ML20070S652

Requests That Proprietary Presentation Matls from 940510 Senior Mgt Meeting on AP600 Design Certification Review Activities Be Withheld (Ref 10CFR2.790)

ML20070S652
Person / Time
Site:	05200003
Issue date:	05/12/1994
From:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Borchardt R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19304C154	List: ML20070S652 NRC-94-4132, Forwards Nonproprietary & Proprietary Presentation Matls Used During 940510 Meeting in Corvallis,Or Re AP600 Design Certification Review Activities.Proprietary Matls Withheld (Ref 10CFR9.17(a)(4))
References
AW-94-632, NUDOCS 9405240130
Download: ML20070S652 (130)

Text

_

4 sa 355 Westinghouse Energy Systems Pinstugh PennsyNarua 1$230 0355 Electric Corporation AW-94-632 May 12,1994 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: MR. R. W. BORCHARDT APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

SUBJECT:

PRESENTATIOb MATERIALS FROM THE MAY 10,1994 SENIOR MANAGEMENT MEETING ON AP600 DESIGN CERTIFICATION REVIEW ACrlV1 TIES

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 repon. In conformance with 10CFR Section 2.790, Affidavit AW-94-632 accompanies this application for withholding setting forth the basis on which the identified proprietary -

information may be withheld from public disclosurc.

Accordingly, it is respectfully requested inat the subject intoncstion which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's regulations.

Correspondence with respectfo this application for withholding or the accompaapg affidavit should reference AW-94-632 and should be addressed to the undersigned.

Very truly yours, N. J. Liparuto, Manager Nuclear Safety Regulatory And Ucensing Activities

.__. /nja .__

cc: Kevin Bohrer NRC 12H5 17M A 9405240130 940512 PDR ADOCK 05200003 A pgg __

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AW-94-632 )

I AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:

ss COUNTY OF ALLEGHENY:

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

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Brian A. McIntyre, Manager Advanced Plant Safety & Licensing Sworn to and subscribed before-me his M day

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of C' .1994

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Notary Public NcMar.a Scal Pa.o Mat P.Tyie, No'ay PLblic 1 Montvede Berc./ib /wy Cconty l My Convrusajan Expireo Nov.4,1996 j Marnber, Pennryrvana/sxxman at N.tarus 1 l

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1735A 1

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AW-94-632 (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 (bX4) 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 frorn 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, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.

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

1735A 1

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AW-94-632 (a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, 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 capacitics, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.

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

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

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

(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.  ;

l (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.

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4 AW-94-632 (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 competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

(c) Unrestricted disclosure would jeopardize the position of prominence of 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.

I

,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-94-4132, May 12,1994, being transmitted by l Westinghouse Electric Corporation (E letter and Application for Withholding Proprietary Information from Public Disclosure, N. J. Liparulo (E, to l l

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.

1735A

AW-94-632 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 tecF .ical and licensing approaches for the AP600 that will ultimately result in a certified design.

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

Further this information has substantial commercial value as follows:

(a) Westinghouse plans to sell the use of 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.

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AW-94-632  !

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.

I Further the deponent sayeth not. i l

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1735A

I WESTINGHOUSE ELECTRIC CORPORATION WESTINGHOUSE /NRC SENIOR MANAGEMENT MEETING AP600 Design Certification

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A. 2 5k pN f7 R

May 10,1994 L I

Corvallis, OR f i

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AGENDA g 9:00 Welcome and introduction W/OSU 9:10 Design Certification Project Overview R. M. Vijuk 9:30 Design Certification Program Discussion items B. A. McIntyre 10:30 AP600 Test / Analysis Program Status L. E. Hochreiter/E. J. Piplica 12:00 Lunch 1:00 SPES-2 Integral System Test Status E. J. Piplica 1:30 OSU Integral System Test Status J. N. Reyes/M. Mahlab 2:30 Commitments / Actions All 3:00 Break 3:30 Tour of OSU Test Facility l

1 t

_ _ _ _ _ _ _ _ _ - _ - - - - - _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ - _ = _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ __. . - - - _ - _ _ _ _ _ _ - _ _ _ = - _ - _ - _ - _ - _ -

!N Design Certification Project Overview Bob Vijuk AP600 Design Certification Project Manager .

DESIGN CERTIFICATION PROJECT OVERVIEW g'

- Design Status

. Review Status

. Test Program Status

. Schedule

o -

DESIGN CERTIFICATION PROJECT OVERVIEW lg DESIGN STATUS

. Ideal situation is no changes to design

- Changes to the design have occurred as a result of:

- Industry review

- Test program results NRC review

- These changes were thoroughly thought out and were communicated to NRC

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

DESIGN CERTIFICATION PROJECT OVERVIEW DESIGN STATUS

- The changes should have a positive impact on the NRC review and review schedule, as they:

Simplify design and operation Increase safety margin Reduce uncertainties

- Eliminate or reduce impact of identified concerns

- Cumulative impact of design changes should simplify and accelerate the review 5

l DESIGN CERTIFICATION PROJECT OVERVIEW g REVIEW STATUS Activities geared to support DSER

- Responses to RAls Approximately 200 RAls received in April '94

- Total of 1600 RAls; approximately 1300 responses to date

- March 14th Agreement Non-testing RAI responses by June 30,1994 Testing RAI responses by July 31,1994

- Focused meetings

REQUESTS FOR ADDITIONAL INFORMATION L$

2000 - - - - - - - - - - - - - - ----- - - - -

1500 - - - - - - - - - - - - -

---

f une J 30th 2

M .'

v d n .7 1000 -- - --- - - - - - - - - --- - - - - - -

-X 500 - -- ---- - -- - - - - - - - - -- -

0 -- - -- *- - - - ' - - - - - ' - ' ' ' ' -- ' --

06-Apr-92 15-Jul-92 23-Oct-92 31-Jan-93 11-May-93 19-Aug-93 27-Nov-93 07-Mar-94 15-Jun-94 23-Sep-94 DATE

+ RECEIVED ANSWERED 7

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DESIGN CERTIFICATION PROJECT OVERVIEW Yg!

TEST PROGRAM STATUS

- Significant progress towards resolution of outstanding test issues April 7,1994 agreements

- Management attention required to close remaining issues

- Test program actively underway

- CMT and SPES-2 matrix testing underway

- OSU matrix testing to start ahead of schedule ADS Phase B construction on-schedule

- Results to-date are as expected

3 8 AP600 TESTING PROGRAM g) 100 90 -

TEST RUNS rn 80 -

h M

70 -

74 82 f  : * *~-

• H 60 66 50 -

54 g 40 - 44 H 30 -

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JAN (94) 1 MAR MAY i

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APR SEP JUN NOV

.i i AUG OCT JAN (95) i i I DEC MAR MAY TIME FEB APR Includes CMT, OSU, sSPES-2, and ADS Test __ Program Plan Objective (u

__._ Actual Test Run Status (through 4/30/94)

_ _ _ _ _ _ _ _ _ - - _ _ - _ _ _ - - _ _ _ - - _ - - _ . . , ----2

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l DESIGNiCERTIFICATION PROJECT OVERVIEW ]g SCHEDULE

- Detailed schedules developed and submitted that incluc;e:

- . Discrete logic between related activities

- Current testing status Intermediate deliverables  ;

- .Results optimized-testing order

- Single DSER

• December 1994 FDA

• June 1996  :

- SECY-94-117 Split DSER Unexpected 11 month FDA delay ,

- Serial process

- Recovery plan is essential .

