ML20065M312

Requests That Proprietary Info on Test Conditions for AP600 Testing Performed at SPES-2 & Osu Test Facilities Be Withheld Per 10CFR2.790

ML20065M312
Person / Time
Site:	05200003
Issue date:	04/12/1994
From:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Borchardt R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19304C001	List: ML20065M312 NRC-94-4070, Forwards Nonproprietary & Proprietary Info on Test Conditions for AP600 Testing Performed at SPES-2 & Osu Test Facilities.Proprietary Info Withheld Per 10CFR2.790
References
AW-94-596, NUDOCS 9404250270
Download: ML20065M312 (45)

Text

'

Westinghouse Energy Systems Ba 355 ,

"'"'""'an rennsyivania 15230 0355 Electric Corporation AW-94-5%

April 12,1994 Document Control Desk U.S. Nuclear Regulatory Commission

~ Washington, D.C. 20555 KITENTION: MR. R. W. BORCHARDT APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

SUBJECT:

INFORMATION ON TEST CONDITIONS FOR AP600 TESTING PERFORMED AT THE SPES-2 AND OSU TEST FACILITIES

Dear Mr. Borchardt:

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-94-5%

accompanies 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.

l Correspondence with respect to this application for withholding or the accompanying affidavit should ]

reference AW-94-5% and should be addressed to the undersigned. l Very truly yours, L /#'

N. J. Uparulo, Manager Nuclear Safety And Regulatory Activities

- /nja -

cc: Kevin Bohrer NRC 12H5 uw 9404250270 940412 PDR ADOCK 05200001 A PDR

9 AW-94 5%

AFFIDAVIT COMMONWEAL *ni OF PENNSYLVANIA:

ss COUNTY OF ALLEGHENY:

Before me, the undersigned authority, personally appeared Brian A. McIntyre, who, being by 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 averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, infortnation, and belief:

^

Ju

. ,fJ Brian A. McIntyre, Manager Advanced Plant Safety & Licensing Sworn to and subscribed before me this /[ day of Ab .1994 i

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uinj Notary Publh rmwa the Abb Payno iltwy PutAc f.btrawe tho, Mg erty Cainty My Comunaan Emres f*ye 4,1tr>6 Monta,PerruWaio Au>:nconat.wam ,

ImA

AW-94-5%

(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 power plant licensing and rulemaking proceedings, and am 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 withhcid from public disclosure should be withheld.

(i) The information sought to be withheld from public disclosure is owned and has been .

held 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, utili7cs 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.

Under that system, information is held in confidence if it falls in one or more of i 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-94-596

-(a) The information reveals the distinguishing aspects of n process (or component, structure, tool, methcx1, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a l competitive economic advantage over other comp;mics.

1 (b)- It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, 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. .j (f) It contains patentable ideas, for which patent protection may be desirable.

'1 l

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

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l (a) The use of such information by Westinghouse gives Westinghouse a l 1

competitive advantage over its competitors it is, therefore, withheld from l 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.

15MA

AW 94-5%

(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 infonnation pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one comp (ment may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

(c) Unrestricted disclosure would jeopardire 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 j provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission. .

1 (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 Letter NTD-NRC-94 4070, April 12,1994, being transmitted by q 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 1 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.

15MA -

AW-94-5%

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.

(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 <lesign.

(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.

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.

The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort '!

and the expenditure of a considerable sum of money, 1537A

. . . _ _ _ _ _ _ . _ . _ _ _ - . . . . m _. _ _ . .

1 AW.94-5%  ;

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

..1 Further the deponent sayeth not.

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.4 Nonproprietary Copy Attachosent 1 to Westinghouse IAtter NTD 94-4070 Information in support of Westinghouse Response to RAI 952.37 RAI 952.41 l

i 1

Question 952.37 Supply the calculated hole size of the vadous ortflee plates for the OSU/ APEX fadlity, including the respective dentred pressure drop and the location to be installed. The star undentands that all orifices may not be lastalled pdor to preoperational testing. Is that cornct?

Response

Table 95237-1 summarizes all orifice plates used in the OSU test facility. _The K value and flow rate are also - )

included.

All orifia plates, with the exception of the ADS stage 1,2,3 and 4 orifice plates, have been installed in the facility for preoperational testing. These orifice plates will be adjusted, if necessary, to provide the prcper line resistance during preoperational testing.

The orifice plates used in ADS stages 1 through 4 simulate the flow area. Pressure drop information on these plates will obtained during hot pre operational testing.

Table 95237 2 summarizes break area calculations for the OSU test facility.

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l l

l nu l

= . . - . - - -

e-Attachment I to Westinghouse Letter NTD.94 4070 (continued)

Table 952.371 AP600 OSU Test Facility Orifice Plate Summary l05UTestFacilityl Component l- " - " ------l l Design lOrif.IDl Remark

...................................j....... ......l..........................................

1. CMT To OV! Line No. 1: l l l (a) CMT-DV1 fee (Node A - Node 1) l l lDWGLKL 920200 Sheet 2 ID, in l 1.120l l InitialPres. psia l38.300l l No. of orifice l 1.000l0RI555jorificeisbetweennodeJandnodeK ,

K, orifice l35.620l l Note 11LineresistanceofbothDVIlines orifice ID, in l 0.547l l are balanced in AP600 and test Flow Rate, ltxn/secl 1.146l l l 1 I (b) DVI fee - DV! Nozzle (inclusive)l l l0WGLKL920200 sheet 2 (0, in l 1.120l lNodeItoNodeM Initial Pres. psia l 38.300 l l No of orifice l 1.000l0RI-253l K , orifice l 0.899l l Orifice 10, in l 1.270l l Flow Rate, lbm/secl 1.146l l I I I

2. CMT02 to Dv! Line No. 2: l l lDWGLKL 920201 Sheet 2 (a) CMT-DV! Tee l l lNodeCM1-CM10 10, in l 1.120l l InitialPres. psia l38.300l l No. of orifice l 1.000l0RI.556lLocatedbetweennodeCMT1andCMT2 K , orifice l36.620l l Orifice ID, in . l 0.547l l FlowRate,tbm/secl 1.146l l l l I (b) DVI Tee DVI Nortle(inclusive)l l l Node CM10 CM13 10, in l 1.120l l InitialPres, psia l38.300l l No. of orifice l 1.000l0RI254l K , orifice l 2.023l l

orifice 10, in l 0.843l l FlowRate, Ibm /secl 1.146l l 1 I i

Attachment I to Westinghouse Letter NTD 94 4070 (continued)

Table 952.371 (continued)

AP600 OSU Test Facility Orifice Plate Summary l0sUTestFacilityl Component l------*-----l l Design lOrif.IDl Remark

.............................l........;.......l.............................................

