ML20058P256

Requests That Proprietary Presentation Matl from 930920 Meeting on AP600 Low Pressure Integral Sys Tests at Oregon State Univ Be Withheld,Per 10CFR2.790

ML20058P256
Person / Time
Site:	05200003
Issue date:	10/15/1993
From:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Borchardt R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19311B118	List: ET-NRC-93-3993, Forwards Nonproprietary & Proprietary Presentation Matls from 930920 Meeting on AP600 Low Pressure Integral Sys Tests at Oregon State Univ.Proprietary Matl Withheld,Per 10CFR9.7(a)(4) ML20058P256
References
AW-93-535, NUDOCS 9310220186
Download: ML20058P256 (76)

Text

Westingtiouse Energy Systems sa 355 Patsburgn Pennsylvania 15230 0355 Electric Corporation AW-93-535 October 15,1993 Document Cmtrol Desk ,

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: MR. R. W. BORCHARDT APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

SUBJECT:

PRESENTATION MATERIALS FROM THE SEPTEMBER 20,1993 MEETING ON AP600 LOW PRESSURE INTEGRAL SYSTEMS TESTS AT OREGON STATE UNIVERSITY

Dear Mr. Borchardt:

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

pursuant to the provisions of paragraph (b)(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.93-535 accompanics this application for withholding setting forth the basis on which the identified proprietary information 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-93-535 and should be addressed to the undersigned.

Very truly yotrs, W

fY /

N. J. Liparulo Manager Nuclear Safety And Regulatory Activitics __

/nja ec: Kevin Bohrer NRC 12H5 N

9310220186 931015 I' PDR ADOCK 05200001 A PDR Q[] g

COPYRIGIIT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies oi 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 local public document rooms as may be required by NRC regulations if the number of copics submitted is insufficient for this purpose. The NRC is not authorized to make copics for the personal use of members of the public who make use of the NRC public document rooms. Copics made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprie.;ry.

4

@ N4

F 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 2.790 of the Commission's regulations concerning j 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 i information has 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 W

- Westinghouse customarily holds in confidence identified in Section (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying thi: transmittal pursuant to 10 CFR2.790(b)(1).

0330A

'AW-93-535 AFFIDAVIT 4

COMMONWEALTH OF PENNSYLVANIA: ,

ss COUNTY OF ALLEGHENY: 1 i

Before me, the undersigned authority, personally appeared Brian A. McIntyre, who, i6g ty rne 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 avernients of fact set forth -

in this Affidavit are true and correct to the best of his knowledge,information, and belief:

Asf r s v

Brian A. McIntyn:, Manager Advanced Plant F,afety & Licensing Sworn to and subscribed before try this /5~ day of h M .1993 Q.

Notary Publi NotanalSeal R330 Ma% Payne,NA7 Pubic Morexvh Boro. A#pyy ' .

My Cormisman Expree rty 4, t ,

thy,Perrsyh/ania AssoaaDona tag 1297A

AW-93-535 (1) I am Manager, Advanced Plant Safety and Licensing, in the Nuclear and Advanced Technology Divisions, 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 power plant licensing and rulemaking proceedings, and am authoriicd to apply for its withholding on behalf of the Westinghouse Energy Systems Business Unit.

(2) I am making this Affidavit in ecmformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse epplication 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 h. formation.

(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 withheld.

(i) The information sought to be withheld from public disclosure is owned and has been hcid in confidence by Westinghouse.

(ii) The information is of a type customarily held in confidence by Westinghouse and not 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, 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 canstitutes Westinghouse policy and provides the rational basis required.

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

1097A

. . ... .. r

l c 'AW-93-535 ,

I i

(a) The information reveals the distinguishing aspects of a process (or component,- i structure, tool, method, etc.) where prevention of its use by any of  ;

Westinghouse's competitors without license frorn Westinghouse constitutes a j i

competitive economic advantage over other companics.

(b) It consists of supporting data, including test data, relative to a process (or f

component, structure, tool, . method, etc.), the application of which data secures ;

a competitive economic advantage, e.g., by optimization or improved i marketability.

1 (c) Its use by a competitor would reduce his expenditure of resources or improve f

his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.

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

i (c) It reveals aspects of past, present, or future Westinghouse or customer funded  ;

i development plans and programs of potential commercial value to Westinghouse.  ;

~

i (f) 11 contains patentable ideas, for which patent protection may be desirable.

i i

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

i i 5

(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.

(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 sell products and services involving the use of the information. ,

i 1297A j i

^

- - . . - -, .- - - . . ,r,

AW-93-535 (c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.

(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competiton; acquire components of proprietary information, any.

one component may be the kcy to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

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

(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.

(iii) The 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.

(v) Enclosed is 1xtier ET-NRC-93-3993, October 15,1993, being transmitted by Westinghouse Electric Corporation (20 letter and Application for Withholding Proprietary Information from Public Disclosure, N. J. Liparulo (20, to Mr. R. W. Borchardt, Office of NRR. The proprietary information as submitted for 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 nuclear power plant designs.

' 007A

AW-93-535 ,

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.

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

(d) Establish technical and licensing approaches for the AP600 that will ultimately result in a certified design.

(c) 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 similar information 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. l Public disclosure of this proprictary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of  !

i competitors to provide similar advanced nucicar power designs and licensing defense services for comracreial 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, j The development of the technology described in part by the information is the result of 4

applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.