- Communication must be improved I

__iU_________.________ _ _ _ _ - - -____._2 __. ._ __ _ _ _ . _____er ___ __ m - _._ _ _.__ _ _ _ _ _ _ ____ __._ r- _ _-__ _v _ _ _ ___ ______ -___ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ l_1._.______-__

s e AP600 DESIGN CERTIFICATION SCHEDULE g

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Design Certification Program Discussion issues Brian McIntyre Manager, Advanced Plant Licensing and Safety

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

AP600 DESIGN CERTIFICATION REVIEW STATUS E.

RAIS

- 1697 RECEIVED v

- 187 IN APRIL

- 102 IN MAY

- 1286 RESPONSES PRA

- ISSUES MEETING 2/15/94 i

INEL PRESENTED AREAS OF CONCERN RAls IN FOUR TO SIX WEEKS

- WESTINGHOUSE HAS REQUESTED MEETING

- KEY TO RTNSS IMPLEMENTATION REVIEW 030sB.ut/2

4.

- AP600 SSAR/PRA NRC Requests for AdditionalInforrnation Source Summary of RAls Received to Date .

From Review Areas Within the NRC Prwed 0596,94 h

No. et Percert No. of Percent of Antsgo Review Areas Rale of Total Meepensee Group Tumeround 100 General  ! 11 l 1! 10 l 91 l 96 210. Mecherucel Enemeering  ! 110 l 7 ' 28 l 25 i 92 220. Structural Engmeanne j 90 l 4 52 l 58  ; 64 230. seemeingy l 96 i 4 51 1 54 l 72 231. Geology 1 32 l 2 l 14  ; 44

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83 240. Hyerstegic Engmeeting . l 01 0 i 0 i "

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241. Geotecimical Engmeeting l 0l 01 0 [ l 250 Innerviosinspecean l 29 ; 21 29 l 100 1 68 251. Component integHey  ; 32 l 2 i 32 j 100 l SS 252.Maiortain Appacemen  ; le t e: 14 l 100  ; e2 2e0.Quemy Assurance i 22 i t i to l es  : 77 270. Erwerenmental Quencanon i 31 0t 3 100 i te

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271. seemic a Dynems Load Quemcemen l 0 : 0 0 '

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200. Fire Preneseen 0 0 0 2st .chemisel Technoingy to 1 is l 100 64

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311.sa Anasyen 1 0 0 0 i  ;

320. Arnaruet a Economic Analysen l 03 0! 0 l l 410. Ausery systeme  : 10s a 7l 10s I e i 10s 4ao . insensnaressen a careres syneems i 124 i s;l tas I e '

s es .Elseets Power syseems  : as i s 73 as s2 440. Reacter synesmo j 84 1 5, si et ,

as dec. Aeeidere Evalussen i e: 1 :l e 100 i es

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41. Mensoreency  : 0 0 l 0 ,l l

4so. Etnumre Tremenere I le 1 ; te ll 100  : 110 470 Rasshamedimpoet  : 15 l t i t5 100  ; 74 .

471 Reassen Preescuen l 21 l 1l 21 100 l 82 4e0.corestenere syenome  : 7e n s e i s2 l 70

40. Fuses l 10 1.l 0 '

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e10.operener useruins 1 0 i 0t o ,l' M. Human Syenome traertuose l So j 0l Go 100 , 102' 830. Tech Spee# TAP  ! 9l 1( 0 ,; 100 108 7:D. Rosetey 4 Risk Assessment l 27s l 17 l 201 i SS 84 - ,,

730. Geneste lemuse 0! 0( 0 i, j 930.selepugls 4 l 0' 2 to l 73 seo.nas.eeneres  ; O! 0 0 t est .nsa.cernemenent systeme l 7i 0 , 7 100 e4 es2.nas.nassear svuname  ! es i 4 ; 54 '

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AP600 DESIGN CERTIFICATION REVIEW STATUS $...

RTNSS

- 9/23/93 SUBMITTAL STAFF DEVELOPING REVIEW GUIDANCE

- RAls RECEIVED FROM SEVERAL BRANCHES WESTINGHOUSE /NRC AGREE ON ONE SYSTEM BY NOVEMBER 1994 030sBAW3

AP600 DESIGN CERTIFICATION REVIEW ,

STATUS g?

TEST PROGRAMS I Frequent And Detailed interactions With NRC Staff l

- Meetings Have Been Hold On Each Test Program (Facility Design Reviews, Test Matrix Reviews, Test Results)  ;

- Responsee Have Been Provided To Staff Requests For Additional Information (RAl's) c . Wooldy Phone Calls On Test Program Schedules And Status t

- Hundreds Of Test Program Documents Foswarded To NRC Staff l

- NRC Staff Have Visited Test Sites To Witness Test Freparations And Operations

- Suggestions Of NRC Staff And Consultants Have Seen integrated into The Test Program

- Issues Are identified And Actions Are Taken To Reach Resolution Meeting Held 4/7/94 To Close Out Remaining items 03068And/4

, _ _ , , , , . , w y _______s_ _ _ ______

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AP600 DESIGN CERTIFICATION REVIEW- geg TESTING STATUS ..

1 SPES 2 l -

TWO MATRIX TESTS COMPLETED

- CMT -l ELEVEN MATRIX TESTS COMPLETED OSU READINESS REVIEW 5/11-12 MATRIX TESTING EXPECTED TO START 5/20 ADS CONSTRUCTION ACTIVITIES WELL UNDERWAY-

' FACILITY COMMISSIONING TESTS TO BEGIN 6/21/94

- MATRIX TESTING TO BE COMPLETED BY 10/28/94 0308BAM/S

AP600 DESIGN CERTIFICATION SCHEDULE p.a7 WESTINGHOUSE - MARCH 28,1993 .._  :

REQUIRED BY 3/7 NRC LETTER INCLUDES ALL ACTIVITIES NECESSARY FOR

- DSER FSER FDA ACCOUNTED FOR DELAY IF OSU TESTING PROGRAM TESTING PROGRAM LINKED TO REVIEW PROCESS INTERMEDIATE DELIVERABLES QUICK LOOK REPORTS l l

TESTING ORDER REARRANGED NRC TEST REVIEW /SER INCLUDED NRC ACTIVITIES AND TIME SPANS FROM 93-097 INCLUDED OMSBAM/6

e AP600 DESIGN CERTIFICATION SCHEDULE ..

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_ _ _ _ _ _ _ _ . . _ _ _ _ . _ . ~ . , ~. .,__m, . .

var NRC SECY-94-117 ..-

-DELAYS ATTRIBUTED SOLELY TO TESTING DELAYS COMPARED TO SECY-93497 DELAY OF 6 MONTHS IN FIRST DSER DELAY OF 14 MONTHS IN FSER DELAY OF 15 MONTHS IN FDA COMPARED TO WESTINGHOUSE 3/28 SCHEDULE FIRST DSER AT SAME TIME SECOND SERIAL DSER ADDED DELAY OF 10 MONTHS IN FSER DELAY OF 10 MONTHS IN FDA 03cs8A M/9 -

i SECY-94-117 .m p!.i WESTINGHOUSE OBSERVATIONS

$@t-5/95 ONLY INPUT FROM WESTINGHOUSE 3/28 SCHEDULE

- PROCESSIGNORED NO ATTEMPT TO ESTABLISH PARALLEL ACTIVITIES TO REDUCE DELAY 1400 RAls RECEIVED ARE ONLY 2/3 OF TOTAL FOR DSER IN 11/94

- IMPLIES 700 MORE RAls FOR DSER

- NOT CONSISTENT WITH 3/14 SENIOR MANAGEMENT MEETING 6/30 NONTESTING RAI CUTOFF 7/31 TESTING RAI CUTOFF 0308BAM/10

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Opportunities for improvement in SECY-94-117 schedule l 1.- Start non-testing portions of FSER earlier .

