ML20153F651

Nonproprietary Slides Used During 921214 Presentation to NRC Staff on AP600 Test & Analysis Programs Schedule Update

ML20153F651
Person / Time
Site:	05200003
Issue date:	12/14/1992
From:	Piplica E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20153F638	List: ET-NRC-92-3783, Nonproprietary Slides Used During 921214 Presentation to NRC Staff on AP600 Test & Analysis Programs Schedule Update ML20153F635
References
ET-NRC-92-3783, NUDOCS 9809290192
Download: ML20153F651 (43)

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>$ [3 E's Presentation to the

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!"# AP600 TEST & ANALYSIS PROGRAMS

~

SCHEDULE UPDATE

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by E. J. Piplica, Manager Test Engineering Westinghouse Electric Corporation December 14,1992 g 7- Aln c 3 7 83 t - - - - - - - - - _ - - _ - - _ - - - - - - - - - - - _ - - - _ - _ - - - - - - - - - - - - - - _ - - - - - - - - _ - - - _ - - - - - - - - - - - - - - - - - - - - - - -

G AP600 TEST PROGRAMS PASSIVE CONTAINMENT COOLING SYSTEM TEST PASSIVE CORE COOLING SYSTEM TESTS COMPONENT DESIGN VERIFICATION TESTS U -. - -_

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1 TEST CATEGORIES .

SAFETY RELATED TESTS NON-SAFETY RELATED EQUIPMENT TESTS BASIC RESEARCH TESTS i

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i SAFETY RELATED TESTS 1

- PROVIDE DATA FOR COMPUTER CODES USED FOR SSAR ANALYSIS:

- MODELS

- CORRELATIONS

- VERIFICATION

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- GENERALLY, A THERMAL-HYDRAULIC TEST

- UNDERSTAND AND-EXPLAIN T/H PHENOMENA ,

- CAN BE SYSTEM OR SEPARATE EFFECTS TEST t

- HIGHEST QUALITY ASSURANCE PEDIGREE i

- NOA-1 APPLIES,10CFR21 APPLIES i

- TEST SPECIFICATION REQUIRED

- TEST OPERATING PROCEDURES REQUIRED

- TEST FACILITY DESIGN DOCUMENTATION REQUIRED

- QUALITY RECORDS REQUIRED

- EXAMPLES

- LARGE SCALE PCCS HEAT TRANSFER TESTS

- INTEGRAL SYSTEMS TEST (SPES-2, OSU)

- SEPARATE EFFECT TESTS (ADS, CMT)

NON-SAFETY RELATED EQUIPMENT TESTS i

3

- PROVIDE DESIGN INFORMATION ON SPECIFIC COMPONENTS

- FEASIBILITY OF DESIGN j - MANUFACTURABILITY

- VERIFY COMPONENT PERFORMANCE E

j - GENERALLY, MECHANICAL TESTS l)

. - PERFORMANCE DATA j

- WEAR DATA 2 '

HIGH QUALITY ASSURANCE STANDARDS I - NOA-1 APPLIES

$ - TEST SPECIFICATION OPTIONAL

- TEST OPERATING PROCEDURES REQUIRED 2

j - TEST FACILITY DESIGN DOCUMENTATION REQUIRED .

j - QUALITY RECORDS REQUIRED z

- EXAMPLES

- HIGH INERTIA ROTOR TESTS

- RCP FLOW TESTS (AIR & WATER)

{ - CHECK VALVE TESTS

i #

BASIC RESEARCH TESTS EXPERIMENTAL IN NATURE  :

GENERALLY BENCH TESTS PERFORMED AT UNIVERSITIES

- INVESTIGATE SPECIFIC PHENOMENA IN DETAIL

- ANSWER SPECIFIC QUESTIONS OF PERFORMANCE OR FEASIBILITY

- PROVIDE GUIDANCE FOR FURTHER TESTING QUALITY REQUIREMENTS

- TEST PLAN REQUIRED

- TEST FACILITY DESIGN DOCUMENTS REQUIRED 1 EXAMPLES

- UNIVERSITY OF WISCONSIN CONDENSATION TESTS

- UNIVERSITY OF TENNESSE REACTOR VESSEL AIR VISUALIZATION TE ,

- BENCH WIND TUNNEL TEST ,

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Supplier j h

l Component NRC l Eardware Requirements d b

N Pinal SSAR I Component Analysis l i Design i Verification Cosoponent Tests Design H

Verification of Design Performance Plant Design Function h

Design Predicted Requirements s. Component l ip Performance Plant Analysis To support Design h

Performance Data for Models

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ig Component Feasibility Tests '

Design Certification Tests (Proof of Principle) 1( (Proof of Principle) i Basic Research Tests

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AP600 es: Objec:ives/ Conc usions Test objecevWConclueion Cx; i- Test Resuno Requer=<

Penelve Containment Coeling Teste Deee '

SSAR FDA/DC 'C-w .