1297A

AW-93-535 i

T In order for competitors of Westinghouse to duplicate this information, similar  :

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 depcment sayeth not.

r t

i

.-l t

I s

6 i

l l

l I

1 1207A 1

\

$.r mu e r 1 \

Westinghouse /NRC Meeting on AP600 Low Pressure 1/4 Height Integral Systems Tests September 20,1993 Oregon State University LaSells Stewart Center, Agricultural Science Room

1. Welcome J. N. Reyes, Jr. 8:15 (:10)

2. Introd uction/ Background /Obj ectiv es E. J. Piplica 8:25 (:15)

3. OSU Facility Design Update 8:40 (1:30)

- Final Design L K.Lau

- Break / Separator System J. T. Groome DAS/ Control Room J. T. Groome BREAK 10:10 (:20)

4. OSU Instrumentation Design J. T. Groome 10:30 (1:30)

- Introduction L. E. Hochreiter

- Walk Through Design and Logic J. T. Groome LUNCH (Valley Footbal Center) 12:00 (1:00)

5. Facility Tour OSU/_W 1:00 (1:30)

BREAK (return to meetins room) 2:30 (:15)

6. OSU Scaling Analysis J. N. Reyes, Jr. 2:45 (1:30)

- Brief Review of Chapters 1-4 i Depressurization Scaling, Chapter S ,

- CMT, Accumulator, IRWST, Chapter 6

- Long Term Cooling, Chapter 7

- Scaling Distortions

7. Test Matrix L E. Hochreiter 4:15 (:30)

8. Schedule E. J. Piplica 4:45 (:15)

9. Adjourn 5:00

e.

ti sommt s t

i WELCOME AND INTRODUCTION  !

EJ. Piplica, Manager -

AP600 Test Ingineering.

)

l l

I t

?

- - - -----_.J

7,.

't v

1 :

1 IlNTRODUCTION t 1

1

Background:

Information j 5

Objectives of OSU Program i 1

i i

Purpose / Objectives of this Meeting 1

l 1

1 l 1

i

fi BACKGROUND INFORMATION Westinghouse visited OSU in 1990 to investigate the possibility of performing long-term cooling tests in a transparent vessel.

Westinghouse /OSU/PGE agreed to a program that would cover both AP600 and Trojan designs.

Westinghouse instructed OSU to perform scaling studies for 1/4,1/6,1/8 height scale and decided on 1/4 height scale.

In August 1991 the facility was changed from a transparent glass / quartz facility to stainless steel, because of safety, and the desirability to increase the design pressure of the facility.

I The current design allows us to initiate transients from )

approximate 400 psia  !

2

\

1 OBJECTIVES OF OSU PROGRAM

• Simulate gravity injection and natural convection in the i small break and long-term cooling mode Provide data on the passive safety system performance Provide data to characterize the cooling flow paths and behavior l 1

Provide data to be used to develop and validate computational methods for analyzing small break /LOCA/long-term cooling conditions k

OBJECTIVES OF OSU PROGRAMfcontinued)

To meet the objectives of the OSU program, the OSU test facility incorporates:

• All RCS, PXS, and NSS components modeled according to the scaling analysis to minimize geometric atypicalities All interconnecting piping and pipe routing to more accurately represent form losses A unique break and ADS measurement system to determine mass and energy releases Extensive instrumentation (~750 channels) to provide the data needed to valid computational models Feedback on the overall facility design from the staff, the ACRS consultants and sub-committee, and the EPRI u'ni representatives w

OBJECTIVES OF OSU PROGRAM (continued) )

Changes made to the OSU program based on feedback from the staff and others:

Broadened scaling report, made it more comprehensive, addressed atypicalities l

Increased OSU model pressure from 200 psia to 400 psia and temperature to 450 F to accommodate broader operating range to address NRC questions

• Added non-safety system to test; CVS, SFW, NRHR Added ability to simulate containment backpressure l

• Added more AP cells in vessel to address 2D/3D effects in '

downcomer l

• Added extra instrumentation in PRHR to provide additional data in C-tube design, and performance

• Comments on the break configuration were factored into the break design for OSU S

o 2

PURPOSE OF MEETING Purpose of this meeting is to: .

Present the final scaling analysis for the facility 1

Provide a test facility design update and status, particularly for the break system 6-Provide an updated instrumentation list and the drawings detailing instrumentation locations i

i Provide an updated test matrix which has been .

modified to include NRC comments I i

1 Provide response to NRC/INEL questions on OSU

\

6

_=. . - . . -

i 1

OSU FACILITY DESIGN. UPDATE :

~ .

54 d

4 1

u

~

'- L1 Lau, Westing,houseW;4~g - , w ,

an. . . a c,,4, .

.. s

'lY'. v e

T. .Ws #n ,1 ;u} ./,",

.,[. 0 5

. . . m ._7.'

2J.T. Groome,TOSUMr , s, .

&.a. - 7 .V+ , j+gmn.~ 'i s,'

f

.#j', *3 4> - :

1. p

[ [ .1 '/ ,

- 'ze  ?

x s

.' ,4 , -

,7. :., '

i

' , , ;$?

. g .} ,

' ylf.:f.4 t A

7;l t.

y,;,

TAg

' J 4' jl' J , {.' 's '

s. . ..;..

.,}?

! jh F, 6

'.c. e, e 4; j:p- . #

.y

~.y,. ,1: a ' +t>-r, ,t.3;4; g>  ::- s + ,

,;.' ' ^ s 'g 4 .,..,m , , ,

g

_.T. t.*_ ..

- - t , > .

'1 , e# _s.

' ' 'M s  % -

B f, ,.4-.

5 - , s 4%.

t; . %' .' i

>.w ,s g y ( ,-

y,/ M _ y , ,

n'.=

. "h. ,",b 1

% A 'g. E

$.+

[g [. , J '. . y" . . -

2 .

, .- #m ,. A ' y 77 -. w n?_.

.N.,,. MIb f

N! 5 1 ,.'4 $:

+

~ c. . . ,

a U . u ,s;9<# . s,.'.?, h%.-(l e.,.,-,. . . ,

,. V .. s a i

g 4..

p s n y g

i

1. . $.1f" k' s r 1.> ]c }. f' s- g s. f* r s * '1

<a

,,y. J * ** >

irQ j g .. g r  ;

.-g #.

wy

- s +a in.W- d ',

3. :.. .

y O I

h s'

. , . 3,5 J 4 f

'f ^444 Y 'r -

ay Y

~ i ( <-

s , s

, ,, s.

~

,. V. J fi ev "y;0x; .

~

. ;3.

./ : %. > .O. I, N . . 7-c,t

• • m.y$O ~ "

y i

+s. s .,

[

_'h . g N 'h I '

, y f d. ' , - +-.' a

..s'.