3.CMt01-ColdLesBalanceLineNo.1:l l lDWGLKL 920200 sheet 4, node CL1 CL11 10, in l 1.120l l Initial Temp. F l444.680l l InitialPres, psia l400.390l l No. of orifice l 1.000l0RI-553lLocatedbetweennodeCLSandnodeCL6

(_ orifice l 3.150l l Note 1: Line resistance of both DVI lines orifice 10, in l 0.812l l are balanced in AP600 and test Flow Rate, Ltzn/secl 0.530l l

\ l l

4. CMT02 Cold Leg Balance Line No.2 l l lDWGLKL 920201 sheet 3 node CT1 CT12 ID, in l 1.120l l Initial Temp. F [444.680l l InitialPres. psia l400.390l l No. of orifice l 1.000l0RI-554lLocatedbetweennodeCTSandnodeCf6 K_ orifice l 3.465l l Orifice ID, in l 0.765l l Flow Rate, itzn/secl 0.530l l 1 1 I

5. ACC 01 DVI s1 Injection Line: l l lDwGLKL 920200 sheet 5. Node Al All ID, in l 1.120l l InitialPres.psfal19.200l l No. of orifice l 1.000l0RI451lLocatedbetweennodeA3andNodeA4 K_ orifice l17,320l l Orifice ID, in l 0.616l l FlowRate,lbm/secl 3.130l l l l 1

6. Acc 02 - DVI *2 Injection Linet l l lDWGLKL 920201 sheet 4 Node AC1 Ac8 10, In l 1.120l l InitialPres, psia l19.200l l No. of orifice l 1.000l0RI-452lLocatedbetweennodeAC1andAc2 K, orifice l16.360l l Orifice ID, in l 0.624l l Flow Rate, Ltxn/secl 3.130l l l 1 1 1

I l

l 1

I

. .. . . - =.

1 l

Attachment I to Westinghouse 1.etter NTD.94 4070 (continued)

Table 952.371 (continued)

AP600 OSU Test Facility Orifice Plate Summary I

l0SUTest Facility (

Component l- --'-"l ,

l Design l0rif.10l Remark .l

..........l........l.......l.............................................

7. IRWST To DVI Line No.1: l l lDWGLKL 920200 sheet 3 (a) IRWST - Sump Tee: l l l Node 14-NodeT4 ,

10, in l 2.250l l Initial Temp. F l ambient l l InitialPres,pslal NA l l No. of orifice l 1.000l0RI-751lLocatedbetweennode13and14 K_ orifice l 2.200l l Orifice 10, in l 1.687l l Flow Rate, Ltxn/secl 0.770l l

! I i (b) Sump tee Dv! Tee: l l lNadeT4NodeT1 10, in l 1.120l l Initial Temp. F l ambient l l InitialPres. psia lNA l l No. of orifice l 1.000joRl*753lLocatedbetweenNodeT1andNodeT2 K, orifice l19.000l l Orifice ID, in l 0.609l l FlowRate,(bm/secl 0.770l l 1 I l

8. IRWST To OVI Line No. 2: l l lDWGLKL 920201 sheet 6 (a) IRW$T - Sump Tee: l l lNodeST9toNoseSN1 10, in l 1.500l l Initial Temp. F l ambient l l InitialPres. psia l NA l l No. of orifice l 1.000 l0RI-752 l Located between Wode ST8 and Node ST9 K , orifice l10.900l l Orifice ID, in l 0.906l l FlowRate,ihm/secl 0.771l l l l l (b) S e p Tee

• DVI Teet l l lNodeSN1*NodeST1 ID, in l 1.120l l Initial Teep. F laatient l l InitialPres,pslalNA. l l ,

No. of orifice l 1.000l0RI754l K_ orifice l.12.680l .l Orifice 10, in l 0.656 l l FlowRate,lbm/secl 0.771l l' I I I 4

= = - -

s Attachment I to Westinghouse Letter NTD.94 4070 (continued)

Table 952.371 (continued)

AP600 OSU Test Facility Orifice Plate Summary l0SUTestFacilityl co ,onent i.................

l Design lOrif.1Dl Remark

...................................j.......l........l............................................

9. Sum Recir At DV! Line No. 2: l l lDWGLKL 920201 Sheet 6 (a) Sump Tee

• Sump (SN1*SN9a): l l l(doublecheckvalveline) 10, in l 0.870l l two sum recirculation lines.

Initial Te g . F l ambient l l InitialPres, psia l17.250l l No of orifice l 1.000 l0RI 912 lBetween node SN9a and primary su m nottle K , orifice l13.400l l Orifice 10, in [ 0.500l l FlowRate,lbm/sec) 0.154l l 1 I I (b) Sum Recir. Parallet Line l l lMOV tine nominal value for the test to model (SN4a SN9b, normally closed) l l l 10, in l 1.000l l Initial Teg . F laabient l l InitialPres,palaj NA l l No. of orifice l 1.000 l0RI-910 lBetween node SN9b & primary sum tank nozzle K , orifice l 3.200l l Orifice 10, in j 0.734l l FlowRate,tbm/sec) 0.154l lThisismax.recirflowatbeginningof l l lrecirculationoperation. Actual flow when l l lthislineisinuseisnotknownatthis

10. Sum Recir At DVI Line No.1: l l lDWGLKL 920200 sheet 3 (a) 1RWST/ Sum Tee' + Sunp (T4 56b):l l lDoublecheckvalveline 10, in l Note 1 l ,l Note 1: Line size varies from Initial Te g F l ambient l l 2.250 in, to 1.000 in.

Initiet Pres pelal 17.250 l l They are predetermined in other No. of orifice l 1.000l0RI909l recirculation line calc.

K,, orifice l27.270l l Orifice 10, in j 0.510l l FlowRate,(bm/secl 0.154l l l l I (b) Sum to sum branch l l lt.ocated between node $6b and sum tank nottle (S2a S6a, normally closed) l l ID, in l 2.250l l Initial Teg . F l ambient l l InitialPres,psisl NA l l No. of orifice l 1.000 l0RI 911 l Located between Node S6a and sunp tank no12Le K , orifice l 2.633l lThisismax.recteflowatbeginningof Orifice 10, in l 1.631l jrecirculationoperation. Actual flow when FlewRate,(bm/secl 0.154l lthislineisinuseisnotknownatthistime i

o 1

i

Attachment I to Westinghouse Letter NTD 94-4070 (continued)

Table 95?.3"11 (continued)

AP600 OSU Test Facility Orifice Plate Summary l0SUTestfacilityl Component l-*'----'-----l l Design l0rif. !Dl Remark

.......................l........l........l.............................................

I I I 11.PRHR Nx Outlet l l l0WGLKL930101 sheet 1 10, in l 1.260l lNodePRHRAtoNodePRNRL Initial Temp. F l170.000l l InitialPres. psia l NA l l No. of orifice l 1.000l0RI855lLocatedbetweennodePRHRCandPRHRD K_ orifice l Note 1 l l Note 1: Orifice plate is not required. A Orifice ID, in l 1,260l l space is used to fill the gap.

