ML20028F752

Presents Overview of Westinghouse Advanced PWR Project. Westinghouse Intends to Submit Preliminary Design Info During Current Pretendering Phase

ML20028F752
Person / Time
Issue date:	01/26/1983
From:	Meyer G Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
PROJECT-668A NUDOCS 8302040131
Download: ML20028F752 (33)

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-4 JAN 2 61983 Project No. 668 MEMORANDUM FOR: SEE DISTRIBUTION FROM:

Gary C. Meyer, Project Manager Standardization & Special Projects Branch Division of Licensing

SUBJECT:

WESTINGHOUSE ADVANCED PWR STANDARD DESIGN l

J The purpose of this memorandum is to present to designated NRR reviewers, a quick overview of the Westinghouse Advanced PWR (APWR) project. Enclosure 1 lists the technical reviewers assigned to this project in response to 1

D. Eisenhut's memorandum of December 21, 1982.

l A " kick-off" meeting with Westinghouse was held on November 30, 1982. Encl osure i

2 is a summary of this meeting. Enclosure 3 is a nonproprietary copy of the j

slides presented by Westinghouse. The first thing you should note from these enclosures is the schedule for this project. We are currently in a pretendering phase during which Westinghouse intends to submit preliminary design information to the staff. T.,is infomation is to be submitted as a series of system modules, I

each of which will fom the basis for design review meetings between Westinghouse and the staff.

Westinghouse currently intends to overlap the pretendering phase with the start l

of an actual review by making fomal application within the next few months.

I This schedule is still under negotiation, however, so we will restrict our attention, for now, to the pretendering phase only.

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Thus far in the pretendering phase, Westinghouse has submitted three documents:

1) the WAPWR Licensing Control Document; 2) Module 1. - Primary Side Safeguards; and 3) Module 2 - Secondary Side Safeguards. The first two of these have been distributed. Module 2 will be distributed during the first week r,f February.

! is a copy of the distribution to be used for the pretendering l

material from Westinghouse.

If you have any questions or changes to this 0l distribution, please contact me as soon as possible.

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sun m e) 8302040131 830126 gonroeseenvweg nac rORM 318 00-80) NACM ONO OFFICIAL RECORD COPY usceo. mi-m m

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JAN 2 61983 The cover letter for the WAPWR Licensing Control Document (LCD) explains how Westinghouse intends to use it in their licensing program. We have been asked to review this document from the standpoint of completeness in addressing new or potential future requirements. Accordingly, each reviewer is requested to look at the LCD within the context of their particular review area. Formal written responses are not required, however, if you have specific comments, please call or send me a note at your earliest convenience. Your familiarity with the document should facilitate the future stages of this review.

Primary Side Safeguards (Module 1) will be the subject of the first design review meeting with Westinghouse.

I am tentatively planning to schedu e this meeting for the first week of March. This schedule is, of course, dependent upon our ability to conduct a meaningful review of Module 1 within this time frame. Again, fomal written reviews are not expected nor desired, however, preliminary hand written comments should be available from each of the affected reviewers at least three days prior to the review meeting. If you can not meet this schedule, please call me as soon as possible.

All affected reviewers are requested to add to their RAMS Sheets: Project #668 I

P. A. #141211.

If you have any questions, please call me (x29787) or stop by my office (Room 450).

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/9 Gary C. Meyer, Project Manager Standardization & Special Projects Branch i

Division of Licensing Enclosures :

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f DISTRIBUTION:

Document Control NRC PDR PRC G. Meyer P. Anderson l

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DISTRIBUTION:

F. Miraglia C. Thomas W. Jensen J. Joyce C. Tinkler G. Harrison P. Gill Shih-Liang Wu H. Richings G. Schwenk J. Read J. Mitchell E. Markee J. Lee F. Skopec H. Shaw N. Chokshi S. Chan G. Geise-Koch J. Kane W. Hazelton R. Klecker J. Schiffgens C. Y. Chang G. Bagchi A. Masciantonio J. Stang S. Kirslis s

A. Bus 11k F. Loffman j

ENCLOSURE 1 4

PROJECTN668 WESTINGHOUSE ADVANCED PWR DESIGN ASSIGNED REVIEWERS DIVISION BRANCH NAME DSI RSB W. Jensen ICSB J. Joyce CSB C. Tinkler ASB G. Harrison PSB P. Gill CPB Shih-Liang Wu H. Richings G. Schwenk AEB J. Read J. Mitchell ETSB E. Markee J. Lee RAB F. Skopec DE MEB H. Shaw SEB N. Chokshi S. Chan GSB G. Geise-Koch HGEB J. Kane MTEB W. Hazelton R. Klecker J. Schiffgens C. Y. Chang EQB G. Bagchi A. Masciantonio CMEB J. Stang

.S. Kirslis DST RRAB A. Buslik F. Coffman

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' UNITED STATES

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og NUCLEAR REGULATORY COMMISSION o

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E WASHINGTcN. D. C. 20555 k,,,,f DEC 13198 s..