Demonetsted operemon of he PCCS over me fue range design basis Completed. X integrei PCCS Test (Weesnghome STC) opereeng condsons Juay 1992 To demonetese opereson of he PCCS on a scaled stucters which Phase 1 - X

> Large Scale PCCS (Weseghowe STC) accurately models bom the contesnment dome end e6dowes heet May 1992 tene'er erose end insido contenment structree Phase 2 - X

June 1993 j /

7

, PCCS Weser Distrbuton (Weetnghouse AESO) ,

t Demoneested the efleceveness of water dineibuton on the conter of Campbted. X Phase 1 - Center of %. 20' Diameter be contenment dome June 1991 i i Demonovated the efiscoveness of waner doesbuton on the Completed. X Phase 2 - Fue Scolo 1/8 Secton contesnment dome and upper endowell Jerusery 1992 .

Venfy deegn of water dettnroon system Apre 1963 Phase 3 - Fue Scolo 1/8 Secton PCCS Whd Tonnel(Urwomety of Westem Ontario)

Demonetsted be wind hduced pressure on the contserrnent shield Completed. X i o Phase 1 - Overedi buddng effects tuidng dse e air bieteoutet conAgwesens and esto saucasrae Juff 991 1

f Detenmned beme loedng end demonetened the eMoct of wind on Completed. X o Phase 2 - Detoded M. Feel VenEcemen February 1992 conemsnment erry.due air flow ,

i i To demonatene enecas of en* 9*o9'ophy end as perform tesen et higher Sepenmber 1993 X i o Phase 3/4 Reynolde e -nbors l ww.

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i

0 Test Objectives / Conclusions C_ 1- Test Reeuna Required 9er wy System Teek Test Ot4ectfveConctueion ,

Dees i SSAR FDA/DC Desson versomeon ,

Determned heat vansler characterescs of me PRHR heer exchanger j wX (Weennghouse STC) and m!amg cherocsonesco h the IRWST j Cornpaeand. X December 1980 Componeed. X ocsober 19eo

.c seeurtzenen System Test (Ceasede, tiety)

To confrm the cepeory of the sparger and to deaermne the dynamic November 1992 X Wger Performance & Tank Loads effects en the IRWST structare To simulate opersoon of me mue>menc deprenowusson syeamen and to December 1993 X sawe Performance confrm a w capooty and operabany of to ADS vakree ,

i Taventy em gravity dram behaver et es core enehaup tank over a hA Apr* 1993 X

• enk(Weeanghouse AESD) l, range of 90s rates and preneures and t2 ver18y me operatori of me tank levet inewknon (

To prowse date => erepuses to opereeen of me PXS et tour preneurs December 1993 X mhng (1/4 Scale) ,

. Urvversny)

To extend be emetng crincel heat fkan corraleson for W heet February 1993 X a Universky) ensembises et lower Son condoorm Proesure Integra! Systems Test To provide date to erelueen she operesan of he MS et high prosaure, November 1993 X l

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, break vene. ente .ms

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300 Test Objectives / Conclusions _ .

Test W W ;:' m C: , u- Test Reevns Moedred for wt Design Teste Done  !

SSAR N DC Desgn venscamon i

Completed. X 4HR Sucson Noz2$e Test (East Pettatarph) ELvurated Sucson Vortex Sepenmber 1986 Compassed, X Coolert Pump (RCPySG Channethead Air No SG e Punp Fbw Anomales March 19et

• esanghouse EMD)  !

