ML20203H869

Summary of 980211 Meeting W/W in Rockville,Md Re W Opportunity to Respond to NRC Insp Rept 99900404/97-02,dtd 980128.List of Attendees & Meeting Handouts Encl

ML20203H869
Person / Time
Site:	05200003
Issue date:	02/19/1998
From:	Joshua Wilson NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
99900404-97-02, 99900404-97-2, NUDOCS 9803030347
Download: ML20203H869 (16)

Text

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February 19, 1998 APPLICANT: Westinghouse Electric Company j

FACILITY: AP600

SUMMARY

OF MEETING ON THE AP600 QUALITY ASSURANCE (QA) PRO- {

CSAM The subject msot!ng was held on February 11,1998, in the Rockville Maryland office of the I Nuclear Regulatory Commisslan (NRC), between representatives of the NRC staff and Westing-house Electric Company (WELCO). A list of the meeting attendees is provided in Attachment 1 and WELCO's presentation handouts are provided in Attachments 2 and 3.

The purpose of the meeting was to provide WELCO with an opportunity to respond to the NRC's inspection report (#99900404/97-02), dated January 28,1998, on WELCO's QA program for the j

AP600 design. During the meeting, the NRC staff expressed its concern with the adequacy of  !

the AP600 design given the discrepancies that were found in the AP000 design during the i NRC's inspection. Mr. Tupper presented WELCO's response to the items identified in the inspection report (Attachment 2) and stated that WELCO nas initiated a design assurance review for the AP600 design. Dr. LaPay summarized WELCO's design assurance review (Attach-ment 3), which will focus on the adequacy of the safety analysis documents that support Chapters 6 and 15 of the AP600 Standard Safety Analysis Report. Dr. LaPay willlead a team of 15 people that will review 24 out of approximately 200 packages of design documentation.

Mr. Tupper is the only team member that reports to the AP600 project. The NRC staff requested that the design assurance review be well documented and that the selection criteria for the initial documentation samples be included, along with the rationale for why the samples do not need to be broadened. In response to an NRC staff question, Mr. Vijuk stated that WELCO decided to perform a design assurance review rather that a root cause analyels. He also stated that WELCO will reassess the need for a root cause analysis after evaluating the results of the design assurance review. The NRC staff requested WELCO to present the results ofits design assurance review at a future meeting (after April 3,1998).

4 A draft of this meeting summary was provided to Westinghouse to allow them the opportunity to comment on the summary prior to issuance.

original signed by:

Jerry N. Wilson, Senior Policy Analyst Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation

/

/

Docket No. 52 003 2 Attachments: As stated b;._d,. ,...

k$,,_ba .-. i bot d gf s cc w/atts: See next page DISTRIBUTION:

• -"*'a a DOCUMENT NAME: A:\MTG-QA.WPD LIIlllull~i To receive a copy of this document, Indicate in the box: "C" = Copy without sttachment/ enclosure *E" = Copy with attachment / enclosure "N" = No copy OFFICE SPA:PDST:DRPM D;PDST:DRPMl l l NAME JNWilsonW TRQuay rT4 DATE 02/17/98 // 02/11/98 9003030347 900219 OFFICtAL RECORD COPY PDR ADOCK 05200003 O PDR

DISTRIBUTION w/aHehments:

Docket File PUBLIC PDST R/F TKenyon BHuffman JSebrosky D8caletti JNWilson DISTRIBUTION w/o attachments:

SCollins/FMiraglia. 012 G18 BSheron,012 G18 -

BBoger,012 G18 JRoe DMatthews l TQuay ACRS (11) .

l- JMoore,015 B18 l SBlack 0 9 A1 j RPettis. 0 9 A1 i

JPeralta,0 9 A1 BGramm,0 9 A1 RLandry,0 8 E23 EThrom,0-8 H7 JLyons, 0-8 D1 -

LSpessard,0-9 E4 RCaruso,0 8 E23 LLois,0-8 E23 SSun,0 8 E23 CBeriinger,0-8 H7 g o ', p i w A7 9

I

n Westinghouse ElecLic Corporation Docket No. 52 003 oc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 Nuclear and Advanood Technology Div!sion Office of 1.WR Safety and Technology Westinghouse Electric Corporation 19901 Germantown Road P.O. Box 355 s Germantown, MD 20874- l Pittsburgh, PA 15230 Mr. Russ Bell  !