Flow Rate, Ltn/Secl 1.210l l l l l 12.PRHR Inlet Loop l l lDWGLKL 930101 sheet 1 4/ (a) H.L. To PRhR Tee l l lNodeCOM1-COM4 10, in l 1.610l l Initial Tenp. F l450.000l l InitialPres.rsial385.000l l No. of orifice l 0.000l l K , orifice l NA l l Orifice ID, in l NA l l Flow Rate, lbm/secl 1.210l l 1 I I (b) PRNR TEE To Ha inlet Nozzle l l lNodeCOM4-PRHR12 10, in l 1.260l l Initial Tenp. F l NA l _l InitialPres,palal NA l l No. of orifice l 1.000l0RI854lLocatedbetweenNodePRHR1andnodePRHR2 K_ orifice l Note 1 l l Note 1: Orifice plate is not required. A Orifice ID, in l 1.260l l spacer is used to fill the gap. l Flow Rate, Ltn/secl 1.210l l l l l

-13.CMT01-PressurizerBalanceLine#1l l l0WGLKL920200 sheet 7 l l l Node P2A1 . Node PZA8 10, in l 0.430l l J Initial Temp. F l NA l l 'l InitialPres, psia l400.000l l l No. of orifice l 1.000l0Rl*551lLocatedbetweennodePZA2andPZA3 I K_ orifice l Note 1 l l Note 1: Orifice plate is not required j orifice 10, in - l 0.423l l when no break is on the line. .j FlowRate,lbm/secl 2.448l l A spacer is used to fill the gap. l l l l 14.CMT01 Pressurizer Balance Line e2 l

i

_ _1 . _ _ _ __ _ _ _ _ -

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

Attachment I to Westinghouse Letter NTD.94 4070 (continued)

Table 952.371 (continued)

AP600 OSU Test Facility Orifice Plate Summary l05UtestFacilityl Conponent l"'--l l Design l0rif.IDl Remark

..................................l........l.......j.............................................

15.RNS Pump Discharge Branch Line #1 l l lDWGLKL 920200 sheet 6 (To DV! #1) l l lNodeR5 Node R1 ID, in l 0.875 l l I ni t i al f enp. F l ambient l l-InitialPres.pslajambientl lOrificeplateisbetweenNodeR3andNodeR4 No. of orifice l 1.000l0RI-853l Note: Orifice plate is alled to balance K_ orifice l 1.380l l flow between two parallel branch lines.

Orifice 10, in l 0.700l l Flow Rate, ltrn/sec l 1.454l l l l l 16.RNS Punp Olscharge Branch Line #2 l l lNodeR8-NodeNR1 (To Dv! #2) l l l ID, in l 0.875l l Initial Tenp. F l NA l l InitialPres.palal NA l l No. of orifice l 1.000l0RI-857lLocatedbetweenNodeNRSandnodeNR6 K_ orifice l Note 1 l l Note 1: Orifice plate is not required. ~A Orifice 10, in l 0.875 l l spacer is used to fill the gap.

Flow Rate, lbm/secl 1.454l l l l l

17. Pressurizer . ADS 1 3 Header l l l0WGLKL920202 sheet 1Rev.5 l l lNodeADS1*AD$5 10, in l NA l l Initial Temp. F l NA l l InitialPres.pslal NA l- l No. of orifice l 1.000 l0RI+653 l Located between Node ADS 3 and ADS 4 K_ orifice l Note 1 l lNoteisOrificeplateisnotrequired. A

{

orifice ID, in l 2.350l l spacer is used to fill the gap. I FlowRate,lbm/secl NA l l

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Attachment I to Westinghouse Letter NTD-94-4070 (continued)

Table 952.371 (continued)

AP600 OSU Test Facility Orifice Plate Summary l0SUTestFacilityl Component l""-*"*--'l l Design lOrif. IDl Remark

... . . ... ... . . . ............;......;.......[...........................................

18. ADS 13SeparatorLiquidDrainLinel l lDWGLKL 920202 sheet 1 Rev. 5 l Node ADSL1 ADS 16C l l 10, in l Note.1 l l Note 1.Linesizevaries,seedrawing.

Initial Temp. F l213.000l l InitialPres.psisl15.000l l No. of orifice l 1.000lORI-659lLocatedbetweennodeADSL4andnodeADSL5 K_ orifice l23.280l l Orifice 10, in l 1.090l l Flow Rete, Ltm/secl 5.263l l l l I

19. 5" ADS 4 Separator Liquid Line l l lDWGLKL 930101 sheet 2 Rev. 3 (Nobreakcaseandallothercases)l l l Node SEP1 to SEP5 to primary stsnp tank.

ID, in l note 1 l lNoteit line size varies. See DWG Flow'Conditionst l l l Initial tenp. F l251.600l l InitialPres, psia l30.690l l No. of orifice l 1.000loRI-603lLocatedatnodeSEPS K , orifice l 5.464l l Orifice ID, in l 2.390l l Flow Rate, Ltn/secl 2.297l l l l l 20, 8" ADS 4 Separator Liquid Line l l lDWGLKL 930101 sheet 2 Rev. 3 (No break case on the line) l l l Node SEP1 to SEP5 to primary suno tank.

10, in jnote1 l l Note 1 Line site variet.. See DWG.

Initial Tenp. F l251.600l l InitialPres,palaj30.690l l No. of orifice l 1.000l0RI602AlLocatedatnodeSEP1A K , orifice l 5.464l l orifice ID, in l 2.390l l Flow Rate, Ltn/secl 2.297l l l 1 I

21. Sa ADS 4 Separator Liquid Line l l lDWGLKL 930101 sheet 2 Rev. 3 (DEG PZR/CMT break case) l l lNodeSEP1toSEP5toprimarysumptank.

ID, in l note 1.l l Note 11 Line size varies. See DWG.

Initial Temp. F ~ l216.300l l InitialPres,pela)16.000l l No. of orifice l 1.000l0Rl*602BlLocatedatnodeSEP1A K , orifice l218.200l l Orifice ID, in l 1.156l l Flow Rate, Ltn/secl 2.170l l l

Attachment I to Westinghouse Letter NTD.94.4070 (contmued)

Table 952.371 (continued)

AP600 OSU Test Facility Onfice Plate Summary l0SUTestFacilityl c ,n.n1  ;.................;

jDesignl0rif.1Dl Remark

.. ......... ...... .........................,........i..........................................,.

22.Large Break Separator Liquid Line l l lDWGLKL 930400 sheet 1 Rev. 2 (For all break cases) l l lNodeAtoNodeE ID, in l Note 1 l l Note 1: Line size varies. See OWG.

Initial temp. F l216.300l l InitialPres.pslal16.000l l No. of orifice l 1.000 l0RI.905 l Located at node E K_ orifice l 9.330l l Orifice 10, in l 1.281l l Flow Rate, ttrn/secl 20.970 l [  !

l d

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+

1 Attachment 1 to Westinghouse Letter NTD.94 4070 (continued)

Table 952.371 (continued)

AP600 OSU Test Facility Orifice Plate Summary The following orifice plates are designed to model ADS flow area, not for line resistance fine tuning.