Sepeember 1994 X ,

'to obtain now, head and smooney clete to accurately preda the a:or Flow (Woonrghouse EMD) performance of he fuswale AP600 reactor coolant pump Demoneirated marweectsrobarer et deposeed urersum roer m and X ,

oumni Bearbg (WenWrghouse STC) large redet beennge and ossermeed rosor dra0 lossee -

Compleed, e1 December 1989 w2 i February 1991 )

t Completed, X  ;

To opinize rotor dreg knees gh inetta Actor August 1992 pouse STC)

-svumenterion Tests (ICts)

Comoisted, X ,

Demonstated that system is net ==W to Electomagnetc '

-snegnese Interierence Sepeember 1990 Interfenance trom the CRDMs

-W MD) E May 1904 X [

-iW Vibroson (teonty not chosen) To demonatene shot the twnbie is not ouW to e% weer I

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?2665 07/14/90 12665 (0) 04/30/92 Cerufeneetten Teete 13307 (0) M/30/92 Integret (seett Scote) Teste l

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. Wtruf Turmel Teste Phoe. 1 13318 (0) O&/30/92 13294 (0) 04/30/92 Phase 2 13315 (0) OL/30/92 13323 (0) 10/02/92 Phase 3 13318 (0) 04/30/92 Phase 6 13318 (0) 04/30/92 i

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Test spec or operating Facility Interie Dete Finst Consmrient Deelyn separt Report Test Supert Tests Test Ptern Proceesee 13296 (e) et/34f92 RCP/SC Chemet esed Air Fles Tnt acP Jeumet Deertne Tests 1Maa erfMp9e Phase 1 13309 (0) 04/30/92 12 des (93 eV30/92 13319 te) sy30/92 h2 13312 (0) et/30/92 13447 to) 14pC2/92 RCP algh Inertie meter Test 13313 (0) 04/30/92 t RCP Water pyteutic Flow Test 13305 (0) 06/30/92 t 12p 3 ge) e4/34/92 L Incers Instrumentatten System St! Test {

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L Pavisten 0: Decautier 13, 1992

M!k7 AP600 CF EQK$$tVE TEST

'gggsp o Verify hydraulic perforiitancef6f: swing check valve (provide valve desigrifsailbillip information)

Opening differentisi pre.siure Differential pressure over the expected valve flow rate with prototypicMEWe5 arrangement

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,. Ig o Develop a qualificationjlarr Contract Penn StateLUniversity to review existing check valve data ,, .

o Utility participation Have contacted 5 utilities about the possibility of testing existing check. valves

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-an- # 16* CV IN SERIES -A- #2 6" CV IN SERIES -e- #16" CV ALONE -H- #2 CV ALONE

30 CHECK VALVE TEST RESULTS '

iferential pressure required to initially open check valve is small (less.than uple inches; of. water .%+

I d N- ;a aeratiori"ofTeachicheciCvalve t + r isismooth'under'all M$i .o flow: r

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my ninarlto idlik,itidtidient"

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' ' GC, ,pp3R essure drop vs.' flow rate is predictable *b

, ere exists a critical flow rate for each check valve at which the disk is just y o p e r..

interaction seen between valves in series when piping between valves is

g. Interaction seen at 3 pipe diameters was very small.

b

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o Current PWRs UselCheck Valves in Similar Service RCS chemistry. . f -l Stainless steel with'st6llite' seats Infrequent use,':no'niially!Olosed 1

nMg&i i

o Well Designed, Sihis!y +gChickLValves Are Reliable in i

Nuclear Power PlantiSEd/ ice-i - 9 i

Search of NPR'DS failure-records (1984 to 90) indicate 4500 checEvdive failures Of these only 87'werel failures to open None of the failures was for a check valve with similar conditions t'olihe'IRWST valves i -

No indication of "boric acid corrosion or self welding

! was found  ; 2 ,

m.

! o Check Valve Testing i *.

Performance tests showjAP600 IRWST injection i and recirculation:cifs;ckivalves perform well l -

Further testing is bdingdiscussed to determine if in j plant testing could:bk: conducted to determine if 4

corrosion bonding o~r?oth'Er sticking failures would j

occur at IRWST opening pressures 3

i 4

FAILURE TO OPEN OR ONLY PARTIALLY OPEN PERCENTAGE OF FAILURES

• IN WHICH DESIGNATED MECHANISM WAS INVOLVED

-BWR'S AND PWR'S-50 A Note that the 16tal percentages exceed 100% due to rnore than one mechanism f j being designated in some failures 40 -

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• TOTAL NUMBER OF FAILURES EOUALS 87 SOURCE : NUCLEAR PLANT REllABILITY DATA SYSTEM JVERAGE YEARS 1984-1990 u