Mr. B. A. McIntyre Senior Project Manager, Programs Advanood Plant Safety & Lloonsing Nuclear Energy Institute Westinghouse Electric Corporation 1776 l Street, NW _

Energy Systems Business UnN Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag Doc Search Associates Advanced Plant Safety & Lloensing Post Office Box 34 l Westinghouse Electric Corporation Cabin John, MD 20818 i

Energy Systems Business UnN

! Box 355 Dr. Craig D. Sawyer, Manager l Pittsburgh, PA 15230 Advanced Reactor Programs l

GE Nuclear Energy Mr. M. D. Beaumont 175 Curiner Avenue, MC 754 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation one Montrose Metro Mr. Robert H. Buchholz 11921 Rockville Pike GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781' Rockville, MD 20852 San Jose, CA 95125 Mr. Storiing Franks Barton Z. Cowan, Esq.

U.S Department of Energy Eckert Seamans Cherin & Mellott NE 50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. Charles Thompson, Nuclear Engineer PWR Design Certification AP600 Certification Electric Power Research Instituto NE 50 3412 Hillview Avenue 19901 Germantown Road Palo Alto, CA 94303 Germantown, MD 20d74 Mr. Robert Malers, P.E.

Pennsylvania Department of Environmental Protection Bureau of Radiation Protection

. Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469

=. __

PUBLIC MEETING WITH WESTINGHOUSE ON AP600 QUALITY ASSURANCE PROGRAM MEETING ATTENDEES FEBRUARY 11,1998 tl6ldg ORGANIZATION Jerry N. Wilson NRC/PDST/DRPM SUZANNE BLACK NRC/HQMB/DRCH ROBERT PETTIS NRC/HQMB/DRCH JUAN PERALTA NRC/HQMB/DRCH BOB GRAMM NRC/HQMB/DRCH RALPH LANDRY NRC/SRXB/DSSA EDWARD THROM NRC/SCSB/DSSA BOB VlJUK WESTINGHOUSE BRIAN MCINTYRE WESTINGHOUSE BOB TUPPER WELCO WILLIAM LAPAY WELCO/NSD TED QUAY NRC/PDST/DRPM JIM LYONS NRC/SPLB/DSSA JACK ROE NRC/DRPM LEE SPESSARD NRC/DRCH RALPH CARUSO NRC/SRXB/DSSA LAMBROS LOIS NRC/SRXB/DSSA SUMMER SUN NRC/SRXB/DSSA

! CARL BERLINGER NRC/SCSB/DSSA Attachment i

AP600 FinalInspection Report Action Plan Initiated efforts to address NRC concerns based on the information presented at the exit meeting 21 Items identified by NRC in January 28, report 15 Items have been closed All eight of the Requests for Additional Information have been responded to the staff Nine corrective action requests and a nonconformance notice have been issued by QA All but two of the corrective actions were in place prior to the NRC report Design Assurance Review (DAR) initiated, Dr. William LaPay is lead All Westinghouse actions (other than DAR) will be complete by February 27,1998 Additional corrective actions (if needed) will be defined by March 20,1998 5

5 I

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AP600 Final Inspection Report Action Plan Updated February 10,1998 Nonconformance 99900404/97-02-01 Item Calc. Note NRC findmg/ observation WELCO Respcase Responsible Compicuan or Due Date 01/I. SSAR<sSC-189 ~ Operator actionimpact needs to be Include Head Vents in Tech _ RomViuk - .

RAItoNRC

r hkd Specs. 1/9/98-See OITS 64113RAI 440.753F)

Respcnd to Of Co.M Ixk ofh=nesats supportingTech '

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01/2: CN-TA-95-83 ' Prepare Calculation _

RonVijuk1 '~

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Respond to 01 -;

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01/3 SEC-APS-4838- AP600 NOTRUMP Code errors. Define and implement correctrve R. A . Due3/15/98 C0 Jwifh% forjudgmg errorto be action for CAR 98-1013 insignificant not avaihble 01/4i SEC-APS-4837-C0 No L. 14 ofauthorw~ to - Evaluate Wrd=== to resolve 7

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'dl/5 SEC-APS-4746-C0 Explain basis forconclusion. ..

Respond to OpenItem n Novendstern RAItoNRC See Offs 6415. (RAI440.757F) _ a" 1/13 S 7 w _= ,. - - . . . -- .. .-

Defmc an!impicment corrective R.A- Due 2/27/98 action for CAR 97-1354 01/6 LTCT-T2C-417 Failure to fit curse to data and to justify Revise the calculatxm and provide R.Ao Due 2/24/93 A. continued use. jog;;, Lee.

01/6 LTCT-72C-418 - Bias applied w/ojustificaixa 0.2 psi -J . Revision 2 ofthee=1c=hekm 1 Novendstern 11/20/97 :

B." ' #chtri remlwd% ace 6'T :ssued. '

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Item Calc. Note NRC Tmdmg/ observation WELCO Response R + .= Jvic CompIction or Due Date 01/71 l SSARGSC 356 .WCOBRA/ TRAC-potential error m flow Assess whether thisis anerrorand R r- L ./ Response .

h u.uuks. updatedc = a%toaddress Kemper Prmi&d LY See OfTS 6413 (RAI440.755F)for concem. Respond to Oi, DCP/NRC122 detaiW _ __ _ . . _._ 191.