Line identification Orifice No. Remark (a) ADS 1-3 Simulating Double Ended DVI Line ORI 655 1 Between node ADS 9 . ADS 9a (ADS stage 1) break and single train of ADS 1 3 (DWG LKL 920202 sheet 1 Rev. 5) ORI 656-1 Between node ADS 7 and ADS 8 (2nd Stage ADS) I OR I -657 1 Between node ADSS and ADS 10 (3rd Stage ADS)

(b) ADS 1-3 simulating Double Ended Dv! line ORI-655 2 Between node ADS 9 . ADS 9a ( ADS stage 1) break and TWO TRAIN of ADS 1 3 (DWG LKL 920202 sheet 1 Rev. 5) ORI.656 2 Between node ADS 7 and ADS 8 (2nd Stage ADS)

ORI-657 2 Between node ADS 5 and ADS 10 (3rd Stage ADS)

(c) ADS 4 on hot leg #1 (CMT side) ORI-651 Downstream of ADS 4 valve, RCS 615 -

(8a ADS 4 separator side) (DWG LKL 930502 sheet 1 Rev. 0)

(With no failure on the ADS 4 line)

(d) ADS 4 on hot leg #2 (Pressurizer side) ORI-652 Downstream of ADS 4 valve, RCS 616 (Sa ADS 4 separator side) (DWG LKL 930502 sheet 1 Rev. 0)

(With no failure on the ADS 4 line) l l

1 l

l 1

1

Attachment I to Westinghouse Letter NTD.94 4070 (continued) l Table 952.37 2 AP600 OSU Test Facility Break Area Calculations I

Break Area Calculations I eu a

P Psia PAPEx - 350 AP600 s I. Hot Lee AP600 APEX (4,c)

Wall Thickness (L) in. 0.5213 ,

0.3208 Break Diameter (D) in.

Break Area (A) in- 0.0808 (UD) 1.625 II. Cold Lee 1 Wall Thickness (L) in. 0.4106 0.3208 Break Diameter (D) in. 0.0808 Break Area (A) in (UD) 1.28 L .

III. ADS ' Throat Area - DEDVI 15 ' Stace ADS Single Line: [ ~I"'9 Throat Diameter ig. 0.2886 Minimum Area in 0.6540 Two Lines Combined:

Throat Diameter 0.4082 Minimum Area in 2 0.1308 2"d and 3rd Stage ADS _

Single Line:

Throat Diameter ig. 0.6234 Minimum Area in 0.3052 Two Lines Combined:

Throat Diameter in. 0.8816 2

Maximum Throat Area in 0.6104 VI. Fourth Stage ADS -(Fluid Property Similitude)

Single Line: kC) 1.004 Throat Diameter in 2 0.7917 Maximum Throat Area in - -

Attachment 1 to Westinghouse letter NTD 94-4070 (continued)

Question 952J8 hientify any valves in the OSU/ APEX facility that may tave significant now kwees as a result of tlwir design. Provide an estimate of the expected pressure drop.

Rosponse De .vives for the Core Makeup Tank. ADS Stages 1 through 4, IRWST, accumulators and sump recirculation are full port ball valves and therefore do not introduce significant flow losses. Standard check valves have been impfemented in the injection lines. De pressure drop in these lines, as well as all other primary system piping, are being measured as part of preoperational testing. Line resistances will be calculated using the flow test results. Control valves used in the feedwater lines, BAMS and condensate return system will be throttled to model scaled AP(40 processes.

Question 95239 Provide the valve opening and closing rates for the motor-operated valves used in the OSU/ APEX facility.

Response-All injection lines, ADS Stages 1 through 4, Core Makeup Tank and sump recirculation line valves have opening and closing times of less than I second.

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4 Attachment I to Westinghouse Letter NTD 94 4070 (continued)

Question 952,40 Provide the planned power to each radial zone of the core heater rods of the OSU/ APEX facility, if specific measurements or design requirement.i have been made of the axial power profile, provide these .

values.

Response

The 051' test facility simulated core region is comprised of 24 rods in tbe high power region and 24 rods in the low power region. Each rod has a heated length of 3 feet and a maximum power of 15 kw. The following additional information is provided:

Table 952.40-1 AP600 OSU Test Facility Core Decay Power Simulation Table 952.40-2 AP600 OSU Test Facility Axial Power Fractions for 1/4 Length Scale Core Figure 952.40-1 AP600 OSU Test Facility Radial Power Distnbution in Model Core Figure 952.40-2 AP600 OSU Test Facihty Core Power Decay Simulation Figure 952.40 3 AP600 OSU Test Facility Axial Linear Power Profile (Normalized) for tim Model Core

4 Attadiment I to Westinghouse Letter NTD.94 4070 (continued)

Table 952.401 AP600 OSU Test Facility Core Decay Power Simulation DECAY , MODEL HIGH LOW MODEL IDEAL TIME POWER POWER POWER Int. Int.

(SEC) (KW) ZONE ZONE (KJ) Energy (KJ) 0.5 700.0 350.0 350.0 175.0 316.0 0.75 700.0 350.0 350.0 350.0 627.8 1 700.0 350.0 350.0 525.0 931.7 2 700.0 350.0 350.0 1225.0 2088.0 3 700.0 350.0 350.0 1925.0 3170.8 4 700.0 350.0 350.0 2625.0 4202.4 5 700.0 350.0 350.0 3325.0 5194.6 7.5 700.0 350.0 350.0 5075.0 7553.4 10 700.0 350.0 350.0 6825.0 9778.8 20 700.0 350.0 350.0 13825.0 17949.9 30 700.0 350.0 350.0 20825.0 25316.4 40 700.0 350.0 350.0 27825.0 32186.9 50 700.0 350.0 350.0 34825.0 38703.1 75 650.0 350.0 300.0 51700.0 53970.7 100 574.7 335.0 239.7 67008.3 68174.1 200 479.3 313.9 165.3 119704.1 119704.2 300 439.7 288.0 151.7 165653.0 165653.1 400 411.7 269.7 142.0 208223.4 208223.5 500 389.8 255.3 134.5 248298.4 248298.6 750 350.0 229.2 120.7 340771.4 340771.5 1000 322.1 211.0 111.1 424785.1 424785.2 2000 260.2 170.4 89.8 715964.4 715964.5 3000 229.4 150.3 79.1 960778.8 960779.0 4000 209.9 137.5 72.4 1180434.1 1180434.2 5000 195.9 128.3 67.6 1383350.8 1383350.9 7500 173.0 113.3 59.7 1844560.0 1844560,1 10000 158.7 103.9 54.7 2259173.4 2259173.5 20000 129.2 84.6 44.6 3698382.5 3698382.7 30000 114.7 75.1 39.6 4917833.7 4917833.8 40000 105.3 69.3 36.5 6020217.6 6020217.7 50000 99.5 65.2 34.3 7046661.7 7046661.8 75000 89.7 58.7 30.9 9411755.2 9411755.3 100000 83.7 54.8 28.9 11579554.3 11579554.4

l Attachmer.t I to Westinghouse L.etter NTD.94-4070 (continued)

Table 952.40 2 AP600 OSU Test Facility Axial Power Fractions for 1/41 ength Scale Core Axial Power Fractions for 1/4 Length Scale Core Fraction of Total Intecration Band (ft) Rod Power 2.5 - 3.0 0.19363 2.0-2.5 0.24293.