2. Accelerate test program reporting to facilitate early review

3. Take full advantage of parallel tasks i

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AP600 TEST AND ANALYSIS PROCESS g '

Test needs identified by engineering and analysis groups

- Provide for proper model/ correlation development and verification

- Validation of the system codes with integral tests

g .. O AP600 TEST AND ANAL YSIS PROCESS' ig UCEPiSING E NE NG SAFETY ANALYSIS G R G AP600 TEST ENGINEERING TESTSPECIFICATION DRAFT 4.

REVIEW BY PARTIES REVISED TEST ,

DRAFT TEST SPECIFICATION MATRIX SIGN-OFF FINAL TEsTSPECIRCATION PRELIMINARY TEST MATRIX d

, o AP600 TEST AND ANAL YSIS PROCESS ig SCALING ANALYSIS '_ TEST DESIGN REVIEW ,

ENGINEERING BY PARTIES j

ANALYSIS ISSUES  :

TESTMATRIX REVIEW  :

NEEDS PRE-OPERATIONAL TESTS  : INPUT TO FACIUTY MODELS MATRIX TESTS '

A S 1P DATA REPORTS (DATA USERS)

UCENSING .

SYSTEMS DESIGN SAFETY ANALYSIS l E EER G

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AP600 TEST AND ANAL YSIS PROCESS g v

DATA REPORTS o

HEAT TRANSFER, FLOWS, POST-TEST DATA ANALYSIS CORRELATIONS, ANALYSIS C.

WITH CODES DATA ANALYSIS -

MODEL REPORT IMPROVEMENTSIF NEEDED o

u CODE VAUDATION  :

FREEZE CODE REVISIT SSAR ANALYSIS IF NECESSARY, REVISE SSARANALYSIS

j e 4

AP600 TEST AND ANALYSIS PROCESS g .

- Specific model/ correlation needs were identified for each specific  ;

transient-type:-

l Large break LOCA Small break LOCA

- Transient analysis

- Containment analysis -

Long-term cooling ,

. The specific differences for the AP600 were examined relative to current W PWRs and the safety analysis computer codes used'for the L the SSAR

- The needs for systems tests were also evaluated to address systems interactions, mass distributions and multiple breaks i

4 l.

AP600 TESTAND ANALYSIS PROCESS [g Code model validation process and analysis - process - systems codes

- Code already validated for current PWR use; the program is to extend their validation.to passive plant design

- Key models are being examined by separate offects tests

- CMT, wall / interfacial condensation

- ADS, Critical flow,24 pressure drop, sparger behavior, condensation

. Integral systems tests will validate the systems performance of the codes and reveal if compensating effects are present

- SPES-2, high pressure blowdowns

- OSU, Low pressure blowdowns, long-term cooling performance

- Integral systems tests will also address NRC concerns expressed in SECY-92-30

l AP600 TEST AND ANALYSIS PROCESS g,. ,

Process - Containment Codes ,

. The containment code is WGOTHIC j

- Separate effects tests have been run (heated plate test, University of Wisconsin experiments, etc.) as well as small and large scale integral

- tests

- Completed large scale integral tests being examined .

Non-condensible behavior He (H2 ) effect, distribution  :

Transient performance of code

- Different break location, geometry i

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)g AP600 TEST AND ANALYSIS PROCESS 1

1

- An example of the process used to identify safety analysis computer code ,

validation needs is for Long-Term Cooling analysis (LTC)

- Code is'WCOBRA/ TRAC .

?

- Objective is to show that phenomena are understood with OSU tests and WCOBRA/ TRAC analysis, then develop simpler model Develop LTC WCOBRA/ TRAC model from WCOBRA/ TRAC OSU model, i.e., simplify

. - LTC process identified the key phenomena to be examined, data needs for computer code model and system validation e

1 i

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AP600 TEST AND ANALYSIS PROCESS g Long-Term Cooling Processes Long Term Cooling AP600 Uniqueness Long-Term Cooling AP600 Specific Comments Process w.r.t. W Plants Model Verification Validation Needed (Does it Exist?)

- Natural Circulation - Loop 24 natural Yes Yes, systems data Frictional / elevation circulation needed on AP600 heads should be specific geometry properly scaled to insure correct flows

- Multiple breaks No

- CMT delivery in No Downcomer

- Mass distribution Code can handle multiple breaks and flow paths

- Long-term core Gravity feed natural No, not in AP600 Yes, Integral Same as above heat removal ' circulation, possible configuration systems tests flooding, CCFL needed l effects 1

- Long-term steam Yes, ADS reduced Yes, FLECHT- None AP600 should be generator heat flow to SG SEASET, ROSA-IV, less sensitive to SG removal LOFT, semiscale behavior l

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AP600 TEST AND ANALYSIS PROCESS !g?

AP600 Safety Analysis Codes, Technology Features and Capabilities Computer Code Single Phase, 1-D Drift Flux 3-D Vessel Model Homogeneous Flow Separate Two-Phase Flow Model WCOBRA/ TRAC ->

NOTRUMP >

LOFTRAN/LOFTTR2 >

-> Increasing technology level l

_ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ p ______

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• AP600 TEST AND ANAL YSIS PROCESS g Relationship between basic research tests, component separate effects tests and integral tests for AP600 containment BASIC RESEARCH TESTS I

SEPARATE EFFECTS NTEGRAL SYSTEMS COMPONENT TEM I ,

TESTS DATA, CORRELATIONS, MODELS M llTERATURE Iden6fy and captuto Examlas phenomena on phenomena on small scale larger scale Exarnine the Inter-relationehlp of different phenomena at Hardwrero, geometry more dfferent scalee AP600 specific Develop boundary conditions for ple d analyels 1

b

_=_-_-______-_-_________-____-______________l__ _ . _ - _ _ - . . - - - _ _ _ _ _ _ .

AP600 TEST AND ANALYSIS PROCESS }g Model development and verification process for code validation CODE MODE  :

• Basle Reesarc T e 1

SEPARATE EFFECTS TESTS GOOD "-

AGREEMENT 7 Yes NTEGRAL SYSTEMS EFFECTS TESTS (sm OSU, LST)

G000 "

AGREEMENT 7 Yes Confirm - SSAR ANALYSIS

O: O AP600 TEST AND ANALYSIS PROCESS {g WCOBRA/ TRAC Verification with separate effects test and validation with integral systems tests i

CORE MAKEUP TANK TEST Interfacial Heat 14ese Transfer SPES-2 HIGH PRESSURE Wall Condenention NTEGRAL SYSTEMS Recirculation TESTS Mixity FlashingNolding OSU LOW PRESSURE NTEGRAL SYSTEMS TESTS 4

DATA, CORRELATIONS, Code / Process Validation MODELS IN

. UTERATURE 2 Phase Pressure Drop ChokedfSubconic Flow Choke Pointo / Locatione Proeourtzer (Storage Vessel)

Mene Flow / Fleshing

o .