Figure 3.1 Percentage of Failures as a Function of Failure Type - BWRs and PWRs

. t FAILURE TO OPEN OR ONLY PARTIALLY OPEN PERCENTAGE OF FAILURES

• IN WHICH DESIGNATED MECHANISM WAS INVOLVED (

-BOILING WATER REACTORS-50 l f a Note that the totalpercentages exceed

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• TOTAL HUMBER OF FAILURES EQUALS 47 SOURCE : NUCLEAR PLANT RELIABILITY DATA SYSTEM - COVERAGE YEARS 1984-1990 Figure 3.2 Percentage of Failures as a Function of Failure Type - BWRs

.y.. . . . ~ -

Table 3.1 Failure Type Categorized by System - BWRs MURE _ TYPE _ ; WEARMECH DAMAGE OORROSCN FOREIGN DEBRIS HUMANERRORS ODG 4

ON>NOMN UNSUREREPLACED TOTALS sOF NL FALURE TYPE NO.: [1] [

[1] [21 [3]' [4] [5] [6] -

[1]-[6] _ FAILURES

a. 3 .

SYSTEM - - -

-- "- - W- .- e - 1 4!N STEAM Mawe's M 1 1 '"re 'I

~**- '-4" *- "-'m &'" -e t 8 V

?- - 16 EACTORCONISOL Q)OLNG Fa~w 21 + :-* r '--

2 3 "' i - U 1*? w"-^9 m ia 8 0- *8 GH PRES COOLANT MJ e %w ~~e 1 er N ~3 " -^ 1 M '-* m '*W, ^*****+ t w r Se+w e 5 *- r-s 5 SSENTIAL SERVICE WATER =-m  ; t u:m-' 1 3' ta

• M 1 - m - 4"* ' + " * - - ---m' c '~ m <e6A 7~ 3 ESEL STARTING AIR ?-m4 ** r "a ~ 1 "We > -

1- ~' => a :^ ' F c? ' '~ - w *r' M PNS OORE SPfMY pm +~</m m 1 '; CS*-

• 2" "" 2 ,

1

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'MBUSTIGLE GAS CONT-DIL " "NOF ":v" -

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x 2' W 2 R10W PRES PUECT * '~1" ~'

1 '

ACT BLDG CCW ' n

~: 2 ' '- 2

~

1 1 2 .

SEL FUEL 08L - - 1 1- 1 EDWATER - 1

'1- 1 I

NTDOL ROO DRNE 1 1- 1 r ALS : 22 5 12 2 8 1 0- 50 I 47 CENTAGES: 46.81% 10.64 % 25.53 % 426% 17.02% 2.13 % 0.00 % 106.38%

'E - THE TOTAL PERCENTAGES EXCEED 100% DUE TO MORE THAN ONE MECHANtSM BElGN DESIGNATED N SOh4E FAILURES 1

O'

S FAILURE TO OPEN OR ONLY PARTIALLY OPEN PERCENTAGE OF FAILURES

• IN WHICH DESIGNATED MECHANISM WAS INVOLVED

-PRESSURIZED WATER REACTORS-40 #

f A Note that the' total percentages exceed 100% due to more than one mechanism being designated in some failures 30 -

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• TO1 SL NUMBER OF FAILURES EOUALS 40 SOURCE: NUCLEAR PLANT RELIABILITY DATA SYSTEM - COVERAGE YEARS 1984-1990 e

Figure 3.3 Percentage of Failures as a Function of Failure Type - PWRs j

Table 3.2 Failure Type Categorized by System - PWRs

>RE TYPE :

WEARMECH DAMAGE tXXe OSON FOAEON DEBFs5 HUMAN ERAORS ODER LtMNCMN UNSUREREPLACED TOTALS 8OF FALURE TYPE NO. : [2]

111 Q] [3] [4] [5] {6] [11-f 6] FAILURES SYSTEM P COOLNGWATER 4 2 1 1 g.- - 3 El STARTNG AIR' * : > 1 1 2 1 1 2 -~ '

3 8 EAR SERVICE WATER - 2 2 - -

.m. y 4 re, s- 4 1 STEAM & Pw w: e > 2' r - .w- ~

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• 1 c + -J+: ?