. f

'g ~ , s. Vf.&F=,h ,. I ,,'?'.') ) ,.

l .v' .

i , , ,~>.; . n v.  :,,' ) ? i*

• p > [s 4--

i s.. ., .. . k.s. ,? .

4

• t--  :..

y f 4 * *

'# .(j . s ' D '

x.*,.'

s ,

y , 3 4

+

4 1 > ,

i U t

OREGON STATE UNIVERSITY (OSU)

LOW PRESSURE INTEGRAL SYSTEMS TEST 4

Design Test Pressure is 400 psia and 450 F 1/4 Linear Scale Sizes are determined by scaling analysis performed by OSU and based on H2TS (NUREG/CR-5809)

Major Components:

Simulated reactor vessel and intemals .

2 simulated loops each with 2 cold legs, I hot ,

leg, and 1 SG Simulated pressurizer and associated lines ,

2 simulated CMTs and 2 simulated accumulators with associated lines Simulated IRWST with associated lines and a sparger a

f

f OREGON STATE UNIVERSITY (OSU)

LOW PRESSURE INTEGRAL SYSTEMS TEST (continued)

Simulated containment sump and the normally  :

non-flooded compartments and associated lines Simulated ADS 1-4 stages Simulated DVI lines and pressure balance lines 1 simulated PRHR Hx and associated loop Simulated RNS RHR pump and lines from IRWST to reactor vessel 1 Simulated CVS makeup pump and line to SG channel head 4 simulated RCPs '

48 heater rods simulating approximately 2%

decay heat i

Simulated passive containment cooling condensate return process a

b OREGON STATE UNIVERSITY (OSU)

LOW PRESSURE INTEGRAL SYSTEMS TEST a

(continued)

Simulation Capability of Test Model Simulated CMT injection Simulated accumulator injection Simulated IRWST injection Simulated sump injection at containment pressure in long-term cooling mode .

Simulated ADS valves and operations Simulated PRHR Hx operations .

Break simulation at hot leg, cold leg, CMT-cold leg pressure balance lines, CMT-pressurizer pressure balance line and DVI injection line.

Long-term cooling, post-LOCA simulation 4

1

i 4-OREGON STATE UNIVERSITY (OSU)

LOW PRESSURE INTEGRAL SYSTEMS TEST-(continued)

Instrumentation - Over 750 Channels Over 118 DP and level cells Over 380 thermocouples for fluid temperature, component wall temperature measurement Over 50 heat flux metes for c'omponent or pipe wall heat loss measurement Over 35 pressure transducers for absolute pressure measurements and pressure monitoring 4 separators for ADS and break flow-measurement Over 60 flow meters such as magnetic flow meter, turbine flow meter, and flow orifice Over 12 OSU/ Westinghouse developed heated '

thermocouples for fluid phase change detection

F i

i 4

i

-h Material proprietary to Westinghouse Electric Corporation I provided under separate cover. -[ >

f f

I Page(s) 6, b  ;

L i

b t

t E

t 4

i E

i

?

i.

i j

O

- - + = = . _ . - . . . , _

"A

/. .b "g

. la

. EU'f

\

/  :

/\ .

lW fs ,

s s t s .,  ;

/,' ' ,

g/ jxy /

J p; ,~Nv// \ -

- i  ;

\ m

.g paw maa

~

l V /

l l

i 7 ,

. .. . . . . . ~ . .. .- - . .

i

.. l i

Material proprietary to Westinghouse Electric Corporation provided under separate cover, i Page(s) 3 - lZ i

k I

t b

s i

D

-h f

J t

~

1 OREGON STATE UNIVERSITY (OSU)

LOW PRESSURE INTEGRAL SYSTEMS TEST (continued) .

Facility Construction Update -- Almost completed All major supporting structures installed Primary loop installed includes: Reactor vessel / internals Hot legs and cold legs and RCPs Steam generators Pressurizer and surge line and spray line DVI injection lines IRWST and associated injection line installed CMTs and CMT injection lines installed ACCs and injection lines installed Primary sump tank and secondary sump tanks installed Sump recirculation lines approximately 98% installed Fill and drain system installed Normal RH pump and associated lines installed I3

f 9

OREGON STATE UNIVERSITY (OSU) i LOW PRESSURE INTEGRAL SYSTEMS TEST (continued)

CVS makeup pump and steam generator feed pump  !

installed PZR to CMT pressure balance lines to be fabricated 4

CMT to cold leg balance lines installed, except ,

connection at top of CMTs '

ADS 1-3 lines from PZR up to and including ADS 1-3 '

separator installed Two ADS 4 separators installed, connecting lines to be ,

installed with the break and ADS flow measurement system ,

i - Sparger fabrication complete and installation in progress  :

I

OREGON STATE UNIVERSITY (OSU)  :

LOW PRESSURE INTEGRAL SYSTEMS TEST (continued)  ;

Control Room and DAS Construction ' Update ,

- Control panel completed 60% field instruments loaded in the control panel  :

- 90 % instrument wiring to hand switches, PLC controllers, etc., completed .

90% wiring from operating panel to DAS system completed >

50% wiring from field instruments to DAS panel completed Outstanding Issues j

• Break and ADS flow measurement system design

- CMT top end steam distributor design

- Order instrumentation for ' break and ADS flow measurement system i

IS

l 1

BREAK & ADS FLOW MEASUREMENT l SYSTEM (BAMS)

DESIGNED TO:

1 SEPARATE 2 PHASE FLOW INTO STEAM AND LIQUID FOR DIRECT MEASUREMENT SIMULATE CONTAINMENT PRESSURE INCREASE OVER TIME PROVIDE FOR HEATED CONDENSATE  :

RETURN TO IRWST AND PRIMARY SUMP REDUNDANT / CONFIRMATORY STEAM FLOW MEASUREMENT ALL STEAM PIPING AND MOISTURE SEPARATORS WILL BE HEATED  ;

i ONE ADS 4 SEPARATOR WILL BE USED FOR  :

DOUBLE-ENDED BREAKS 4

6 L

4 16

A

!~

Material proprietary to Westinghouse Electric Cogoration provided under separate cover.

