l om ns , n,< m >~ , . .. , w l

n y-WESTINGHOUSE PROPRIETARY C. LASS 2 AP600 CONTAINMENT COOLING SCENARIOS PASSIVE RESIDUAL HEAT REMOVAL TRANSIENTS PASSIVE RHR OPERATION Pressure Transient versus Time 25 - - -

m 24 23 s

22 g 21 /

=

g 7 O 20 /

!! /

3 19 s'

$ ,/

A- 18 -

/

s 17 -

/

B E -- E -

M M M 15 8 ' ' ' * -

14 DJA4 FCS12094 AP6 January 19,1994 Time (Seconds)

O AP600 CONTAINMENT COOLING SCENARIOS NEGATIVE PRESSURE TRANSIENTS .

Events Considered PCS actuation IRWST Pumpout Failed Fan Cooler Control Purge System Maloperation Loss of all AC @ Limiting Environmental Conditions

- Environmental Conditions (-40 F/45 mph wind)

Results (hand calculations) <3.0 psid @ 30 minutes Event Termination 1

i OM PCSi2094 AP6 Jaway 21. I994

4 A ~)600 __

CO \ ~~A \ V E N~~ COO _. \ G SC E N A 9 OS CONTAINMENT TEST l\G PROGRAMS CONTAINMENT WATER DISTRIBUTION TESTS OBJECTIVES: CHARACTERIZE WATER DISTRIBUTION FOR RANGE OF FLOWS VARIETY OF DISTRIBUTION MECHANISMS WORST CASE SURFACE DEFECTS ESTABLISHMENT OF WATER DISTRIBUTION DESIGN LARGE SCALE CONTAINMENT COOLING SYSTEM TESTS OBJECTIVES: TO PROVIDE DATA TO VERIFY CONTAINMENT COMPUTER CODES AND MODELS USED TO ASSESS PCS PERFORMANCE OVER RANGE OF VESSEL PRESSURES RANGE OF WATER DISTRIBUTIONS RANGE OF AIR VELOCITIES WIND TUNNEL TESTS OBJECTIVES:

DETERMINE WORST CASE PRESSURE DISTRIGUTION DEVELOPED ACROSS THE AIR BAFFLE DEMONSTRATE INTERACTIONS OF WIND AND BUILDINGS WILL NOT CAUSE A DECREASE IN NATURAL CIRCULATION COOLING INTEGRAL CONTAINMENT COOLING TEST OBJECTIVE: CONFIRM THE OPERATION AND HEAT REMOVAL CAPABILITY OF THE PASSIVE CONTAINMENT COOLING DURING ACCIDENT CONDITIONS DJM PCS12094 AP6 Man.n 25.1994 J