1.5 - 2.0 0.22485 1.0 - 1.5 0.17981 0.5 - 1.0 0.11724 0 - 0.5 0.04154 Total 1.00000 l

1

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3 - -!

-Attachment I to Westinghouse Letter NTD 94-4070 (continued) .

-t Figure 952.40 1 '

AP600 OSU Test Facility Radial Power Distribution in Model Core

.L k

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G G

(

Q G .

A x .... x /

/) o e e e e- o / ,

/ r G

o G

o e

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e X

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e e

e e

G o-Q G

f

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N N e e e o f -

" Legend g g o Low Power e High Power -

4 Thermocouple Rods

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,., e- - - - - -

. - - + - -

Attachment I to Westinghouse Letter NTD.94-4070 (continued)

Figure 952.40 2 APM)0 OSU Test Facility Core Power Decay Simulation 800

/00as - - m- m- um- m m- -u -m--- - - - - --- -- - - - - --

a .,

600- --------m--------------------

500- - --- - - - -- - -

a v e g ...........................................................mg ....................................................

> De a m eeB mm a a :. . 00

• b 300-- -- - -- - - - - - - - - - - - - - - - - -

- - - -- - -*- x - - C- o D a

- - --- -- - --- - - U -- - =- 8m- - - - -- - -

200-

"a C

• • g a 100--

-- D M - g

• g , H '**' m' n

. *x - - w, U-G - d- 0 00 a r

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C , , . . ..... . . . ,..... . . , . . . . , , , , . . . . , , . . r r mr l 1E405 1E+00 1E+01 1E+02 1E+03 1E+04 TIME (SECONDS) -l 1

m TOTAL HIGH POWER

• LOW POWER i

j 4

- - .~. ~ - ..-. - -. . . . . . .. ~ . . - . _ . ..... . - _ . - - - _ _ - . __ __

l l

l Attach. 2nt I to Westinghouse Letter NTD 94-4070 (continued) J l

Figure 952.40 3 j AP600 OSU Test Facility i Axial Linear Power Profile (Normalized) for the Model Core  !

i  !

5 I

i HEATER ROD AXI AL POWER PROFILE i 0 25 l

cc 0.2- - - - -

l 3 l e 1 7 0.15- ~~"

1 b

m 2 1 g 0.1 - -

5  :

5 \

2 0 .05- -- --

I 0

025 0.75 125 1.75 2.25 2.75 i

, ELEVAT10N (Fea) l

! NORMALIZED POWER PROFILE 0.6 1 0.5 -

5

,o4 . . . . . - . _ . . . .

k 03 ~--

i cc 02-

/

0.1 03 i is 2 2.s a ELEVAT10N (Fees) d i

-.e , , , . ,, , . . . _ . , y..._-_..-. . , , , .

- - = . ,

Question 952.41 Provide Drawings LKL 930104 (referenced in Note 5 on LKL 920200, sheet 4) and LKL 930105 (referenced in Note 7 on LKL 920200, sheet 2).

Response

The following draft drawings are provided as Enclosure I to Westinghouse letter NTD-94 4070, dated March 31, 1994:

LKL920200 Sheet 3, Revision 7, AP600 Long Term Cooling Test Model Isometric-0 Deg Side LKL920201 Sheet 6 Revision 5, AP600 Long Term Cooling Test Model Isometric 180 Deg Side LKL930112 Sheets 1-2, Revision 0, CMT/CL Balance Line Small Break LOCA LKL930lG4 Sheets 1-4, Revision 1. CMT/CL Balance Line DEG Break LOCA LKL930105 Sheets 1-2, Revision 1, DVI #1 Line Small Break LOCA LKL930106 Sheets 1-3, Revision 2. DEO DVI Break Piping Arrangement LKL940110 Sheets 1-3, Revision 0, PZR/CMT Line DEG Break Pipe Arrangement LKL930108 Sheets 1-2, Revision 1, Hot 1.eg Small Break Piping Arrangement LKL930108 Sheet 3, Revision 2 Hot Leg Small Break Piping Arrangement LKL930501 Sheet 1, Revision 0, Cold I.eg Small Break Pipe Arrangenwnt LKL930107 Sheet 1. Revision 2, Cold leg Break Spool

Nonproprietary Copy Attachment 2 to Westinghouse Letter NTD-94-4070 Information in support of Westinghouse Response to RAI 952.49 Initial and floundary Condition Data for AP600 Testing at the SPES-2 Test Facility Question 952.49 - Provide the following information on the SPES 2 test conditions:

a. Ilreak Geometry a.1. Target break mass flow at specified conditions.

Response

Figure 952.49-1 provides the break flow for a SPES-2 "2 inch cold leg break" test as calculated by the NOTRUMP computer code. Figures 952.49-2 and 952.49-3 identify the the break spool piece configuration and location.

a.2. Scaling criteria for break area.

Response

The scaling criteria used for SPES-2 is to divide the simulated plant break area by the scaling factor of 395.

a.3. Break length.to-diameter ratio.

Response

The break IJD ratio has been based on the wall thickness of the AP600 cold leg piping, which is 2.56 inches. For example, a "2-inch" break would have an L/D of approximately 1.3 (see Figure 952.49-4).

This criteria will not apply to the DVI and CL to CMT balance line DEG breaks since tiey are full guillotine breaks of the piping..

a.4. Break geometry, e.g., beveled orifice, etc.

Response

The break ori6ce will use a rounded inlet with a radius equal to the break diameter. 'Ibe L/D portion of the break will start after the inlet rounding and where the flow area is a constant. Figure 952.49-4 illustrates the break geometry.

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l Attachment 2 to Westinghouse letter NTD.94-4079 (continued)

h. Core tmwer decay h.1. Basis for core power decay, viz. exposure, fbel makeup, steady-state conditions.

Response

he basis for the SPES-2 core power decay is to simulate the heat flux vs. time from the AP600 fuel rods; including stored energy and fission product decay heat. His core power decay vs. time has been I determined based on AP600 LDFTRAN analyses. De fission product decay heat n. time is based on the ANS 1979 decay beat standant plus two sigma uncertainty. De SPES-2 heat loss compensation value (150 kw) is based on pre-operational testing and is added to the SPES-2 core power decay. Table 952.49-1 provides the SPES-2 decay heat simulation as a function of time after trip with the exception of the compensation for the SPES-2 heat losses. Becatse of the limitations of the SPES-2 heater rod mntrol system, the AP600 mre power vs. time is simulated as follows:

SPES.2 core power is maintained at 102% for 5.75 seconds aner the reactor trip setpoint is readied.

The SPES-2 power is reduced in a single step to 20% (maximum power of the continuous low power heated rod power control system) and maintained until 12.38 seconds after reactor trip.

At this time the integrated SPES-2 heated rod power is equivaler,t to 1/395 of the AP600 nuclear fuel heat input.

De SPES-2 power level is maintained at 20% (the maximum per level) until 14.5 semnds.