Page(s) I 7, lg i i

8 L

t i

5 5

B i

i

+ ( ., k. p

.r S

r>

T A

-.OSU;INSTRUMENTATIONLDESIGNC - - # .

<. , ~

,E t &

yy a ,y'a m.4 .*2 ,

, , ,Jg u y k g 1 e?

$1 .f L- 'l '

+(

..c<' c.s;%' w P -

q u 7. -

.. l : <i;4 s -vf,.g y -hw Y h',,'*} 4*

ni g . g+, ;P 4>

• y, yp'. :; q;gpl".

k --

..  % ll # f 'P c.--  !

n"':

',? - f?w" br\ ' E ,-$pgE'd' Q YM

-je .L',+

. ~ yfu ' 1 ~ .:g, r , 9 M. u, n

,l. ' 3 _

a. t -

, _ .g; g.. s-k;  : *^

..,

• ws , ,' ,e-Qf to Fsf

.o

[  ;,. + ,,t *l' i,q,j s \';,, , ~

~ ?, }' g' '. ; ua 1

• _ ,

i W _ /' ,i

, ;.g

• A Y,hi&Y*lhT %f.

• W Q.E A%f5 x

?, h Y h,:,} $ k; &$b,YS.

kh . h 4eRJGyh;A*ih h hj$f "5f M,,,dM_? $kN@BlM0%@hlM:A.L, broofiieg~OSUpdi?!@hN a&,f k[. n f

-- . ~ypy ij w%dy#ng y,,

unema, n 3 I 4 n

,R

+ mwnFgjegImEQHuchtsiter}W,qg@g,m wp w ag mmsa ,

a s'.

ruv A M_$$#

,,- Y '

1. ,s_ _

4

.m y y p6 W W T N p ?d fi$b M ~ S d xwg p g, i@g;s ym. 4 ~w -g su m, m m%.4}i

~ w; -[ vg.hlf k n*,,,

+ T ~; *yb :: kh]wA g; e

.' Y' g;p9 7 44..;u, 4 +. t &esn;{

jf yp .4% ; ,m.m,yyy 4

kkk{l$n$$:W:.Q.U,%e,.,f

.dw swli{;1 5n m gg y.f , n 'm %

5f)s.

Q hglch um s e p">

(

a dMN.' f

• j c p mh5 Ag&f%$k&waa#WGWf&an a

R2 ras $

nag 9yt N2 ~. +A5m r cc3M Ag,NWe " wsWMM wht r W cWh  % Tb @& ,

>, '"myy%.

t}**e w? -Q?d Q T * * $y$gw h &ng;<y$]g N dt N8 v eW P MOW $

= m & w&wQA5%Ol$p$p

-+ m:% }. .g vw m: . p %q m

.4a. 4r h4 d gne yp ," e,.

p .g.a%fy; M QQy f[. :: gu' J4 yppv.p- ,pugo a p-?p w n n p ~;p f n+ Q f;y p i& W

~;y; u n,, vm- Q~ p n p.. y .g,eu 4,. .,

p; 4 iA . . . ,>+'

s.g l c an

&g in h '.9 ww

-Q t. yg e - ~.; h }l[ i Akt%,: 4M edff%Q 15lq%gS&ymp

- 3 ;,

'Nh y W .

n?1 Ngg,7 '

4.gjk@gl4f'Mg%y;,4 j BA$yyh}%gkW*%

R ;M

-. ug g, w v vgggby ~. g m%

wa yk_,~

~'

h '

~ -

c s n.wm - '

, o w. ~ .

, f . .

'In m):J:,K:b%a#

Q : 5f. nz,(4.M > f;y h n ,y.Qnjy wmc ',

+ .

' l ~ ~ *. -j<.4 'k

. s . L gm e p

' g% * %w -.,Q{ 4.,

..y

. :rt n

~} %u ,A 2

5'

+4 y g .g % Ab; A3,/ (~ ,

~- ,

&.;a 7

;2fr*yd f%yf y ]-

s- ,

t .-4 &

s s

L 9

6

INSTRUMENTATION PLAN System wide treatment mass / energy balance can be achieved Individual component mass / energy balances can be directly measured or calculated from the data Rod bundle heat transfer measured Accumulator, CMT, IRWST, Sump flows are measured B

PRHR flow measured when single-phase .

Balance line flow measured when single-phase liquid or single-phase steam PRHR heat transfer measured l

l

/

4 1

Steam generator steam / feed flows measured Steam generator heat transfer measured All break steam flows, break liquid flows measured All ADS steam flows, ADS single-phase liquid flows

~

measured CMT heat transfer, (wall, liquid) measured IRWST pool heat transfer .

measured System heat loss measured Stratified flow regimes can be obtained in hot / cold legs and pressurizer surge line

I PHILOSOPHY

- Use conventional, more reliable, instrumentation, arranged to maximize knowledge Supply redundant measurement when possible Design instrumentation to obtain system wide, and where possible, component mass / energy balances Control process instrumentation separated from data acquisition system Instrumentation was designed with-computer code validation in mind l

3

OSU APEX INSTRUMENTATION l OVER 750 INSTRUMENTS MEASURING FLOW, ,

DIFFERENTIAL PRESS DROPS, LEVEL, HEAT ,

FLUX, PHASE, POWER, AND TEMPERATURE-118 DIFFERENTIAL PRESSURE DETECTORS 33 PRESSURE DETECTORS .

20 MAGNETIC FLOW METERS 5 TURBINE FLOW METERS

^

6 VORTEX FLOW METERS ,

a 6 ; HEATED T/C FLOW METERS 4 -

3 TRUE RMS POWER METERS 1

12 LOAD CELLS .  ;

12 OSU/WESTINGHDUSE DESIGNED HEATED PHASE SWITCHES -

i 51 HEAT FLUX METERS -

424 THERMOCOUPLES BREAK AND ADS FLOW MEASUREMENT SYSTEM INSTRUMENTATION BEING DESIGN l

1

i i

r l

Material proprietary to Westinghouse Electric Corporation  :

provided under separate cover.