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-1 -

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JTANMENT SPRAYOC* - - 5" - 2 +N + "* - 1 ^> " - +' m . ~2 - - .~ n - - s:- ' b;3'N W3-DENSATE*** r5WWeb emurtw'm de 2 ~ - W " *-*"- W.- r-

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'BUSTIBLE GAS CONT-Olt :N ~e ~:%* e2 - *

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+; - , .- 2- 1; LS: 15 to 6 3 1 5 1 41 40 TNTAGES: 37.50% 25.00 % 15.00 % 7.50 % 2.50% 12.50% 2.50% 102.50%

DIE TOTAL PERCENTACES EXCEED 100% DUE TO MORE THAN ONE MECHANtSM BElGN DESIGNATED N SOW FAILURES l m

O

1 6

t FAILURE TO OPEN OR ONLY PARTIALLY OPEN PERCENTAGE OF FAILURES

• AS A FUNCTION OF VALVE SIZE 60 # -

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• TOTAL NUMBER OF FA! LURES EOUALS 87  !

SOURCE : NUCLEAR PLANT REllABILITY DATA SYSTEM - COVERAGE YEARS 1984-1990 Figure 3.4 Percentage of Failures as a Function of Valve Size '

l I

i 4,

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WR C- EC < VA_VE =AILU 9E. .

)BSERVATIONS l@BMM Most check valve failuk hr bue to

~

mechanical / wear damasb$idtTyblicable to AP600 l valve application) w@Wgm$pr6 MB

' -s w ss e i

1 No fa. lures sta,inless to open steel valves- d due nf@bGer696sibrFobs

~ ms?g  :.9 u No failures to open due to$fd$ihn debris in water service for stainless steel 5hlves!

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FOURTH STAGE ADSLTEST5 PROGRAM

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BACKGROUND o

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c. i ORIGINAL 7ADSiFOURTH..,' STAGE VALVE WAS .

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AN 8-INCA VA'iSETAND WOULD HAVE BEEN ADDRESSE@lNiTNEfCURRENT' A DS TEST l A PROGRAMM$@%%ay%. m .

.,: .n%WNp ' !

THE ADS.iTESTS?ARE' COMPLEX EXPER'IM5NT,SL.THATL. EXAMINE THE ENTIREADSiSY. STEM, VALVES, PIPING, '

AND~SPARGERE epwm '~

aMmyq n p e w q w: w K y n o

AS A RESULTgOE4HE;SSAR ANALYSIS, THE .,

VALVE SIZEiWAS INCREASED TO A 12-INCH

. VALVE TO VENTING M [CAPA,V.idE!!NCREASED

- ._F(O RCS CITYy; N r.

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r Ag~s$gge A SPECIFIC FOURTH ST $~dGE]E6SyALVE -AS ,

COMPONENTfDESIGN1 VERIFICATION TEST, NOT AS PART[dF,l

. a.. DESIGN' CERTIFICATION .

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INFORMATION REOUIRED'FROM' FOURTH STAGE ADS VALVE PROGRAM UM g.

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THE MAJORITY OE THE INFORMATION NEEDED FROM SUCH A PR'd,GR M[15'S'P5CIFICALLY COMPONENT DESIGNIRELhfE6Pb

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INFORMATION ISALS - NEEDED TO. VERIFY THE FLOW BEHAVIOR OF THE VALVEE-$HOWEVER OTHER ~

SOURCES / BASIS F..dR.A ._

'T - .- ~HISIINFORMATION s DOES/WILL EXIST TO REDUCE' UNCERTAINTIES 6 o 9NU!$@l @$$$$$ .

FOURTH STATE AD.S:AN_ DaVALVE IS A SIMPLIFIED .

SYSTEMfAN6 DISCHARGES ~iDIRECTLY TO CONTAINMENW'"Y -

ua &ia sw%42 dk5%w.+ S T *@% '

o DATA FROM THEF8-INCH < ADS VALVES IN CURRENTLPRdGRhM Wil'l3BE'AVAILABLE vgewyn agn&mgfsy e o

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MODEL,S,TO.N. NTH.,!N THE o JMi$kIMdhihE IF NECESSARY!/A'MORE CONSERVATIVE MODEL COULD BE USEdlMS$ANIMS W R

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.WOSilA$10use Eners Systems. soisss -

PittstMgh Pernsylvarna 15230 0355 -

L Electric Corr. oration DCP/NRC1409 NSD-NRC-98-5753 Docket No.52-003 August 13,1998 Document Control Desk

. U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY - i

SUBJECT:

RESPONSE TO NRC LETTERS CONCERNING REQUEST FOR WITHHOLDING INFORMATION

Reference:

1. Letter, Sebrosky to McIntyre, " Request for withholding proprietary information for Westinghouse letters dated December 14,1992, and December 17,1992," dated >

July 10,1998.