At this time the AP600 core power fraction of full power is 0.169; where 0.169 (4.89 MW) +

150 kw = 0.2 (4.89) and 150 kw is equal to the heat loss compensation.

From 14.5 seconds until the actuation of the first stage of ADS, the SPES 2 power decay is that identified in Table 952.49-1plus 150 kw (the hest loss compensation).

When the first stage of ADS is actuated, the SPES-2 heat loss compensation is stopped and the power decay is as show on Table 952.49-1.

h.2. Scaling hashi, e.g., how should stored energy be consklered.

Response

he observed SPES-2 facihty total heat capacity including both primary and secondary side metal and water is approximately 4700 Btu /'F. This compares with an ideal scaled heat capacity of 2700 BTU /"F (AP600 beat capacity /395). His additional heat capacity is due entirely to metal heat since the SPES-2 primary and secondary water volumes are scaled (1/395 of AP600). On the basis of pre-test analyses, the fourth stage ADS flow area was made 2,6 times larger than scaled.

isar

,. . - ~ - -

Attachment 2 to Westinghouse letter NTD 94-4079 (continued)

c. Trace heatina Should trace heating he used and if so using what scaling basis. Description of control logic

Response

he SPES-2 facility uses trace heating for both the cold leg-to-CMT and pressurizer-to-CMT balance unes to achieve preset temperatures. Power to the trace heaters is turned off following receipt of an "S" aignal and thus no scaling basis is required.

d. Initial conditiorm d.1. Pressurimr level (Based on what? Scaled gas volume? Scaled liquid volume? IIelght?)

Response

he initial pressurizer level is provided in Table 952.49-2. His kvel is based on both scaled gas volume and scaled liquid volume, with icyc1 adjustments to obtain correct liquid volume.

d.2. Initial thermodynamic conditions in primary and secondary, e.g., p.u m and ,

temperature.

Response

Initial thermodynamic conditions for the primary and semndary systems are identified in Table 952.49-2. He initial conditions are established to preserve primary system initial conditions (pressure, temperatures, flow). The semndary system pressure of 4.9 MPa (abs) was determined simply .1 to obtain the proper primary conditions. This pressure was determined by pre-test analysis such that .

when the " core outlet" temperature was 315'C (600'F) and core power was 4.9916 MWt (102%), T.

was 276*C (529'F). His pressure is lower than AP600 due to the fact that the SPES-2 steam generator ,

tube area is less than the scaled AP600 area.

d.3. Initial flow mnditions.

Response

De initial primary system flow c mditions are identified in Table 952.49-2. His flow is scaled from the AP600.

l d.4. .Wey water level or mass level?

Response 1 he initial steam generator narmw range water level is identified in Table 952.49-2. Ris initial level- lI corresponds to a reference elevation of 12.8 meters (see Figure 952.49-5, SPES-2 SG Measurement y Arrangement). At this level, the scandary water mass is approximately 160 kg per SG. l 1

d.5. Pressurizer heater level.

Response

De pressunzer internal heaters are shut off if the pressurizer level is 5,2 meters. The beaters are also' shut off on an "S" signal. The presssurizer heaters are not used for heat loss compensation.

I 15%A '

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1 Attachment 2 to Westinghouse Letter NTD-94 4070 (continued) d.6. Tank water levels, e.g., IRWST -l Remonse Initial water levels for the IRWST, CMTs and Accumulators are provided in Table 952.49-2. These levels are prototypic based on the full height scale of the test facility, i e., I to I height relationship.

d.7. Ilack pressure setpoints for breaks. ,

Remonse l All breaks and the ADS vent to atmosphenc pressure.

e. Iloundary conditions e.l. Trip points and time delays for all equipment, e.g., pressurizer heaters. S valves (CMT, IRWST, PRIIR and isolation valves), ADS, scram, turbine stop valve, secondary SRVs and PORVs, pumps, accumulators.  ;

Remonse The trip setpoints arx1 time delays are identified in Table 952.49-3.

e.2. Pump coastdown curves

Response

The SPES-2 pumps are tumed off 16.2 ~Gi; efter the S-signal. The pumps coast down to 0 rpm in 5 8 seconds, e.3. Pressurizer heater controls Remonse The pressurizer intemal heaters are shut off if the pressurizer level is $ 2 meters. The beaters are also shut off on an "S" signal. The extemal pressurizer heaters are not used for heat loss compensation.

e.4. Secondary valve closure controls

Response

This infonnation is provided in Table 952.49-3.

e.5. Core power control.

Restxmse This information is provided in the response to item b.l.

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d Attachment 2 to Westinghouse Letter NTD 94-4070 (continued)

f. ADS

f. l . liasis for design

Response

The basts for the ADS tiow area is the same as that for the break, that is, the minimum plant area is divided by the scale factor of 395. The ADS valve opening times are desenbed in Table 952.49-4 f.2. Scaling requirements for ADS orifices including taq;et mass flows at specified conditions

Response

The orifices that will be used for the ADS valve simulations will be sharp edged abrupt onfices with no inlet rounding. Table 952.49-5 provides the AP600 minimum and maximum valve areas and resistances. Table 952.49-6 provides the required saturated steam critical flow rates for the AP600 ADS control valves.

g. SRVs & PORVs Target mass flows at specified conditions.

Restxnse SPES-2 SG PORV Simulation

- The SPES-2 steam generator PORV line contains a square edged orince with a 5.2 mm diameter orifice

- Design Dow is 0.24 kg/s at 7.8 MPa SG pressure For the small break LOCA simulations, the SPES-2 steam generator PORV opening setpoint is 7.0 MPa.

SPES-2 steam generator PORV reclosure occurs at 6.5 MPa. This pressure range (6.5 - 7.0) assures that T,,w during natural circulation will remain at approximately T,,w (547 T).

SPES-2 SO Safety Valve

- 10 MPa set pressure

- SV's are 3x4 inch with a 34 mm diameter flow area The SPES-2 steam generator safety valves are set for equipment protection only. Ttrir use is not anticipated.

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l Attachment 2 to Westinghouse Letter NTD 94 4070 (continued) l Table 952.491 SPES 2 Power Decay Curve Time from trip (seconds) Fractional Power 0.0 1.02 5.75 1.02 5.76 0.2 12.38 0.2 15.00 0.1542 17.5 , 0.1300 20.82 0.1121 22.5 0.0917 25.0 0.0868 3 27.5 0.0823 30.0 0.0782 35.0 0.0710 40.0 0.0648 45.0 0.0604 50.0 0.0573 70.0 0.0479 100.0 0.0403 200.0 0.0317 500.0 0.0259 1000.0 0.0222 2000.0 0.0183 3000.0 0.0162 4000.0 0.0148 l

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. +.