Page(s) 6- Elp i

9 t

f k

b f

f

~

t

Scaling Analysis for the OSU AP600 (APEX) Low Pressure Integral System Test .

4 Jos6 N: Reyes, Jr.

Department of Nuclear Engineering Oregon State University e I

- r - , , w-, - - . . , - - , . -

, + - . --,

OSU/AP600 (APEX) Scaling Analysis General Program Objectives and Scaling Objectives General Scaling Methodology H2TS Analysis Method Chapter 4: Closed Loop Natural Circulation Scaling Analysis Chapter 5: Depressurization Scaling Analysis Chapter 6: Venting, Draining, and Injection Scaling Analysis Chapter 7: LCS Recirculation Cooling Scaling Analysis Chapter 8: Summary of Results, and Critical Attributes i OSU NUCLEAR ENGINEERING

'~

GENERAL PROGRAM OBJECTIVES t

Design, construct and operate a 1/4 length scale test facility to examine AP600 integral system behavior, gravity driven injection and natural convection, long term cooling.

l l . Obtain experimental data to assess the computational methods that will be used to analyze the core cooling capability of the AP600.

2 OSU NUCLEAR ENGINEERING

SCALING OBJECTIVES A. Obtain the similarity groups that should be preserved between the test facility and the full-scale prototype, B. Establish priorities for preserving similarity groups, C. Assure that important processes have been identified and addressed, D. Provide specifications for test facility design, and E. Quantify biases due to scaling distortions.

3 OSU NUCLEAR ENGINEERING

i!

i Material proprietary to Westinghouse Electric Corporation provided under separate cover.

I Page(s) 4 I s

r

?

9 i

i

')

?

4 t

p

_ - _ _ . _ _ _ _ _____ _ ______ _ _ . _ _ _ _ _ . _ _ , - - , - - - --v- v - -

1

HIERARCHICAL TWO-TIERED SCALING ANALYSIS METHOD

. Developed by USNRC

- Documented in NUREG/CR-5809

- Comprehensive scaling methodology

- Ishii-Kataoka similarity criteria can be developed using H2TS method .

13 OSU NUCLEAR ENGINEERING

The basic objective of the H2TS method is to develop sets ofL characteristic time ratios for the transfer processes of interest.

. Control volume balance equation for constituent "k" dVg$k

= A [Qk%kl EjkmA km

. dt 1

where A [Qk%kl = [Q k%k lin - EQ k%k lout (1.2) 4 In equation (1.1) the $k term represents the conserved property; $k = p, pu, or pe (mass momentum or energy per unit volume), Vk. is the control volume, Qk i s the volumetric

-14 OSU NUCLEAR ENGINEERING 1

~~^

flow rate, jkm is the flux of property I'k t ransferred from l constituent "k" to "m" across the transfer area Akm-

- Dimensionless initial conditions and boundary conditions Vk + t#k Qk V+=

k ' I 'k k '

V k,0 $k,0 'Q+ = Ok0 ,

(1.3)

.+ jkm + A km

~

3km '

km " g jkm,0 km,0 Substituting these groups into equation (1.1). yields:

+ _ .

dV+% kk +

Vk,0$k,0 Qk,0$k,0 A Qk+I'k dt _

(1j)

( ) .+

I ()km,0A km.0;' JkmA k +m 15 OSU NUCLEAR ENGINEERING

Dividing both sides of this equation by Qk,0 "k,0 yields:

++

Tk dt

=A Oukk I ndkmAi gm where the. residence time of constituent "k" is Vk,0 T (1.6) k = O k,0.

and the characteristic time ratio for a transfer process between constituents "k" and "m" is given by:

_ jkm,0A km,0 (1.7)

O k,0 "k,0 16 OSU NUCLEAR ENGINEERING

CHAPTER 4, CLOSED LOOP NATURAL CIRCULATION-SCALING ANALYSIS .

t

- Rationale for selection of length scale and diameter scale

- Phenomena examined: '

l Single-phase natural circulation ,

Two-phase natural circulation-Core heat transfer Flow regime transitions Critical heat flux L

- Parameters scaled l -

Time Length Primary system volume

. Core geometry, flow area, length, power. .

Hot leg diameter, flow area, length, power Cold leg diameter, length .and. geometry Pressurizer surge line diameter, length and geometry All components relative elevations-17 OSU NUCLEAR ENGINEERING

l t

Chapter 4 Scaling Results

. Ishii-Kataoka Scaling Ratios were obtained using H2TS methodology.

'I

• Analysis revealed the importance of satisfying the two-phase

scaling criteria as a " set" in order to achieve properly scaled l loop flow rates.

i

- When fluid property similitude exists, the core II groups are unity.

18 OSU NUCLEAR ENGINEERING

_ _ _ = _ _ _ _ _ - - - _ _ _

_ . ~. -.. .. . . . - . . . - . . . . - . . - -. . , .- _ . , -. . . - . r.

Chapter 4 Additions

• Include section on single-phase forced and mixed. convection  :

heat transfer.

For the AP600 cases of interest:

G rL>>l 2

Reg This indicates free-convection turbulent flow along a heated l

vertical surface (Chen,1986) l i

l' 39 OSU NUCLEAR ENGINEERING -

t L

l- ..

r . .-

b.

However, using the criterion of Metais and Eckert,1964 for flow inside vertical tubes, GrD Pr L/D versus Reo , indicates 4

that forced convection turbulent flow behavior can be expected for portions of the transients.

e

" . Effect of heat transfer regime during single-phase natural .

circulation transients is not significant as long as core power ,

is being effectively removed.