Derme and impicment wuet R.u 6. Due 2/27/98 action for CAR 97-1352 01/8. SSARGSC 377 Physacal Impossibilities - h iviani of; Assess whetherthis is an errorad . R-Au / -- RAItoNRC LTC water c. citing the piw. .

update ex =- - ' A+ to address Kemper I!!5/98 DVIreverse flowis not physcally concem. Respond to OI -

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possible 5 e OITS 6417 (RAI 440.756F) for deta'ds m_ mm _ _ .1 , . . - f 1. ; .

Defir.c and L..ykow ccrrective R,uh , Due 2/27/98 l action for CAR 97-1353 Nonconformance 99900404/97-02-02 02/1 ' WCOBRA/ TRAC R<m stail error in NID-NSA-95-362 not Redew squow..ma and prepare a R,u h o/ Due 2/27/98 entered into error tracking system WELCO pos: tion. Kemper  !

Close CAR 98-1014 02/2 ' GOTHICj ^:- Disposition oferror nohces from NAI ~ Aiiress errors percode error- Greshana

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Unresolved item 99900404/97-02-03 (See page 18,20,21,22 and 23 of NRC Inspecties Report) 03/1 CN-CRA-93-219/0 Provide duuommaaben ofjuMA of Revise calculation Gresham Due 2/27/98 mnM%+ inns made to CLIME model NR 97-453 n,4 2/4/98 03/2- SSARGSC 1251 Artificial term added to GO'IMIC for code A_w 4.iuMthatthis 4 G A .'Vaughn NR 97-453 '

4 stability which creates v.nergy was notan error.! See SAE-CRA-1 closed 1/2/98 '

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Westinghouse Review and Verification of AP600 Safety Analysis Documentation i

Objective Assess the adequacy of the AP600 safety analysis documents supporting Chapter 15 and the containment analysis portion of  :

Chapter 6 of the SSAR to satisfy the provisions of Appendix B ,

in 10CFR 50 E

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Westinghouse Review and Verification of AP600 Safety Analysis Documentation ,

Focus of Review -

! Safety related calculations that form the basis for Chapter 15 and the containment analysis portion of Chapter 6 of the SSAR i

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Westinghouse Review and Verification of AP600 Safety Analysis Documentation -

Areas to be Reviewed .

The review will focus on

,

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! (1) Large LOCA (2) SmallBreak LOCA (3) Non-LOCA Analysis (4) Containment Systems i (5) Long Term Cooling l (6) Radiological i

Three distinct areas will be evaluated in each of the above items:

(1) plant configuration input; (2) analysis; (3) and V&V.

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i Westinghouse Review and Verification of AP600 Safety Analysis Documentation REVIEW PROCESS

1. Develop a sample selection based on the matrix shown on Figure 1.

2. Establish the review criteria

3. Perform calculation reviews

4. Characterize and document review results

l 4

Westinghouse Review and Verification of AP600 Safety Analysis Documentation Figure 1 - Review Focus Matdx Amhshea Impt Amh* CodeVAV l

w ae* LOCA X i

SmmH BenLOCA X X X  !

n=tocA x i

.; t i

o s 2 -. = x x x  :

l RmMgical X  ;

i ImgTermcootmg X X f

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Westinghouse Review and Verification of AP600 Safety Analysis Documentation l

Reviewers' Criteria

1) Applicability of the analysis and modeling methods and engineering assumptions (judgments)

2) Reference to current analysis or design input

3) Competency of the engineer and verifier in understanding methodology and procedures

4) Verification techniques used by the verifier

5) Verification of computer codes, macros, and error reports

6) Adequacy and clarity of documentation

7) Accuracy ofportions of the analysis calculation selected for review

Westinghouse Review and Verification ,

of AP600 Safety Analysis Documentation i Review Process - Criteria Continued ,

I Reviewer shall document conclusions or observations related to any of the above items, or where there were difficulties l due to content of the calculation selected for review i

Reviewer shall contact the responsible engineer and/or verifier when necessary for clarification or to address questions

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~ Westinghouse Review and Verification of AP600 Safety Analysis Documentation I

REVIEW SCHEDULE:

Sdectionofteanisarmies Februny9,1998 ReviewStart Februsy10,1998 ReviewCornpicte Mm:h20,1998 Project G-...ma on Review March 27,1998 Issue Ae_ Report April 3,1998 4

CORRECITVE ACTIONS:

CouddcbyApril30,1998

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