AP600 TEST AND ANALYSIS PROCESS g NOTRUMP Verification with separate effects test and validation with integral systems tests CORE MAKEUP TANK TEST SPES-2 HIGH PRESSURE Interfacial Heat / Mass Transfer INTEGRAL SYSTEMS Well Condensation TESTS

. Rectrculation Mixing OSU LOW PRESSURE FlashingNolding INTEGRAL SYSTEMS TESTS Code, Process Va!!dation DATA, CORREL.Am MODELS IN UTERATURE 2 Phase Proesues Drop Choked / Subsonic Flow Choke Points / Locations Proesurtzer (Storage Vessel)

Maes Flow 1 Flmehing f

AP600 TEST AND ANALYSIS PROCESS g LOFTRAN Verification with separate effects test and validation with integral systems tests CORE MAKEUP TANK nSTS W*b N SPES4 HK3H PRESSURE Gravtty Drain Effects NTEGRAL SYSTEMS TESTS Steam On Tube Rupturs PRHR TESTS Primary SIdo Heat Transfer Outelde Surface Heat Transfer in IRWST ,

AP600 TEST AND ANALYSIS PROCESS g Research and Engineering tests input to LOFTRAN Code on TESTS Itenned Conolation for Low Flow feOH ltERTIA ROTOR r LOFTTR2 of u vERsov oF TENNESSEE VESSEL MDCNG TESTS Scoping Tees on Vessel

.o e AP600 TEST AND ANAL YSIS PROCESS g Models, correlations and input conditions developed from component separate effects tests and engineering tests NEATsD PtATE TESTS

1. 8 for correlotto  %

s CONT. ANNULUS PRESSURE DROP TESTS ant Geometry Form and friction loesso in mirmleted containment CONTA9 MENT annulus for air flow path ANALYSIS godt6cos WND TUNNEL TESTS ydnel M ON AP600 SITE goo*

Preesure distributions D C

around air inlet ducts 1.cok for recycled air s

/

effects LARGE SCALE WATER DISTRBUTION TESTS Verfflestion of pesolve methods to spread water on contelnmerit surface to mexirntro coverage

__m.. ____- _; -

AP600 TEST AND ANALYSIS PROCESS Pg Documentation plan for tests / analysis

- Each DC test will have issued:

Data report

- Data analysis report

- A code verification report will be issued for:

WCOBRA/ TRAC l -

NOTRUMP Individual code comparisons LOFTRAN/LOFTTR2 to ADS, CMT, SPES-2, OSU WGOTHIC and Containment tests t

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M AP600 Test / Analysis Program Status E.J. Piplica Manager, AP600 Test Engineering w - - _ . , _ _-_______m m u - m ~m -

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PASSIVE CONTAINMENT COOLING SYSTEM TESTS muuw,,

PASSIVE CONTAINMENT COOLING SYSTEM TEST STATUS

. TESTING COMPLETED; TEST DOCUMENTATION UNDERWAY LARGE (1/8TH) SCALE HEAT TRANSFER TEST 10 QUICK LOOK REPORTS COVERING 16 TESTS HAVE BEEN SUBMITTED'TO THE NRC FOR REVIEW 3 REMAINING QUICK LOOK REPORTS ARE IN PROGRESS

- WATER DISTRIBUTION TEST FINAL TEST REPORT SUBMITTED TO THE NRC FOR REVIEW

- WIND TUNNEL TESTS FINAL TEST REPORTS FOR PHASE 4A AND 4B COMPLETED AND UNDER REVIEW ,

ALL PCS TESTLDOCUMENTATION WILL BE SUBMITTED TO THE NRC BY AUGUST,1994 ttMD.WPF -

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-O 'e CMT TEST MATRIX  !!N1 a 1 CATEGORY 1 TESTS 1

- SERIES 100 TESTS

- CMT WALL CONDENSATION WITH AND WITHOUT NONCONDENSIBLES (N 2)

- SERIES 200 TESTS

- CMT WALL AND WATER SURFACE CONDENSATION

- SERIES 300 TESTS

- CMT DRAINDOWN AT CONSTANT PRESSURE CATEGORY 2 TESTS

- . SERIES 400 TESTS i

- CMT DRAINDOWN DURING DEPRESSURIZATION

- SERIES 500 TESTS

- NATURAL CIRCULATION FOLLOWED BY DRAINDOWN AND DEPRESSURIZATION i

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CORE MAKEUP TANK TESTS a TESTING PLAN

- RUN HIGH PRESSURE CATEGORY 1 TESTS

- Il 3 TALL STEAM FLOW METERS

- PERFORM LOW PRESSURE CATEGORY 1 TESTS

- PERFORM LOW PRESSURE CATEGORY 2 TESTS

- REMOVE STEAM FLOW METERS

- PERFORM HIGH PRESSURE CATEGORY 2 TESTS 04/27/94D.WPF

.. # 6 CMT TEST STATUS _

PRE-OPERATIONAL TESTING COMPLETED MATRIX TESTING UNDERWAY MATRIX TESTING BEGAN ON 2/15/94

- HIGH PRESSURE CATEGORY 1 TESTS COMPLETED

- STEAM FLOW METERS INSTALLED

- LOW PRESSURE CATEGORY 1 TESTS INITIATED

- SERIES 100 TESTS COMPLETED

- SERIES 200 TESTS UNDERWAY

a. ,

CMT TEST STATUS }

TEST DOCUMENTATION ON-GOING

- TEST SPEC REVISED FOR CMT/PZR BALANCE LINE DELETION

- SCALING REPORT COMMENTS ARE BEING ADDRESSED

- OPERATING PROCEDURES FOR SERIES 100,200 & 300 ISSUED

- PRE-OPERATIONAL TESTING QUICK LOOK REPORTS PREPARED, UNDER REVIEW

- SERIES 100 QUICK LOOK REPORT STARTED-APOVER1 WFF

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AUTOMATIC DEPRESSURIZATION SYSTEM TEST PLANS / STATUS 4

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- FULL SCALE SIMULATION OF THE ADS SYSTEM:

LOOP SEAL ADS VALVE PIPING PACKAGE DOWNSTREAM PIPING SPARGER

- QUENCH TANK GEOMETRY:

- DIAMETER 25 FEET

- WATER LEVEL 24 FEET

- SPARGER ARMS LOCATED 9.5 FEET BELOW WATER LEVEL APOYEtt WFf

FIGURE 1 DESIGN CERTIFICATION. TESTS

- ADS; PHASE B TEST VALVE PACKAGE CONFIGURATION 1

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Blowdown Fluid ADS Simulation AP600 Pressure Comments Simulated Stage 1 open ~ 2250 to 400 psig Maximum flow Saturated Steam resistance simulated.

from top of -

Stages 1 and 2 open ~ 800 to 100 psig Obtain 1$ T/H data.

supply tank Stages 1 and 3 open ~ 500 to 50 psig Stages 1,2, and 3 open ~ 500 to 50 psig Stage 1 open ~ 2250 to 400 psig Maximum flow Saturated water -

resistance simulated.

from bottom of -

Stages 1 and 2 open ~ 1200 to 100 psig 12-inch gate valve supply tank P '" "

Stages 1 and 3 open ~ 500 to 50 psig an of 24 ja'ta.

Stages 1,2 and 3 open ~ 500 to 50 psig Stage 2 open ~ 2235 psig (inadvertent opening at full power)

- Stages 1,2 and 3 open* ~ 500 to 50 psig Minimum flow resistance Saturated water simulated. Maximum from bottom of ~ 500 to 50 psig flow / minimum quality for Stages 1,2 and 3 open supply tank max loads on sparger Stages 1 and 2 open* ~1200 to 100 psig and quench tank.