Project No.:

668 APPLICANT: WESTINGHOU'SE ELECTRIC CORPORATION FACILITY:

Advanced.PWR Standard Design

SUMMARY

OF NOVEMBER 30, 1982 MEETING WITH WESTINGHOUSE ON ITS ADVANCED PWR STANDARD DESIGN On November 30, 1982, members of the NRC staff met with representatives of Westinghouse to discuss the Westinghouse Advanced PWR (APWR) standardization program. is the list of attendees from this meeting. The meeting was held, at Westinghouse's request, as a kick-off meeting with the NRC technical staff. Westinghouse presented an overview o.f its program including a proposed schedule for the NRC review leading to the issuance of an FDA in mid 1986.

One of the Westinghouse's objectives in this program is to " optimally address new and potential future licensing requirements in the W APWR design... with the goal of achieving assurance that the fundamental W XPWR design will re:ain relatively unchanged as a result of future regulatory changes."

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achieve this objective, Westinghouse has requested the NRC's involvement earlier in the design process than is " traditionally" expected.

The NRC would then be able to influence certain basic design selections by providing early feedback on Westinghouse's analyses of design alternatives.

To initiate and guide the review process, Westinghouse has prepared the "W APWR Licensing Control Document." This report, dated August 1982 is intended tc {l) present the bases for the W APWR design in response to new or potential future licensing requirements, and (2) indicate Westinghouse design, analysis evaluation, and licensing documentation intentions for the Westinghouseha)detailsofthisdocumentwillbereviewedinconcertrequested s W APWR.

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The technical with the design modules discussed below.

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DEC 15198;2 The first phase of the technical ritvik, proposed 5'ylestinghouse, is to be

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conducted pretendering.

Westinghouse proposes to prepare a number of system design modules to 1) provide W APWR design Betail; 2). establish SAR documen-tation requirements; and 3) reflect Licensing Control Document commitments in order to obtain NRC agreement with design basis and to obtain NRC feedback on design options. These modules would be reviewed and form the basis for discussions at design review meetings.

Formal written evaluations would not be prepared.

Feedback would be provided in the form of design review meeting' minutes.

To this end, Westinghouse has submitted the first two modules:

1)

Primary Side Safeguards,i and 2) Secondary Side ; ifeguards.

Review of these documents will be initiated in the near future.

The staf' 's initial reaction to Westinghouse's proposal was an expression of f

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concern about our ability to conduct a phased " modular" review without the benefit of an overall design document.

In particular, R. Mattson suggested that Westinghouse accelerate its plans for submitting a PRA.

In response, Westing-house agreed, as a first order of business, to meet with the staff to discuss the content and schedule of the W APWR PRA.

t' Gary Meypr Project Manager ase.

Standardization & Special Projects Branch Division of Licensing cc:

D. Eisenhut F. Miraglia Meeting Attendees e

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11/30/82 NEETING W/WESTINGHOUS$

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ON A-PWR DESIGN ATTENDEES s.-

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__l NAME AFFILIATION C. Thomas NRR/DL G. Meyer NRR/DL

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J. Rosenthal NRR/DSI R. W. Houston NRR/DSI R. Mattson NRR/DSI R. Capra NRR/DSI E. Rossi NRR/DSI-W. Gammill NRR/DSI L. Rubenstein NRR/DSI W. Johnston NRR/DSI L. Soffe'.-

NRR/DE R. Bosnt_k NRR/DE J. Read NRR/DSI G. Lear NRR/DE W. Butler NRR/DSI J. Chandrasekaran NRR/DSI C. Nichols NRR/DSI R. S. Lee NRR/DSI J. P. Knight NRR/DE D. Muller NRR/DE,

" " F.. Thomson Westinghouse R. Vijuk Westinghouse s

D. Bevard Westinghouse B. Luce Westinghouse N.S.

T. Johnson Westinghouse Plant Design Integration

- L. Conway Westinghouse APWR Fluid System Design T. Schulz

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NUCLEAR REGULATORY ddMMISSION - WESTINGHOUSE I