2.: Letter, Huffman to McIntyre, " Request for withholding information from public

^ disclosure of Westinghousc AP600 design letters of December 15,1992," dated

.. ,, July 14,1998.

v '

3.' Letter, Sebrosky to McIntyre, " Request for withholding information from public  :

.. disclosure for Westinghouse AP600 design letter of February 24,1993, April 19, 1993, and July 14,1993," dated June 18,1998.

[

4.' Letter, McIntyre to Quay, " Status review of AP600 proprietary submittals," dated September 18,1995.

Dear Mr. Quay:

j ' Reference I provided the NRC assessment of the Westinghouse claim that proprietary information was

't provided in a letter dated December 14,1992, that provided the NRC with copies of presentation ,

, material from a management meeting held December 14,1992, discussing the AP600 testing program.

. ., The NRC has no record of a nonproprietary version of the slides being provided. At the time this presentation was made, the information was proprietary since that description of the AP600 testing program had commercial value to Westinghoe. At this time, almost six years later, this information

, 'does not have commercial value and is no longer considered to be proprietary by Westinghouse.

Reference I' also provided the NRC assessment 'of the Westinghouse claim that proprietary information was provided in a letter dated December 17,1992, that provided the NRC with copies of presentation

• material from a meeting with the technical staff held December 9-10,1992, discussing the AP600

~

I  : nn. e v

~

);

W'"'t -

so ao s zooasiriocreoqatteetcair m insogow-w e y az:ci es.cy one

r

?

w

,t age '

< DCP/NRCI409 NSD-NRC 98 5753 August 13, 1998

)

testing program. The NRC has no record of a nonproprietary version of the slides being provided. At the time this presentation was made, the information was proprietary since that description of the AP600 testing program had commercial value to Westinghouse. At this time, almost six years later, this information does not have commercial value and is no longer considered to be proprietasy by Westinghouse, i

Reference 2 provided the NRC assessment of the Westinghouse claim that proprietary information was -

provided in a letter dated December 15,1992, that contained a preliminary description of the AP600 refueling outage plan activities. The NRC assessment was that no material in the letter was specifically identified as being proprietary and that a nonproprietary version was not provided. At the time this subject was being discussed with the NRC technical staff, the information was considered to i

be proprietary by Westinghouse since it contained information that had commercial value to i Westinghouse. At this time, almost six years later, this information does not have commercial value l and is no longer considered to be proprietar; by Westin8 house.

Reference 3 provided the NRC assessment of the Westinghouse claim that proprietary information was i provided in a letter dated February 24,1993, that contained presentation materials from the February 24,1993, Westinghouse /NRC AP600 senior management meeting. The NRC asser nent was that the material was similar to material that exists in the current (1998) nonproprietary v Con of the AP600 l probabilis*ic risk assessment and AP600 standard safety analysis report. In add' the staff indicated

. the material was used by the staffin the development of the AP600 draft safety alu'ation report and therefore should remain on the docket. Our 1995 request, Reference 4, indicatea that the material provided in the Westinghouse letter of February 24,1993, was presentation material that was intended V

for clarification only, not part of the formal review material and requested that the material be returned to Westinghouse. At the time this subject was being discussed with the NRC technical staff, the

!' information was considered to be proprietary by Westinghouse since it contained information that had commercial value to Westinghouse, if this presentation material was indeed used by the staffin development of the AP600 draft final safety evaluation report in November 30,1994, then at this time, over five years later, this information is no longer considered to be proprietary by Westinghouse.

Reference 3 provided the NRC assessment of the Westinghouse claim that proprietary information was provided in a letter dated April 19,1993, that contained presentation materials from the April 20, 1993, AP600 overview. The NRC assessment was that the material was similar to material that exists in the current (1998) nonproprietary version of the AP600 probabilistic risk assessment and AP600 standard safety analysis report. In addition the staff indicated the material was used by the staff in the development of the AP600 draft safety evaluation report and therefore should remain on the docket.

Our 1995 request, Reference 4, indicated that the material provided in the Westinghouse letter of April 19,1993, was preser,tation material that was intended for clarification only, not part of the formal review material and requested that the material be returned to Westinghouse. At the time this subject was being discussed with the NRC technical staff, the information was considered to be proprietary by Westinghouse since it contained information that had commercial value to Westinghouse. If this presentation material was indeed used by the staff in development of the AP600 draft final safety evaluation' report in November 30,1994, then at this time, over five years later, this information is no longer considered to be proprietary by Westinghouse.