Attachment 2 to Westinghouse Letter NTD 94 4070 (continued)

Table 952.49 2 SPES-2 Test Initial Condition Criteria PRIM ARY CIRCUIT Value/ Tolerance Units Heat rod power 4.9916 1 0.1 MW Pressurizer pressure 15.51 22 0 MPa abs Pressunzer level 3.78 3 038 m (~ 56% level)

Average HL/ Core outlet temperature 315.5 2 3 *C 4

Core inlet temperature 276.4 2 *C Core flowrate 23,25 0.25 kg/s Cold leg flowrate 5.8610.10 kg/s DC-UH bypass flowrate 0.18 2 005 kg/s Accumulator water level 2.33 0.10 m Accumulator water temperature 2025 *C Accumulator pressure 4.9 1 0.1 MPa abs IRWST level 8.5 0.1 m IRWST water temperature 20 15 *C PRHR supply line temperature 1751 25 *C Average UH temperature 296 5 *C Pressurizer to CMT BL temperature 340 +25/-0 *C CL to CMT BL temperature 2761 5 *C CMT level Full (0.61 kPa)

CMT temperature 20 5 *C l

SECONDARY CIRCUIT i Value/ Tolerance Units  !

SG's narrow range level 1.48 1 015 m. (-60% NR)

SG's main feedwater temperature 22617 *C SG's pressure 4.9 1 0.2 MPa abs j l

. l l

Attachment 2 to Westinghouse Letter NTD-94-4070 (conunued)

]

l Table 952.49-3 SPES 2 Test Serpoints for Cold Leg Break Matrix Tests Actuation signals, setpomts, trips and boundary condinons to be used for SPES-2 tests are reported here.

Reactor Trip and "S" Signal Trio Setpoints Reactor tnp "R" when PR pressure P-027P = 12 41 MPa abs Signal "S" when PR pressure P-027P = 11.72 MPa abs Type of operation Signal Delay Time (s) Actuation Time (s)

SCRAM R 5.75 (Table 952.49-1)

MSIV closure R 2.0 2.0 MFWIV closure S 2,0 2.0 PCP trip S 16.2 -

CMTIV open S 2.0 2.0 SFW start (+) S 2.0 --

CMT balance line trat tracing off S manual actuanon --

PRHR IV open (++) S 2.0 2.0 PZR Int. Heaters off S -- --

(+) SFW flowrate values are specified below.

(++) Passive RHR activation: also by Protection System when either SG's low narrow range level is at 5.6% of span corresponding to measured levels L.A20S/L-B20S = 0.15 m = 0.492 ft, plus a delay time of 60 s.

Startup FW isolation: the SFW will be stopped by two different trips:

a) by low T,,w trip at 514'F = 268'C measured in any one of the four cold legs (T-A012P/T B012P/T-A011P/T-B012P).

b) by high SG narrow range level at 79% of span corresponding to measured levels L-A20S = 2.1 m = 6.89 ft.

In this case the SFW will be stopped only for the SG in which the narrow range level reaches the trip of 2.1 m, while it will continue to feed the other SG. The SFW should restart if/when the norrnal SG narrow range level is restored.

Normal RHR: For Matrix Tests 2 arxi 4, the NRHR begins to inject when prirnary pressure is lower than 1.1 MPa abs with a flowrate temperature T-A02E/T-B02E = 20_+5'C. 'Ihe NRHR pump flowrate vsc primary system pressure is:

Primary pressure (MPa abs) Total Flowrate (kg/s) F A00E/F.B00E (kg/s) 1.1 0 0 1.0 0.11 0.055 0.86 0.17 0.085 0.69 0.21 0.105 0.5 0.25 0.125 034 0.28 0.140 0.2 030 0.150 0.1 032 0.i60

Attachment 2 to Westinghouse Letter NTD 94 4070 (contirtued)

Table 952.49 3 (continued)

SPES 2 Test Setpoints for Cold Leg tireak Matrix Tests ADS logic actuation versus CMT's measured levels (L-A40E/L-B40E) plus time delay:

Valve Open Valve CMT L.A40FlL-B40E Signal Actuation ADS Orifice Dia.

Volume (%) (m) Delay Time (s) Time (s)

Stage (mm) 67 4.152 30 2 sec.

First 4.370 67 4.152 125 2 sec.

Second 9.346 67 4.152 245 2 sec.

Third 9.346 20 1.192 60 2 sec.

(+) Fourth (A) 20.681 20 1.192 60 2 sec.

(+) Fourth (B) 14.624

(+) For matrix tests 5 and 6 (DVI line breaks) the fourth stage ADS actuation setpoints are:

founh (A) both 20% CMT volume (1.192m) plus 60 seccix!s, but at least 360 seconds after 67%

CMT A or B volume is reached.

fourth (B)- both 20% CMT volume (1.192m) plus. 60 seconds, but at least 360 seconds after 67%

CMT A or B volume is reached For matrix test 6 (DEG DVI break) ADS Stage larea = 3.09 mm. ADS Stage 3 area = 6.609 mm and ADS Stage 4 (B) area = 20.681 mm.

CVCS: For Matrix Tests 2 and 4, the CVCS begins to inject following the "S" signal and FZR level falls to 10%. The CVCS pump is stopped if PZR level increases to 20%.

The CVCS fluid temperature is 20iS*C; the CVCS pump flowrate vs. primary system pressure is:

Primary Pressure (MPa abs) Flowrate (F-001 A) (kg/s)!

15.5 0.034 13.8 0.040 10.3 0.050 6.9 0.060 3.4 0.070 0.1 0.080

• Test flow rates based on 1/395th scale SFWt For Matrix Tests 2 and 4, the SFW begins to inject at "S" signal plus a delay time of 2 s. The SFW temperature is T-A20Afr-B20A = 30*C (86'F). The SFW characteristics are:

SG Secondary Pressure (MPa abs.), Total Flowrate (kels) F. A20A/F.H20 A (kr]s) 0.064 0.032 7.48 0.084 0.042 7.0 6.0 0.112 0.056 0.150 0.075 4.8

4 Attachment 2 to Westinghouse Letter NTD 94 4070 (continued)

Table 952.49J (continued)

SPE54 l'est Setpoints for Cold Leg fireak Matrix Tests Other Setpoints Pressurizer PORV (ADS !st stage) opening serpoint 16.2 MPa abs Steam Generator PORV opening setpoint 7.0 MPa abs Setpoint for PR intemal heaters trip 2.0 m .