[

L

- Use additional CHF correlations to examine HCHF distortions.

l 1

( :.-

l'

[' 20 OSU NUCLEAR ENGINEERING e 9W - =' e- th m 'euEd*FM* *w s"urrii-lua k' =4W'W~"%'*-* M 9 T4 h *% 1W+='%.' 1 'r e- ^#-*'e w--" d-wh*'er M = w % ft'-eg4 y*W*" ^^T'* s dM 4 t-' 7 m M +t'M~kb 93 - 9er 4'@8- *FY"t'4- 'M r 7 +4'A r- A ' ' ' 'tuJ$d'K:15'-bc-wy-e-6

CHAPTER 5, DEPRESSURIZATION SCALING ANALYSIS-i l'

l - Phenomena examined:

L System depressurization rate L

Fluid property scaling Critical flow Core decay power Components stored. energy Steam generator dryout Pressurizer stored energy PRHR mass flow rate  ;

• Parameters scaled:

Pressure setpoints Core power ADS / break sizes Steam generator tube size, number, and shell side liquid level PRHR tube size and number 21 OSU NUCLEAR ENGINEERING

i

-r llo i i

l 1

I i

I L

f f

Material proprietary to Westinghouse Electric Corporation provided under separate cover.  !

i i

I i

Page(s) 22~Z3 f

a 1

?

t t

i f

5 I

b 9

P 2

6 b

l I

i

?

1 Table 5.2 System Level Scaling Analysis:

Control Volume Balance Equations for System Depressurization (with Simplifying Assumptions)

System Fluid Mass:

d t g'P,y,V,ys) = Lh g -Lig (5.10)

System Fluid Energy:

hp,y,b,y,)= d Vsys - E'* ""'

Solid Structure Energy:

I d (T, -Tunb)

-(p,V,C,,T,) = -%f U, - Tr) A,i - (5.5) dt R$ ,,

24 OSU NUCLEAR ENGINEERING-

Material proprietary to Westinghouse Electric Corporation provided under separate cover.

Page(s) 36 -d 1

t

t e

A3600 SBLOCA SCE\ ARIO ,

i  :  :  :

4-l- BLOWDOWN

! ADS i IRWST i

.LCS  :

i i OPERATION i INJ. i RECIRC.

W j SATURATION  ; j j c-  :  :  :  :

D i NATURAL-  !.

U)  :  !.  !.

u)  :  :  : i W i CIRCULATION i  !  !

c-O.

i i

i .  :  :

:  :  : i

:  :  : i i  :  :  :

: . 1

, . . . i 1

T1ME i

i I

1 28 OSU NUCLEAR ENGINEERING  !

1 .yym_.

I i) 1 Material proprietary to Westinghouse Electric Corporation provided under separate cover. >

i J

Page(s) 29 g7  !

J t

?

9 L

9 4

k P

i Material proprietary to Westinghouse Electric Corporation provided under separate cover.

i Page(s) #S- GS  ;

i r

h r

3 5

I a

5 h

F f

i e - n ,

4 3

x W

W Z

U z ,

W M

W 1

O

. p

!! $... okifi w Z S

u M

f '

! $ D 9ll

1. l }( ?! u fB >

s il ll  : <,' -

r.'.

. . , ,3 ,,

^

$e

<=

,-,,-,s,,'

.' 5. . .

,h)'il  ;

u  :

t -

antsaaiwas

.E O

o b bd .Eg es i

a CHAPTER 8:

SUMMARY

OF RESULTS AND CRITICAL ATTRIBUTES Sixty-three II group ratios have been developed to scale the following processes of importance to AP600 SBLOCA and long-term cooling:

Natural circulation and recirculation flow phenomena -

Depressurization phenomena Venting, draining, and injection phenomena

. Upper and lower values have been calculated for each II group ratio to assess the degree of distortion introduced because exact similitude is not achieved.

l l

l 57 OSU NUCLEAR ENGINEERING

I 9

i f

1 a

L Material proprietary to Westinghouse Electric Corporation provided under separate cover.

1 i

Page(s)__54 - 63 t.

i s

I e

d 9

6

-I f

h t

5 k

4 f

i i

Results of H Group Ratio Evaluation:

Two-phase natural circulation. processes during long-term cooling will be adequately modeled in the test facility. HCHF- '

will be examined further.

. Depressurization:

Dominant H group ratios are represented by H 7 through ,

H 10 and H through H36 (break mass and energy flow rate ratios)25. Distortions are due to the effect of pressure scaled fluid properties on critical flow ratios. The break mass flow and energy flow rates cannot both be ideally scaled under reduced-pressure conditions with the same fluid. .

Although the values for Hjg through H24 (SBLOCA. power ratios) exceed 1.5, Table 5.16 indicates that these H "

groups are not important to:depressurization.

64 OSU NUCLEAR ENGINEERING _'

_ . _ _ _ - . . - . . ._..-____._._._.__;..~..__.__.--._..._.._._____.-

Results of II Group Ratio Evaluations (continued): .

• Depressurization (continued):

Because fluid property similitude will exit during ADS 4-operation, depressurization from ADS 4 conditions will '

be simulated quite well. -(See H ii , H29, and H35 ) '

Venting, Draining, and Injection:

The dominant II groups for the CMT phenomena are II 37-through II39 The distortions in II,7 (CMT steam condensation rate) is due to the retuced CMT surface area and. effects of pressure scaling on fluid properties.

• Evaluate the importance of the distortions on the data.

r 65; OSU NUCLEAR' ENGINEERING -

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ -_ _____...__.c. --. _ - _ .- _ . . - _ . _ _ . _ __ . . ~ .N

Conclusions:

Assessment of II groups indicates that pressure scaled phenomena in the model will be representative of phenomena expected in the full-scale AP600.

Long-term cooling behavior will occur when fluid property similitude exists. II group assessment indicates that ADS 4 depressurization process through long-term cooling will be modeled well in APEX.

. The APEX facility data will provide sufficient data to benchmark the codes.

66 OSU NUCLEAR ENGINEERING

1 l

l OSU AP600 LOW PRESSURE INTEGRAL SYSTEMS EFFECTS TESTS -

TEST. MATRIX

~ ~

L.E. Hochreiter Westinghouse Electric Corporation l

l

\.