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testing program. The NRC has no record of a nonproprietary version of the slides being provided. At the time this presentation was made, the information was proprietary since that description of the AP600 testing program had commercial value to Westinghouse. At this time, almost six years later, this information does not have commercial value and is no longer considered to be proprietary by Westinghouse.

Reference 2 provided the NRC assessment of the Westinghouse claim that proprietary information was provided in a letter dated December 15,1992, that contained a preliminary description of the AP600 refueling outage plan activities. The NRC assessment was that no material in the letter was specifically identified as being proprietary and that a nonproprietary version was not provided. At the time this subject was being discussed with the NRC technical staff, the information was considered to be proprietary by Westinghouse since it contained information that had commercial value to Westinghouse. At this time, almost six years later, this information does not have commercial value and is no longer considered to be proprietary by Westinghouse.

Reference 3 provided the NRC assessment of the Westinghouse claim that proprietary information was provided in a letter dated February 24,1993, that contained presentation materials from the February ,

24,1993, Westinghouse /NRC AP600 senior management meeting. The NRC assessment was that the  !

material was similar to material that exists in the current (1998) nonproprietary version of the AP600 probabilistic risk assessment and AP600 standard safety analysis report. In addition the staffindicated the material was used by the staff in the development of the AP600 draft safety evaluation report and therefore should remain on the docket. Our 1995 request, Reference 4, indicated that the material provided in the Westinghouse letter of February 24,1993, was presentation material that was intended U

for clarification only, not part of the fcimal review material and requested that the material be returned to Westinghouse. At the time this subject was being discussed with the NRC technical staff, the information was considered to be proprietary by Westinghouse since it contained information that had commercial value to Westinghouse. If this presentation material was indeed used by the staffin develcpment of the AP600 draft final safety evaluation report in November 30,1994, then at this time, over five years later, this information is no longer considered to be proprietary by Westinghouse.

Reference 3 provided the NRC assessment of the Westinghouse claim that proprietary information was provided in a letter dated April 19,1993, that contained presentation materials from the April 20, 1993, AP600 overview. The NRC assessment was that the material was similar to materint that exists in the current (1998) nonproprietary version of the AP600 probabilistic risk assessment and AP600 standard safety analysis report. In addition the staffindicated the material was used by the staffin the development of the AP600 draft safety evaluation report and therefore should remain on the docket.

Our 1995 request, Reference 4, indicated that the material provided in the Westinghouse letter of April 19,1993, was presentation material that was intended for clarification only, not part of the formal review material and requested that the material be retumed to Westinghouse. At the time this subject was being discussed with the NRC technical staff, the information was considered to be proprietary by Westinghouse since it contained information that had commercial value to Westinghouse. If this presentation material was indeed used by the staff in development of the AP600 draft final safety evaluation report in November 30,1994, then at this time, over five years later, this information is no longer considered to be proprietary by Westinghouse.

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Reference 3 provided the NRC assessment of the Westinghouse claim that proprietary information was provided in a letter dated July 14,1993, that contained presentation materials from the July 14,1993, meeting where the AP600 main control room habitability was discussed. He NRC assessment was that the material was similar to material that exists in the current (1998) nonproprietary version of the AP600 probabilistic risk assessment and AP600 standard safety analysis report. In addition the staff indicated the material was used by the staffin the development of the AP600 draft safety evaluation report and therefore should remain on the docket. Our 1995 request, Reference 4, indicated that the material provided in the Westinghouse letter of July 14,1993, was presentation material that was

'mtended for claritication only, not part of the formal review material and requested that the material be returned to Westinghouse. At the time this subject was being discussed with the NRC technical staff, the information was considered to be proprietary by Westinghouse since it contained information that had commercial value to Westinghouse. If this presentation material was indeed used by the staff in development of the AP600 draft final safety evaluation repon in November 30,1994, then at this time, over five years later, this information is no longer considered to be proprietary by Westinghouse.  ;

I This response addresses the proprietary issues delineated in the references.

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A Brian A. McIntyre, Manager M

Advanced Plant Safety and Licensing s , ., jml cc. J. W. Roc NRC/NRR/DRPM J. M. Sebrosky - NRC/NRR/DRPM W. C. Huffman - NRC/NRR/DRPM H. A. Sepp - Westinghouse i

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