Primary cimuit safety valve opening setpoint 20.0 MPa abs Secondary circuit safety valve opening serpoint 10.0 MPa abs SPES-2 core temperature limit 590*C CMT secondary side PORV opening setpoint 6.7 MPa abs i

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- Attachment 2 to Westinghouse Letter NTD 94 4070 (continued)

Table 952.49 4 SPES 2 ADS Valve Opening Time Logic ADS AP600 ADS AP600 ADS SPES.2 Valve Stage Isolation Valve Control Valve Stage 1 actuation on CMT level of 67% ET - elapsed time 1 0 to 100% open 0 to 20 sec. ET 0 to 100% open 20 to 40 sec. ET 30 seconds ET 2 0 to 100% open 60 to 90 sec. ET 0 to 100% open 90 to 160 sec. ET 125 seconds ET 3 0 to 100% orca 180 to 210 acc. Er o io 100% open 2io to 280 sec. ET 245 seconds ET Stage 4 actuation on CMT level of 20%

4A 0 m IN % orea 0 m 30 sec. ET o m im% open 30 to 45 sec. ET m aceds ET 4B 0 to 100% oren 30 to * =c ET 0 to 10iyr. open . 60 io 75 sec. ET

o. j

Attachment 2 to Westinghouse Letter NTD 94-4070 (continued)

Table 952.49 5 Limiting AP600 ADS Valve Parameters

r l Flow Area fin') Resistance (UD)

! ADS Stage Valve flody

! Minimum Maximum Minimum Maximum

(%C)

Stage 1 Isolation gate Stage i Control globe Stage 2S isolation gate Stage 2S Control (globe) globe Stage 2D Control (gate) gate i

Stage 41 solation gate Stage 4 Control (squib) squib Stag 4 Control (gate) pate 1

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Attachment 2 to Westinghouse Letter NTD.94 4070 (continued) l Table 952.49 6 Required Critical Flows (saturated steam) for ADS Control Valves ADS Stage Minimum Flow Area Inlet Pressure Flow Rate (in') (psia) (Ib/sec) s Stage 1 Control

- (% t.) .

Stage 2S Control Stage 4 Control l

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Attachment 2 to Westinghouse Letter NTD 94-4070 (continued) l I

l Figure 952.49 1 Calculated Break Flow vs. Time for SPES-2 2 inch Cold Leg Break i

SPES 2in CLB 18 NOTRUMP TEST 3anx sua e.n eut,ured ra c,y.s l

0.8 r 1

0.6 -

<n ,

x l 0.4 I r

N 7' V '

O.2 -

l l

0 0 200 400 600 800 1,000 1,200 l TIME l l

l

,, Attachment 2 to Westinghouse I.etter NTD.94 4070 (continued)

Figure 952.49 2 SPES.2 Break Spool Piece Configuration i.

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s. _

a 43 -

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dg / -

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st i

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0- x s +--v+i /

, m b

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/ /

/

f/./ /g gy //,/,/

s". ,a sa .

o -

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Westinghouse Responses to Questk>as Concerning the Hrst SPES 2 Experiment Question 952.50 l l

What basis was used for determining the quantity of fuel rod stored heat used to pavgram the SPES-2 q heater rods? Provide the quantity and distribution of AP600 fuel red stoewi heat that was simulated.  ;

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Response

lhe SPES-2 tests start from full volume scaled power to achieve tbc desired primary and secondary conditions. l The SPES heater rods have a uniform axial power distribution. When modellag the power decay, the stored energy effects of the fuel rods, the delayed neutron effects, arx1 the decay power effects are simulated. The  ;

approach used is to have the power supply match the calculated heat Dux from the Westinghouse LOFTRAN  !

mde for an AP600 plant transient. By matching the heat flux from the nucicar rod calculation, the effects of stored energy, delayed neutron heating, and decay power were simulated. The decay power is based on the ANS j 1979 plus two sigma uncertainty. Table 952.49-1 (Attachment 2 to Westinghouse letter NTD-NRC-94-4070, I dated March 31,1994) provides the power simulated in the first test without the heat loss compensation. To compensate for the heat loss in the SPES facility, it was determined from pre-test analysis and conf!rmed from the hot pre-operational tests that the best simulation of the AP600 would ocair if the mre power was increased by 150 kw from 14.5 seconds to the first stage activation of ADS. The SPES-2 power versus time control approach is given in the response to RAI 952.49, item b.1 (Attachment 2 to Westinghouse letter NTD-NRC 4070).

Question 952.51 Ilow much mass was simulated la the SPES-2 secondary?

Response

See the response to RAI 952.49, item d.4 (Attachment 2 to Westingbouse letter NTD-NRC-94-4070).

Question 952.52 Define the basis for determining the pressurizer water level.

Response

See the response to RAI 952.49, item d.1 (Attachment 2 to Westinghouse letter NTD-NRC-94-4070).

Questk>n 952.53 How were the secondary conditions determined for the first SPES-2 test?

Response

See the response to 952.49, item d.2 (Attachment 2 to Westinghouse letter N11)-NRC-94-4070).

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m Attachment 3 to Westinglxame letter NTD 94-4079 (continued)

Question 952.54 Provkle the scaling rationales for designing the experiment and tlw SPES-2 facility so that a similar scaling rationale can be used to denne the ROSA /AP600 experiments.

Resnonse The scaling rational for designing the SPES facility and the experiments has been previously transmitted to the staff as WCAP-13277, Revision 1 (Westinghouse letter ET-NRC-93-3883, dated May 11, 1993).

Questkm 952.55 Ilow is heating by delayed neutmns simulated in the SPES 2 power decay?

Resnonse See response to RAI 952.50 (Attachment 3 to Westinghome letter N1V-NRC-94-4070).

Question 952.56 What is the basin for tlw heat kms compensation programmed into the SPES 2 heater rods? What is tlw relationship between the heat loss compensatkm assigned to the SPES 2 heater rods and the heat loss mmpensatkm fman the traa heaters?

Response

See the response to RAI 952.50 (Attachment 3 to Westinghouse letter ?UD-NRC-94-4070).

Questkm 952.57 What are the ekning setpoints for the secondary safety relief valves (SRVs) and tlw pilot +perated relief valves (PORVs)7 Resnonse See the response to RAI 952.49, item g (Attachment 2 to Westinghouse letter NTD-NRC-94-4070).

Question 952.58 Ilow Le the pump speed ramped to aero rpm?

Resnome See the response to RAI 952,49, item e.2 (Attachment 2 to Westinghouse letter ?RD.NRC-944T/0).

Question 952.59 Are the pressurizer heater rods used to compermate for heat loss fruss the SPES-2 pressurizer?

Resnome See the response to RAI 952.49, item c.3 (Attachment 2 to West!ngbouse letter NTD-NRC 94-4070).

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Nonproprietary Copy (Drawings Excluded)

Enclosure to Westinghouse Letter NTD 94 4070

' AP6N OSU Test Facility Drawings LKL920200 Sheet 3, Revision 7, AP600 Long Term Cooling Test Model Isometdc-0 Deg Side LKL920201 Sheet 6. Revision 5, AP600 Long Term Cooling Test Model Isometric 180 Deg Side 1,KL930112 Sheets 12, Revision 0, CMT/CL Balance Line Small Break LOCA LKL930104 Sheets 14, Revision 1, CMT/CL Balance Line DEG Break LOCA LKL930105 Sheets 12, Revision 1, DVI #1 fine Small Break LOCA LKL930106 Sheets 13, Revision 2, DEG DVI Break Piping Arrangement LKL940110 Sheets 13, Revision 0, PZR/CMT Line DEG lireak Pipe Arrangement LKL930108 Sheets 12, Revision 1, Hot Leg Small Break Piping Arrangement LKL930108 Sheet 3, Revision 2, llot Leg Small Break Piping Arrangement LKL930501 Sheet 1. Revision 0, Cold Leg Small Break Pipe Arrangement LKL930107 Sheet 1, Revision 2 Cold Leg Break Spool l

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