- Quench tank water Stage 2 open* ~ 2235 psig initially at 212 F

l ADS PHASE B TEST STATUS Lb PROCUREMENTS COMPLETE

- VALVES SHIPPED AND ON-SITE

- ALL PIPING AND FITTINGS OBTAINED DAS SHIPPED AND INSTALLED q ALL INSTRUMENTS AVAILABLE CONSTRUCTION PROGRESSING VALVE PIPING PACKAGE SUPPORTS INSTALLED l VALVE PIPING PACKAGE BEING FABRICATED SPARGER AND PEDESTAL INSTALLED IN QUENCH TANK SATURATED WATER SUPPLY LINE BEING INSTALLED DAS IS FUNCTIONING AND UNDERGOING CHECKOUT AND VAllDATION CONSTRUCTION COMPLETION AND FACILITY TURNOVER SCHEDULED FOR JUNE 21

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SPES-2 INTEGRAL SYSTEMS TEST THE SPES TEST MATRIX WILL ADDRESS:

- SMALL BREAK LOCA SIMULATIONS

- BREAK SIZE, LOCATION, INTERACTIONS WITH NON-SAFETY SYSTEMS

- STEAM LINE BREAK

- INTERACTIONS WITH PASSIVE SYSTEMS, IF ANY

- STEAM GENERATOR TUBE RUPTURE DESIGN BASIS WITH/WITHOUT ACTIVE SYSTEMS TO MITIGATE DESIGN BASIS WITH ADS ACTUATION APOVER1 WPF

SPES-2 INTEGRAL SYSTEMS TEST STATUS PRE-OPERATIONAL TESTING COMPLETE INCLUDED INADVERTENT ADS ACTUATION FROM FULL POWER ,

MATRIX TESTING

- MATRIX TESTING BEGAN FEBRUARY 9,1994

- AN ElGHT WEEK DELAY DUE WAS INCURRED TO REPAIR FAILED GASKETS AND' REPLACE THE UPPER SUPPORT PLATE IN THE POWER CHANNEL THE REFERENCE MATRIX TEST, A 2-INCH COLD LEG BREAK WAS PERFORMED FOR THREE DESIGN CONFIGURATIONS:

. - THE.SSAR DESIGN

- THE REVISED DESIGN AS PRESENTED TO THE STAFF OF FEBRUARY 22-

-THE REVISED DESIGN WITH THE CMT/PZR BALANCE LINE-DELETED ,

- THE MOST-RECENT MATRIX TEST WAS SUCCESSFULLY PERFORMED ON

- MAY 6,1994, A'1-INCH COLD LEG BREAK il$aD.t?F

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4 DESIGN CERTIFICATION TEST ISSUES .

E. J. Piplica, Manager Test Engineering iuMW

m -.--- -

9 9

-CORE MAKEUP TANK TEST - NRC ISSUES -

TEST MATRIX / INSTRUMENTATION TEST MATRIX MODIFIED ADDITIONAL INSTRUMENTATION INSTALLED SCALING ANALYSIS SCALING REPORT ISSUED FOR NRC REVIEW WESTINGHOUSE IS RESPONDING TO NRC COMMENTS ON THE SCALING REPORT NRC ISSUES HAVE BEEN ADEQUATELY ADDRESSED WESTINGHOUSE HAS THE ACTIONS TO PROVIDE REVISED CMT TEST MATRIX AND RESPOND TO NRC COMMENTS ON CMT SCALING REPORT

8 4 SPES-2 INTEGRAL SYSTEMS TEST - NRC ISSUES SGTR LEADING TO ADS ACTUATION

- STAFF CONCERN IS WITH ADS OCCURRING DURING A SGTR AND THE RESPONSE OF THE PASSIVE SYSTEMS DURING THIS SCENARIO

- ANALYSIS INDICATES THAT MULTIPLE TUBE RUPTURES WILL NOT ACTIVATE ADS

- WESTINGHOUSE HAS AGREED TO PERFORM A SGTR TEST WITH FORCED ADS ACTIVATION AND DELETE THE MULTIPLE SGTR TEST

- STAFF AGREED THIS APPROACH IS ACCEPTABLE STAFF TO PROVIDE A RECOMMENDATION FOR THE TIMING FOR MANUAL ADS ACTUATION IN THE TEST tisM=o8

SPES-2 INTEGRAL SYSTEMS TEST - NRC ISSUES (CONT'D)

STATION BLACKOUT FOLLOWED BY ADS ACTUATION STAFF IS CONCERNED WITH UNIQUE T/H PHENOMENA

- WESTINGHOUSE HAS PERFORMED STATION BLACKOUT ANALYSIS AND CONCLUDED THAT THE RELEVANT PHENOMENA ARE ALREADY COVERED BY THE SPES-2 TESTS STAFF IS AWAITING RESULTS OF INEL CALCULATIONS TO CONFIRM WESTINGHOUSE POSITION STAFF HAS THE ACTION TO REVIEW WESTINGHOUSE SUBMITTALS l

AND THE INEL CALCULAT!ONS

( -

THIS ISSUE REMAINS OPEN UNTil NRC REVIEW IS COMPLETE t tsra wys l

agaas SPES-2 INTEGRAL SYSTEMS TEST - NRC ISSUES (CONT'D) $!!!P.f'.!

ATWT CORE POWER RESPONSE CANNOT BE SIMULATED IN SPES-2 PLANT CONDITIONS AND PHENOMENA WILL BE ADEQUATELY ADDRESSED IN SPES-2, OSU AND CMT TESTS ATWTS RESPONSE HAS BEEN ANALYZED AND SUBMITTED TO THE STAFF STAFF IS AWAITING RESULTS OF INEL CALCULATIONS TO CONFIRM WESTINGHOUSE POSITION STAFF HAS THE ACTION TO REVIEW WESTINGHOUSE SUBMITTALS AND THE INEL CALCULATIONS THIS ISSUE REMAINS OPEN UNTIL NRC REVIEW IS COMPLETE

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4 SPES-2. INTEGRAL SYSTEMS TEST - NRC ISSUES (CONT'D)

NON-CONDENSIBLES

- NITROGEN IS USED IN THE ACCUMULATORS AND IS ALLOWED TO

! .' ENTER THE RCS FOLLOWING- ACCUMULATOR INJECTION HYDROGEN IS NOT A CONCERN AS A~ RESULT OF THE DELETION OF THE CMT/PZR BALANCE LINE 4

I

- THIS ISSUE IS ADEQUATELY ADDRESSED BY THE DESIGN CHANGE tum-pt t

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OSU INTEGRAL SYSTEMS TEST .NRC ISSUES 4

4 f SIMULATION OF HIGHER RISK SHUTDOWN EVENTS STAFF ASKED FOR CLARIFICATION ON THE AP600 RESPONSE TO SHUTDOWN EVENTS AND-WHETHER TESTS SHOULD BE RUN AT OSU TO SIMULATE THESE EVENTS

- WESTINGHOUSE MET WITH THE STAFF ON MARCH 10TH TO SPECIFICALLY DISCUSS AP600 RESPONSE TD SHUTDOWN EVENTS .!

t

- STAFF CONCLUDED THAT TESTS ARE IN PLACE AT OSU TO PROVIDE ADEQUATE INFORMATION TO QUALIFY THE CODES ,

THIS ISSUE IS ADEQUATELY ADDRESSED .