Approach OSU test matrix consists of two types of experiments Cold and hot pre-operational tests used to characterize the system and components. of the facility For computer code input to reduce uncertainty To provide additional data on components  :

with controlled boundary conditions

• Matrix tests with one-at-a-time parameter variations l

I j

OSU COI,D PRE-OPERATIONAL TESTS - (Revised 9/14/93)

TEST DATA IlOW USED IN CODE CMT Gravity Drain Flow versus line AP, CMT volume versus height Verify the line resistance form and frictional losses of the CMT injection lines, CMT volume Accumulator Drain Flow versus line AP, volume versus height Same as above but for accumulator IRWST Drain Flow versus line AP, volume versus height Same as above t>ut for IRWST Sump Drain to RCS Flow versus line AP, volume versus height Same as above but for sump Charging Pump Flow vs. Pressure Flow versus pressure table Used as a boundary condition in ,

the code NRilRS Pump Flow vs. Pressure Flow versus pressure table Same l Primary Flows and AP's Loop pressure drop for a given flow Used to adjust the form losses in the l code to match AP's for a given flow l

l Vessel Bypass Determination Determination the vessel bypass to Set bypass flow upper head

! Pressurizer and CMT balance line Flow versus AP for balance lines Confirm line resistance, set APs orifice as needed i

l l Loop Drain for Volume Check System volume versus height Confirm OSU model volumes l

0572LII-09I493 N

. . _ . _ _ _ __. - _ . . _ _ _ - - - - _ . -. .. - -_.______._________.--__r.--

OSU IlOT PRE-OPERATIONAL TESTS - (Revised 9/l4/93)

TEST DATA IIOW USED IN CODE Steady-State Forced Flow Flow rate, pressure drop, and temperature Verify the loop form and frictional Test lleat Losses, and distributions, pipe metal temperatures resistances, heat loss, system heat Calometric Balance rod bundle, PRilR, steam generator balance, heat transfer in bundle temperatures steam generator, PRilR Primary system heat Cool down rate of the system wall, Verify the structural capacity test fluid temperatuies, pressure models in the code Secondary Side Performance lleat transfer versus power level, verify the Verify steam generator model in codes steam generator control system PRilR Natural Circ Tests PRilR temperatures, IRWST temperatures. Confirm PRilR flow, heat transfer, PRllR flow for code Primary Side Natural Cire Flow Primary system, pressure, temperature, AP distribution Confirm the natural circulation Rod bundle, PRilR, steam generator temperatures behavior of cale for primary, flows, temperatures, core, steam generator, heat transfer.

CMT Recirculation Behavior CMT balance line flows, CMT wall fluid Confirm CMT recirculation behavior, temperatures, pressures flows, and temperatures, mixing effects CMT Draindown via Pressurizer CMT fluid and wall temperature distribution; pressurizer Verify CMT draining behavior, heat transfer, Balance Line balance line, temperature, pressure distribution; system heat up, CMT condensation behavior, pressures, pressure drops, pressurizer pressure mixing effects to develop / verify CMT model CMT Draindown via Cold Leg ' Same except use cold leg balance line as steam Same, except examine CMT Balance Line supply from rod bundle behavior with larger cold leg balance line flows Low Pressure Depressurization Full compliment of data on system Verify break flows, system transient Checkout behavior, pressures, pressure drops, temperatures and break flows 0572Lil-091493 03 l

- - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ ___-____v-_w w a 2 v' t-

OSU TEXT MATRIX - Revision 3 9/14/93 TEST TEST PRilR NSS SINGLE NO. TYPE TEST DESCRIPTION STATUS STATUS FAILURE COMMENTS SBl SBLOCA 2" CLB, bottom of pipe, Loop A," On Off I of 2 4th Reference cold stage ADS leg break SB2 SBLOCA 2" CLB, bottom of pipe, Loop B On Same Same Break on opposite side of plant SB3 SDLOCA 2" CLB, top of pipe, Loop A On Same Same Break orientation SB4 SBLOCA 2" CLB, bottom of pipe, Loop A Off On Same Safety /non-safety system interaction, prevent 4th stage ADS SB5* SBLOCA ~l" CLB, bottom of pipe, Loop A On Off Same Break size effect SB6 SBLOCA 4" CLB, bottom of pipe, Loop A On Off Same Break size effect SB7 SBLOCA 2" CLB, bottom of pipe, Loop A On Off Fail Beyond design basis.

complete ADS performance train 1-4 SB8 SBLOCA 2" CLB, bottom of pipe, Loop A On Off Fail ADS perfomtance stages 1,3

• Continue into long-term cooling mode

• • Loop A is CMT side, Loop B is pressurizer side 05U U509149)

N

OSU TEXT MATRIX - Revision 3 9/14/93 4

TEST TEST PRilR NSS SINGLE NO. TYPE TEST DESCRil' TION STATUS STATUS FAILURE COMMENTS SB9 SBLOCA 2"CL balance line, horizontal loop, On Off Fail I of Break location Loop A 2, 4th asyrnmetric CMT Stage ADS performance SBIO* SBLOCA DEG, CL balance line, horizontal On Off Same Break size effect Loop A SBil* SBLOCA DEG, DVI line break On Off Same Break location, loss of on ECCS train SB12* SBLOCA DEG, DVI line break On Off Fail 1,2 Alternate Single ADS Stage Failure SBl3* SBLOCA 2" DVI line break On Off I of 2,4th Break size, asymmetric stage ADS CMT behavior SBl4* SBLOCA Inadvertent ADS, stage I open On Off Same ADS performance