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OSU INTEGRAL SYSTEMS TEST - NRC ISSUES (CONT'D)

EFFECTS OF HYDROGEN AND NITROGEN NITROGEN IS USED IN THE ACCUMULATORS AND IS ALLOWED TO ENTER THE RCS FOLLOWING ACCUMULATOR INJECTION t

- HYDROGEN IS NOT A CONCERN AS A RESULT OF THE DELETION OF THE CMT/PZR BALANCE LINE THIS ISSUE IS ADEQUATELY ADDRESSED BY THE DESIGN CHANGE i I IISMM 5

s OSU INTEGRAL SYSTEMS TEST - NRC ISSUES (CONT'D) ,El l

CAPABILITY OF PERFORMING SGTR AND MSLB

- OSU CURRENTLY DOES NOT HAVE THE FULL CAPABILITY TO r PERFORM SGTR AND MSLB TRANSIENTS

- HOWEVER, THIS CAPABILITY HAS NOT BEEN PRECLUDED

- IN THE EVENT SPES-2 TESTS IDENTIFY ANY UNUSUAL OR UNEXPECTED BEHAVIOR FORTHESE EVENTS, WESTINGHOUSE WILL EVALUATE THESE RESULTS TO DETERMINE WHETHER ADDED TESTING IS WARRANTED AND WHETHER THIS TESTING SHOULD BE PERFORMED AT OSU

- THIS POSITION ADEQUATELY ADDRESSES THE ISSUE i

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

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PRHR HEAT EXCHANGER - NRC ISSUES Nf

NEED FOR ADDITIONAL PERFORMANCE TESTING j

, ADDITIONAL INFORMATION HAS BEEN PROVIDED TO THE STAFF ON ,

i THE PRHR TESTS AND THEIR APPLICABILITY IN RAI 952.14 AND 440.13 q

WESTINGHOUSE IS INVESTIGATING THELITERATURE TO OBTAIN t INFORMATION ON CHF LIMITS FOR TUBE BUNDLES AND ARRAYS SIMILAR '

TO THE C-TUBE' GEOMETRY OF THE REVISED PRHR

! CALCULATIONS WILL BE PERFORMED TO QUANTIFY CHF MARGIN i

THE STAFF IS REVIEWING THE RESPONSES TO THE RAl'S ,

THIS ISSUE REMAINS OPEN UNTIL THE STAFF COMPLETES THE  :

REVIEW OF WESTINGHOUSE SUBMITTALS AND OTHER FERTINENT INFORMATION i

4 4TH STAGE ADS VALVES - NRC ISSUES PERFORMANCE TESTING

- AS PART OF DESIGN CERTIFICATION, WESTINGHOUSE WILL- PERFORM ,

SENSITIVITY CALCULATIONS TO QUANTIFY THE DESIGN MARGIN

- DURING THE EQUIPMENT QUALIFICATION PROGRAM, TESTING OF THE PROTOTYPE 4TH STAGE VALVES WILL BE PERFORMED

- WESTINGHOUSE WILL PROVIDE ADDITIONAL INFORMATION ON ,

TESTING TO BE PERFORMED OUTSIDE OF DESIGN CERTIFICATION THIS ISSUE IS ADEQUATELY ADDRESSED BY THE SENSITIVITY STUDIES-.

- THE STAFF WILL ASSESS THE- ADEQUACY OF THE POST DC TEST PLANS

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CHECK VALVES - NRC ISSUES N PERFORMANCE AND RELIABILITY QUALIFICATION TESTING AND ISI/IST WESTINGHOUSE PROVIDED ITS TEST PLAN AT THE DECEMBER 10,1993 MEETING WHICH INCLUDES ADDITIONAL TESTING OF EXISTING CHECK VALVES AT OPERATING PLANTS WESTINGHOUSE IS REVISING THE IST PLAN TO INCLUDE MEASUREMENTS OF THE Ap REQUIRED TO INITIATE FLOW AND THE FLOW REQUIRED TO FULLY OPEN THE VALVES THE STAFF AGREES, IN PRINCIPLE, WITH THE WESTINGHOUSE PLANS FOR PERFORMANCE AND RELIABILITY QUALIFICATION TESTING WESTINGHOUSE HAS THE ACTION TO PROVIDE ISI/IST PLANS IN RESPONSE TO RAI 210.24 l

PASSIVE CONTAINMENT COOLING SYS. TEST - NRC ISSUES SCALING ANALYSIS

- ADDITIONAL SCALING EVALUATIONS ARE UNDERWAY AND WILL BE PROVIDED IN DRAFT FORM TO THE STAFF IN JULY TEST SIMULATIONS

- INTERIOR VELOCITY MEASURMENTS AP600 WETTED FRACTION DOWNCOMER FLOW A SERIES OF FOCUSED MEETINGS TO CLARIFY THE ISSUES AND EXCHANGE INFORMATION HAVE BEEN PLANNED.

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SPES-2 Integral System Test Status E. J. Piplica Manager, AP600 Test Engineering

A SPES-2 TEST RESULTS

SUMMARY

i TRANSIENTS INITIATED FROM FULL POWER CONDITIONS COMPLETED TO DATE INADVERTENT ADS ACTUATION (H-06)

PERFORMED AS LAST PRE-OP TEST ,

ADS STAGE'1 OPENED AT FULL POWER NO NON-SAFETY SYSTEM OPERATION i

ADS ACTUATIONS BASED ON CMT LEVEL 2ND AT 60%,3RD AT 50%,4TH AT 20%

- ADS 4TH STAGE NOT OPENED l  :

l 2-INCH COLD LEG BREAK (S00103)

- NO NON-SAFETY SYSTEM OPERATION INCH "

DIAMETER", SQUARE-EDGED BREAK ORIFICE b

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SUMMARY

(CONTINUED)

TRANSIENTS INITIATED FROM FULL POWER CONDITIONS COMPLETED TO DATE 2-INCH COLD LEG BREAK (S00203)

- REPEAT OF S00103 .

- "2-INCH DIAMETER", ROUNDED ENTRANCE BREAK ORIFICE ,

REVISED ADS SETPOINTS AND VALVE SIZES 1ST AT 67% CMT LEVEL,2ND AND 3RD TIMED,4TH AT 20%'CMT LEVEL

- PRHR HX ACTUATED ON "S" SIGNAL 4

i -

2-INCH COLD LEG BREAK (S00303) ON 4/30

! - REPEAT OF S00203

- PZR TO CMT BALANCE LINES DELETED

- DATA PROCESSING IN PROGRESS

- NO DIFFERENCES WITH S00203 OBSERVED 1-INCH COLD LEG BREAK (S00401) ON 5/6

- NO NON-SAFETY SYSTEM OPERATION

- DATA TAPE NOT YET RECEIVED

- NO UNEXPECTED OCCURRENCES APOVTRI.WPP

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

iri ~

SPES-2 TEST RESULTS

SUMMARY

(CONTINUED) . .

TRANSIENTS INITIATED FROM FULL POWER CONDITIONS COMPLETED TO DATE NEXT SCHEDULED TRANSIENTS 2-INCH COLD LEG BREAK (S00504)

- SCHEDULED FOR WEEK OF 5/15/94

- WILL INCLUDE NON-SAFETY SYSTEM OPERATION TO OBSERVE PASSIVE /NON-SAFETf SYSTEMS INTERACTION

- DVI LINE BREAKS INCH AND DEGB CL TO CMT BALANCE LINE BREAKS INCH AND DEGB Il38DMP

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( x OVERVIEW OF APEX SCALING BASIS f

For:

AP600 Design Certification Westinghouse /NRC Senior Management Meeting May 10,1994 l

4 Presented By: 7/

Dr. Joss N. Reyes Oregon State University

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 sirnilarity 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.

OSU NUCLEAR ENGINEERING

GENERAL SCALING METHODOLOGY (j) ~ SPecify Experimental objectives (2) PPIRT (3) Perform Scaling Analysis

,, ,, d ,,

1

"**I N Venting, Draining. Recirculation

! M CQ ...

Depressmization -+- and Injection - -

Scaling Scaling Scaling Analysis Ana ym.s Analysis Analysis

,I ,I IP ,f Develop Develop Develop Develop (4) H Groups H Groups H Groups H Groups and Simihrify and Simihrity and Similarity and Similarity Gteria dieria Gteria Gieria Yes Yes Yes Yes

,, ,, ir ,,

i Signifr$nt Signifant Signifan' Si'aifan'

.(5)

Scaling -

W - Scaling Datortions?

Scaling Dtstortions?

T%stortions? Distortions?

No No No No . '

,r ,r ,,

System Design System Design System Design - System Design (6). Swi6cathas Swirnens Speineathm Specifications l

2r 1r p) AP600 Test Facility Design Specifications ))

and Q/A Gtical Attributes OSU NUCLEAR ENGINEERING.

i c^ =- -- _ _ _____________1_________________________._

l i

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 OSU NUCLEAR ENGINEERING g

' APEX! Facility Scaling Ratios Parameters Scaling Ratio i

1. LLength Scale 1:4

2. Time Scale 1:2

3. Velocity Scale 1:2 ,

L l 4. Flow Area Scale- 1:48

5. Power Scale. 1:96 L 6. . Volume Scale 1:192 L 7. Pressure Scale * ~1:3

8. ..

Mass Flow Rate 1:96

• Can!be variediby adjusting initial conditions in APEX.

l .g

-I OSU SCALING AND FACILITY DESIGN u

[ .

TO FURTHER EXAMINE THE OSU FACILITY SCALING, THE OSU TEST FACILITY HAS BEEN COMPARED TO THE AP600 PLANT USli4G THE PRESSURE SCALING FACTORS OSU INITIAL STEADY-STATE CONDITIONS: -

REACTOR COOLING SYSTEM CORE POWER 0.700 MWt CORE FLOW .

116.7 lb/sec PRESSURIZER PRESSURE 400 psia CORE INLET TEMPERATURE 410.4 F CORE OUTLET TEMPERATURE 415.6 F

' SECONDARY-

, _ STEAM GENERATOR TEMPERATURE 407.6 F BREAK SIZE SIMULATED 2" cold leg break '

i l

l l

OSU SCALING AND FACILITY DESIGN COMPARISON PLOT SCALING AP600 OSU Time t-ta 2*(t-to)

Pressure P/1080 P/320 Flow W/96 W Mixture Elevation Fraction of Component Mass Fraction of RCS Total

'~^

AP900/ OSU NORMALIZED RCS PRESSURES PFN 9. OSU PFN NORM. PRESSUHL

.9 AP600 NORM. PRESSURE

-(4,b) 6 2

P,a Pg

-5'00 ' '

" 6 ': -560' 1000 1500 Reference.t;ime-(AP600 time) -

APE 00 / OSU NORMALIZED ACCUMULATOR 2 LEVELS EWiXSFN 61 OSU ACC FILL

. e EWlXSFN 61 AP800 ACC FILL

. (9,5)

I mix I sotal I k L --- ~

Reference time (AP600 time) -

' 5'_:_ , .

AP600/ OSU NORMAUZED CMT2 LEVELS EMIXSFN 66 OSU CMT FILL a sEMIXSFN 66 AP600 CMT FILL

- %)

' Lil 1

l_

f00 15'00 Reference time {AP600l time) z___

AP600 / OSU NORMAL 17Fn SYSTEM MASS HISTORIES MASS 70 OSU NORM. MASS s eWASS 78 . . AP600 NORM. MASS

- (9,6)