• Continue into long-term cooling mode 0573tH U98493 1

OSU TEXT MATRIX - Revision 3 9/14/93 TEST TEST PRilR NSS SINGLE NO. TYPE TEST DESCRililON STATUS STATUS FAILURE COMMENTS

< SB15 SBLOCA 2" IILB bottom of pipe, Loop A On Off I of 2 4th Break orientation stage ADS SBl6* SBLOCA DEG PRZ/CMT BL break, between check On Off Same Break location valve /CMT, Loop A SBl7 SBLOCA DEG, PRZ/CMT BL break between On Off Same Break location PRZ and check valve SB18' SBLOCA 2" CLB, bottom of pipe, Loop A On Off Same Repeat test SB19 SDLOCA 2" CLB, bottom of pipe, Loop A On Off I of 2 4th Effects of transient il with transient containment back stage containment pressure f prassure SB20 SBLOCA 2" CLB, bottom of pipe, Loop A On Off I of 2 4th Effects of reduced with revised condensate retum stage condensate retum on core cooling LTC21 LBLOCA Simulate long-term cooling effects On Off I of 2 4th Decay heat removal following LBLOCA stage effects early in transient

• Continue into long-term mode 037)LH 09149)

D

_ _ . _ _ _ .- . _ _ _ _ _ _ _ . _ - - _ _ _ . _ _ _ _ _ Z^ 1-

. Test matrix Tests have been structured around the SSAR Analysis Tests are planned examining different and more limiting single failures Some NRC comments have been incorporated into matrix, others are under evaluation Overlap tests are planned with SPES to examine scaling behavior.

0572LH4)91493 7

j!

Conclusions ,

Test matrix is sufficiently broad to adequately provide the information to validate the SSAR analysis codes Overlap tests with spes are included to provide a scaling overlap.

0572LH-091493

OSU PROGRAM SCHEDULE n .

EJ. Pipilca, Manager AP600 Testing Engineer,, y 4A .

' i~

t5

.. 't j' .} .

A

),.,,_ #

'F

(- *1 f 5 -'

l 6 m9 dy -> . n <s.t.'

M

't... . t l l

1 I

e 7 P i e 3 d

v 1

I l

1 1

1 l

f !

a e i m e r -

l e reu t

u J I s

. a o

I TJ -

y a r r I r

o a e

1 Ta e s - TL a

F s

A x

e 4 p

p A hJ T_

1 r4 rP rA 5

% 9 4 c

s n l L. I 9

- a l ui l. T4 H

J T

• d U

L F r L

E F

e 1 I I

~

_ ] -

rE TF U

S e J h

_ _ pA e r

M E

a _.

TJ T

S C

E .h r Y O 2 rEC

. S TO _

L Wli M

r rW A i A TM .

G E

T C l i

r .

O i rTC T

N TO -

- I P

i r

E S

I i

FPE T

H rS G L I r

G UL -

I A

rCa E 1 i TA 4

H i i I L

h 4

t 3 9

Ul J i i

m i I

I I I

I i LN iL.

i P

3 9

/

N Ul I I r4 P 1 J i TU E

I I M TJ .

R Y

i I I r

A l rY m

l I U M i A

- S S

l I M M T A.

E R

i i I r

R P

P A

R i l

i mM I I M M m M mM rPH TA -

• A I i R M M Mm a

e. iA O i im A

L B

i r

0 1

E l S

N i

i m 'M .

Mm rtR.

TF M i M A

m l

J i iA T i J N

A C i

r mM m rE C H E D l m mM i

C iD i

Ni i

- 2 9

T I

N i i

mM m m m iN i .4 2

9 i T C

O i I

i u m m -

iC i O r

P n P e

El S i m m lE i S E h 1

a . . E

. 9 o q m . _ -

o s

a e

m m

4 ,

, o. .

4 h

e l.

d mrc m c

a e . .

A , a c . .

e .

m, ts

- o .o .

a

.o _

_. . . e

=

a c

a m

G.

S . . .

L ,m

.e n

,- m_

, . L .

. e

. . = .

G . , A O .

. ,. a _

O m A

o. o

, c .

,~~

. . ,a _

. t . o .

. s

. e

.i a

. T T - .

t ,

A . e o

a

, . . , it a . e .

c

. c - . 4 . t m

. a c C o

x.

.c e

• e m

c .

4L C

A

. m .~.

- m m as a

_9 m

. . e e e , .. - , .

m .e .,a o ,

. L . A .e

=

%8

L i =-

a a s=i i ie N! si

,I bh l h b!,

, 1_ - _ ._ _f 8

.=  : :  : 2 g ._

m

, g h' ' uj  : '

bu o 8J l' 1

h' F .8

.- ~ m

, IG  :  :$

y a _ _ _ _ _

o u;

,1 8  :  :  :  : : r8

} ,_ _ I

_ _ _ _ W g

NT p  :  :  :  : : : $

h h I E hhh  !

q _-

m

. i  ! _4

s =

.i ie al l

. I I I fi a

a

!s ll '

l l

'l l + .I s!

.e

• 1- . t1 i'

e d l ~e Il! i T~

o . _ .

c  !, ___

l 0

se lll l lg l ~s

!T lg3 T5 8T Z8 a - a I  ! ,

i; s*~{

^ I . e r$

, i !

• I "le

!l y e

- lf  !.

j .

i, i

a 5

l

!. l 5

a f

i. i g a i

8 i

i j i ;I i

~

l 'l .!!

.I iy i

i 1

5 a

i

?

y-

.! . i .

i ! e 1 8

' I f I i t :. I;a 8

1 ] r gi n 3l

.g )

e i ;v g 2i

; v ! ! !

) ;r 9 i-s!I o 3 i I.....

i

g4.1 -

e . a : l a 1 a i i a i, .s : i

.! . . . . 1 i

b v <c,

h SCHEDULE Facility construction is about six months behind our FY 93 work plan developed in July 1992 Original plan for testing was serial:

Complete all construction activities Cummission facility Perform cold shakedown tests Perform hot shakedown tests Delays in the design of the BAMS and its subsequent fabrication and installation threatens to further delay the initiation of testing Develop revised construction / testing plan Continue facility construction Perform cold shakedown tests as construction continues Complete BAMS design; procure, fabrication and installation and cold shakedown tests Perform hot shakedown tests Initiate matrix tests 3

SCHEDULE 1 Actions to implement revised plan Develop detailed project schedule Add manpower to identify activities to complete and develop schedule Assign Westinghouse Test Engineer to OSU Construction contractor will support test activities through shakedown testing i

b I'

k 1

6