I 4

-M Ma

(

1 1

I Reference. time (AP600 time)

~~~

~

l i I ,

Conclusions

- Preliminary comparisons of the NOTRUMP AP600 Plant and OSU APEX look favorable and support the pressure scaling approach to establish initial conditions in APEX.

. H2TS scaling methodology is comprehensive and traceable.

- Scaling analysis indicates that pressure scaled phenomena in the model will be representative of that expected in the full-scale AP600

- Long-term cooling behavior will occur when fluid property "

similitude exists. Processes occurring subsequent to ADS 4' stage depressurization will be modeled well in APEX.

. OSU APEX will provide sufficient long-term cooling data to benchmark the codes.

f

]

i .

Technical Brief on AP600 OSU Test Facility  ;

Low Pressure integral System Test - Facility Status for U.S. Nuclear Regulatory Commission  ;

Senior Management Meeting at Oregon State University ,

i May 10,1994 ,

presented by

~

Moshe Mahlab, Manager OSU Test Facility Project t c.

Westinghouse Electric Corporation l 50448A.1 -

4

_2_.. . _ .____m____ _ _ . _ . .___._____.___._.__s- -

- <____m . .. .

h 1

I Presentation Outline i

Program Objectives  ;

i Facility Design  ;

t

Facility Construction and T/O

! Instrumentation and Control '

4

- Data Acquisition System (DAS) ,

! Pre-operational Testings Facility Operation ,

- Data Reduction  ;

Matrix Test Schedule 1

! ^

t L

Objectives of OSU Test Program

. To provide data to validate the computer codes used in Westinghouse I i AP600 SSAR Analysis.

Simulate gravity injection and natural convection due to small break in long-term cooling mode.

- Obtain data on the passive safety system performance i

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

- All AP600 RCS and passive injection systems are modeled i according to the scaling analysis

- All interconnecting piping and pipe routing to more accurately represent form losses

- A unique Break and ADS Measurement System (BAMS) to determine mass and energy releases r

- Over 750 data instrumentation to provide the data needed to

-validate the computational models

k. ,

SO44aA.3 -1 4

-..a= . ._-_._-._a = . - - - _ _ - - - _ _ - - . w -

t

'k Facility Design Design pressure is-400 psia Design temperature is 450 F a

1/4 linear scale n 1/2 time scale Sizes are determined by: scaling analysis performed by OSU- ,

j t

1 50448A.4 l^ ,

l

.- .. . - . . . . . . . . - . ~ . . . . .- - - . , . _.=_-_-__--_-____:__-:-

a Primary Systems .

Simulated reactor vessel and internals Two simulated loops: Each with two cold legs, one hot leg, and one S/G Simulated pressurizer and surge line One simulated PRHR HX and associated loop Four simulated RCPs 48 heater rods simulating approximately 2% decay heat 50448A.5

Injection Systems Two simulated CMTs and two accumulators with associated piping Simulated IRWST with associated lines and a sparger Simulated containment sump and associated pipings Simulated ADS 1-4 stages Simulated DVI lines and pressure balance lines Simulated RNS RHR pump and lines from IRWST to reactor vessel Simulated sump injection at containment pressure in long-term cooling mode ]

.-.w.. , w e + w w = ., s vs-,..

Break & ADS Flow Measurement System Designed to: .

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 ,

l

- - All steam piping and moisture separators are

! heated o

50448A.7 i

_m ...__m, _..m____m .___. _ _ _ . _ _. . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _- _

____e =ww.w--*--:+-*c. .--er. E -m- . .- --

m- w.. r

f 6

Break & ADS Flow Measurement System (Cont.)

Break simulation at hot leg Break simulation at cold leg (top and bottom) ,

Break simulation at CMT- Cold leg pressure balance.-

line -

Break simulation at the DVI injection line

-l Flow separators and flow measurement system

Condensate makeup system .

50448A.8

-e--._,-_ a_ _ - - - - _ - - - - _ _ . _ _ . . _ _ - - _ - _ - - ----__-_----x ___ - ---_ w _ _ . _ -s- - avenw- -

n w 4 w,e w e m e,-ww.- - e

Auxiliary Systems Feedwater System ,

Vent and Drain System-S/G Blowdown System Water Makeup System WaterTreatment System Nitrogen; Pressure System 1 Electrical Power Supply ,

l ' Grounding l 1 UPS 50448A.9

__._--_______-_-__--____-..u

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

Building Services Structure / Floors / Platforms Fire Protection HVAC Instrument Air Supply Insulation Heat Tracing Lighting ,

50448A.10

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p c

I ei r t r

ue sm s o _

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6 s Py 1 AS 1 _

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8 .

4 -

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0 5

7 b

Facility Construction Constructor - The Industrial Company (TIC), Northwest ,

Construction Manager - Jim Nylander TIC is an ASME Section I and Section Vill Certificate Holder with U, R, A Vessel Stamps and Power Piping ]

Stamp TIC developed and implemented a QA/QC program for the i- ' OSU test facility TIC provided on-site Q/A, O/C manager to follow.the ,

construction quality I TIC provided an onsite, full.in.- trument calibration service ,

i 50448A.17 -

t. .

- _ _ - . . , . . -- . , . . .a- - - . - , . . - . . ~ .

L i

! Construction Tumover i

System walkdown Generation of punch listitems System flushing System hydrotest (1.5 design pressure)

Vessels and piping accepted by the A/l Systems and component documentation records were prepared and submitted to Westinghouse /OSU Electrical system accepted by the' State inspector Westinghouse has performed an independent review of all pressure vessels Westinghouse has performed static and d!/namic piping and support analysis for all high energy lines and all break piping and equipments

" Facility turned over to OSU on March 31,1994 for hot shake-down testing 50448A.18

b t

Instrumentation and Control Use of commercial reliable instrumentation ,

Design instrumentation to obtain system wide, and component mass / energy balances by direct '

measurement or calculated from data

- Supply redundant measurements when possible Control process instrumentation is separated from the i data acquisition system-i

?

50448A.19 -

_______________.______________z_______. -

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

Instrumentation and Control 4( Cont.1)

Total of 754 instruments measuring flow, differential pressure drops, levels, heat flux, phase, power, and temperature

- 118 Differential Pressure Detectors

- 42 Pressure Transmitters

- 25 Magnetic Flow Meters

- 5 Turbine Flow Meters l

- 6 Vortex Flow Meters l - 5 RMS - Power kW Meters

- 12 Load Cells

- 12 Heated Phase Switches

- 53 Heat Flux Meters ,

- 16 Heat Trace Thermocouples

- 405 Thermocouples

- 7 Process Controllers

- 48 Solenoids with Limit Switches 5048A.20

i

.f

~

Instrumentation and Control (Cont.}

Control System The control system is independent from the Data Acquisition

' System (DAS)

Several field signals are being duplicated to be used in the control system for setpoint detection, alarms and annunciation ,

The control system is based on PLC (OMRON) hardware and on

-process control devices (Fischer Porter)

The Control System Documents are

- The setpoint documents

- The facility logic diagrams. '

- The PLC ladder logic diagram

- The process control devices programming ,

- The controllogic test procedure 3

- The control logic test report 50448A.21

l.

t

h r

Data Acquisition System  ;

Monitors 750 data points Maximum scan rate is 1 . nack i nack 2 nacka channel'per second in burst mode nS-232 nS-232 nS-232

'A 12 channel strip chart used for selected osc ec Ta m -

oec ec writabie _ oec ec instruments SYS A SYS B SYS C Data stored and transmitted to Energy ethemet {

Center on CD ROM i Writable -

Remote "CD

" " "Transfw Software validated to -co ec ,

NOA-1 Signals from the control panel will be restored on

. dedicated PC soum.=

t t

i Pre-operational Testing Cold and hot pre-operational. tests used to characterize the system and components of the facility Cold pre-operational testings included .

! - Vessels Volume Determination 1

- Lines flows vs. pressure drops including flow orifice sizing j and testings

- Pumps flow curves

- Simulated control logic testings

- Instruments calibration and testings  ;

- Background. electrical noise measurement .

~

. , , . - .:. . . - ~ . . -.  : . . - . - . - . . - .

Hot Pre-operational Testing Ambient heatloss determination '

. Steady-state characteristics.at various power levels Obtain data.to determine the PRHR HX, S/G, and LCMT performance at various plant power levels The capability and performance of the BAMS j Obtain data to verify the algorithm for the decay power i

Obtain data to verify valve actuations and fl'ow injection values Verify the performance otDAS under test conditions y i

50448A.24

_ _m- _ _ _ . . - , . . . . , .-, - , = , .. -,, = .--m. ,______m m_ _ _ _ _ . _ ____ --

QA and Configuration Management Developed and implemented a specific Project Quality Plan (PQP) for l the test facility for design, construction and testing The POP is focused on assuring the-quality of the:

- Plant physical data L - The instrumentation data measurements

- Personnel safety

- Protection of the :.westment

- A set of as-built facility data has been generated and is controlled.

This set of data is intended to be the basis for the fa,cility

. description report

- A detailed software validation program was established for the project to assure the quality of the measured data sou m.2s

Matrix Test Schedule (2 Week -Intervals)

SB01 April 1-21 Prepare and Review Test Procedure July 1-7 Perform Test July 8-11 Prepare and issue Day-of-Test Report July 13-14 Prepare Determination on Proceeding to SBO4 August 9 issue SB01 Quick Look Report SB13 Sept.16-22 Perform LAST Category 1 Test SB19 Feb 2-8,1995 Perform LAST Category 2 Test May 2,1995 Final Test Report 50448A.29

A Readiness Review

. Scheduled May 11 and 13 Will be conducted by Westinghouse Test .

Engineering, Safety and Licensing, Project Engineering with Utility, DOE and EPRI representation NRC has been invited to observe

! Expect to concur with the initiation of matrix testing by a May 20,1994 .

l 50448A.30 L

L l . _ __ _ . . . - . . . .

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

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

4 1

Onsite Test Data Handling Objective

- Verify that individual test requirements have been met Prepare " day-of-test report" Procedure Download data from.DAS PCs to CD ROM including display

. files, continuous monitoring files, burst data files, and ,

configuration files 1 Break data files into 1.~4 MB size with matrix format and convert to. engineering units Record the formatted files on CD ROM for analysis at the Westinghouse Energy Center Plot; display files on hard copy mn

.___ _ _ _ _ _ _ _ -_ _ ___ __. __ _ _-. a ____ .

,__ ___ ______. m. . . _ . . = , . - -. , . . . . . ; .2 - . - ._ _ : : - ,v._ . . . .

4 D

Site Operation and Testing Staff Program Manager Dr. J. Reyes Data Processing Operators Test Engineer Tech Support 9

V. Nayyar J. Groome-Mgr C Dumdsay-Mgr F. Kengle L. Ross** J. Haitis R. Ferrel D. Holland **

D. Wert** M. Yundt - J. Schlaman R. Klein*

M. Miller M. Carter Dave Dody* . 1 C. Bexter

• • Service Contract - as needed basis

• TIC-Contractor 1

50446A.27

i Operation 1

Operators are trained and qualified to operate the facility Operation and maintenance procedures are in place '

Spare parts are stored onsite Instrument calibration lab is in operation OSHA and F/P evaluation has been completed

Emergency operating procedures are approved and -

were incorporated into the Radiation Center safety ,

procedures Operating permit was obtained from the State fre-% -em+e>meFr' - m e'mY m 4