ADVANCED PRESSURIZED WATER REACTOR PROGRAM KICK-OFF MEETING NOVEMBER 1982 I

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Introduction

• Licanalng Control Document

= General Program Description

= Purpose

= @ APWR Organization

= Format

= Licensing Objectives and Approach

= Content Westinghouse /Mitsubishi Program

= Examples.and Matrix

= Organization

• System Design Modules

= Fundamental Design Objectives I

= Purpose

= Design Considerations

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= Format 1

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= Program Schedule

= Schedule i

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Licensing Program

• Summary i

= Objectives and Elements 1

'= Nuclear Power Block

= Program Schedule,,

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w APWR GENERAL PROGRAM DESCRIPTION Japanese involvement ll.S. Utility involvement

= @/MH1 Major. Design

=; Utilities Co-Development Program l

• Commonwealth Edison

• Final design detail by 1985

• Tennessee Valley Authority

• Design tests completed by 1984

• Duke Power

• Verification testa completed by 1986 American Electric Power

= Japanese Utility Consortium i

e Texas Utilities

• REP submittal by late 1985

• Public Service Electric and Gas

• Final design submittal by late 1986 Wisconsin Electric Power Southern Company Belgian involvement

= Informal technical review

= Project / policy overview

= Technical evaluations i

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@ APWR ORGANIZATION

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(ENGINEERING)

Advanced APWR Development R. A. George 1

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I Plant Design AP.WR Reactor APWR Fluid.

APWR Reactor i

Integration Equipment Design Systems Design Equipment Testing T. van de Venne J. A. Drake C-K Kim J. D. Nastasy 1

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i APWR Core Steam Generator AdvancedI&C Electrical Systems l

Design integration Engineering Mechanical Dev.

B.M. Cook E. G. Herrick l

S. Cerni R. M. Wilson i

Advanced Plant &

Fuel Licensing D. G. Bevard D

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W APWR W APWR ORGANIZATION (NUCLEAR SAFETY)

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Nuclear Safely Deparlment Manager E. P. Rahe, Jr.

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I Product Risk Assessment Strategic Safeguards i

Licensing Technology Licensing Eng. & Development D. H. Rawlins D. C. Richardson D. W. Call F.F.Cadek

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Domestic Plant Probabilistic Risk Advanced Plant &

Safeguards

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Fuel Licensing Analysis Licensing Assessment D. G. Bevard I&C Systems Transient Operational Licensing Analysis Licensing Safeguards Analysis

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initiatives

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Mechanical Equipment

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Core, Containment, &

Reload Fuel &

& Systems Licensing Cons. Analysis Strategic Programs Forces Analysis I.lconsing

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International Application

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Plant Licensing Progrhmming Methode T/H Testing HCS Components Licensing Analysis T/H Methods s

o W APWR LICENSING OBJECTIVES AND APPROACH

• Final self standing one-step design certification through rulemaking by 1987

• Preliminary design certification by 1985

• Licensing control document

• NRC(Utility involvement in design selections

• Improved SAR format (system based)

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• SAR and SER " construction"

• Continued ACRS involvement

• Overalllicensing perspective

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W APWR WESTINGHOUSE /MITSUBISHl-APWR PROGRAM ORGANIZATION l,_, ingot.....

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APWR Program l

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Engineering Meneger i

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MAPI MELCO Engineering Engineering Department (N.I.)

Center (T.I.)

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W APWR APWR FUNDAMENTAL ~

DESIGN OBJECTIVES

• Improvement of plant availability

= Extended fuel cycle operaflon

= Rationalization of the periodic inspection

= 1mprovement of plant reliability

• Improvement of nuclear power economics

= Reduction of fuel cyc.le cost

= Reduction of construction cost

= Conservation of uranium resources e improvement of plant operability

= 1mprovement of. man-machine interface

= lmprovement of capability to respond to power grid requirements e improvement of load follow capability

• Automatic frequency control e Decrease in plant startup and shutdown time

• Capability to withstand grid frequency changes l

• Reductions in radioactive waste, effluents, and radiation exposure

W APWR

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APWR PROGRAM SCHEDULE

• Design Development Early 1979 - Mid 1981

• Design Evaluation / Selection Mid 1981 - Mid 1983

• Final Design Detail Late 1982 - Early 1985

• Testing and Verification Early 1984 - Late 1986 i

• Plant Construction / Operation Mid 1992 (Japan)

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@ APWR LICENSING PROGRAM OBJECTIVES Obtain a licensed standard plant design

[through rulemaking) that:

= Can be used for one-step licensing

m. Meets all NRC licensing criteria m Provides future assurance of fundamental design

= Incorporates all plant safety functions and reduces interface problems

= Provides a mechanism for possible early utility tie-in t

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@ APWR LICENSING PROGRAM

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ELEMENTS j

• Probabilistic based design

• Nuclear power block concept

• Clear addressment of all NRC licensing regulations and guidance

• Incorporate NRC and Utility feedback L

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(S) APWR LICENSING PROGRAM

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1982 1983 1984 1985 1986 1987 1l2 3l 4 1 l 2 l -3 l 4 1l2l3l4 1l2l3l4 1l2l3l4 1l2l3l4 PROGRAM KICKOFF MEETING WITH HRC 11/82 9 LICENSING CONTROL DOCUMENT (LDC) SUBHITTAL 11/82 9 LCD COMPLETENESS REVIEW 11/82 O O 3/83 12/83 11/82,

- 2/84 PRET5NDERING ALTERNATE DE SIGN DISCUSSIONS COMPLETE

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NRC DISPOSITION OF PRETENDERING 1/83' 4/84 HODULAR PRELIMINARY SAR APPLICATION 3/1 3O O 8/E 4 HODULAR PRELIMINARY SERS 6/83 0,

O 10/84 MODULAR FINAL SAR SUBNITTALS 12/83 C O 12/85 H0DULAR FINAL SERS 2[84 O

O 2/86 START Fl NAL ONE-STEP SI RS CERTIFICATI( N APPLICATION 10/82 FDA 10/86 NPB LICENSING 11/82 0 0

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0 1/87 3/83 PREL. 1/85 (PDA) 2/06 5/86 RULEMAKING PRETENDEP.IN SERS COMPLETE

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W APWR LICENSING CONTROL DOCUMENT PURPOSE

• In r,esponse to new or potential future licensing requirements:

= Establish the basis for the @ APWR design

= Indicate Westinghouse design, analysis / evaluation, and licensing documentation intentions for the

@ APWR

• Such that:

= Both current and anticipated licensing requirements and guidance are considered as an integral part of the

@ APWR Design Program i

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= Fully and directly addressing all regulatory requirements and concerns l

s,y APWR

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LICENSING ' CONTROL DOCUMENT FORMAT

• Identification of licensing issues f

= NUR$G's '(including race.nt SER's)

= Federal register notices

= NRC letters

= Other NRC regulatory guidance (regu.latory guides, discussions with the ' staff, etc.)

• Discussion of issues

= 14RC staff "words" were used to the extent practical

= Discussions are augmented (as appropriate) with

@ APWR design information/ status.

@ APWR response

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= Design commitment

= Analysis / evaluation commitment i

= Documentation commitment l

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W APWR LICENSING CONTROL DOCUMENT CONTENT

• Section 1.0 Introduction

• Section 2.0 Licensing Requirement Sources

• Section 3.0 Post-TMI Requirements and Recommen,dations-

• Section 4.0 Unresolved Safety issues

• Section 5.0 Generic Safety lasues

• Section 6.0. - Regulations and Regulatory Guidance e Section 7.0 Licensing Requirement Matrix e

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W APWR LICENSING REQUIREMENT MATRIX d

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Com-Pro-System ponent Analysis cedure Licensing A

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Control Document item TMIlasue A e

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SYSTEM DESIGN.MODOLES

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W APWR SYSTEM DESIGN. MODULES PURPOSE l

• Provide @ APWR design detail

• Establish SAR documentation requirements

• Reflect licensing control document commitments in order to:

• Obtain NRC agreement with design basis

• Obtain NRC feedback on design options

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FORMAT

• Sectioh 1.O - S'ystem Functions a Safety functions

= Non-safety functions i.

• Section 2.0 - System Design Basis

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= Limiting safety criteria (shall)

= Performance and design goals (should)

• Section 3.0 - System Description

= Including power supplies, Instrumentation, wafer requirements, etc.

l e Section 4.0 - Design Evaluation

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= Demonstrate conformance with design basis

= Including detailed indication of coinpliance with SRP i

j acceptance criteria, regulatory guide positions, NUREGS, and other regulatory guidance

• Design evaluations will not be complete in Inillal packages 4

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Schedule

• Module 10/15/82 j

o Primary Side Safeguards System 11/15/82 o Secondary Side Safeguards System 12/15/82 o Containment Heat Removal System 1/15/83

• Emergency SealInjection System 2/15/83

• Chemical and Volume Control System 3/15/83

• Component Cooling Water and Service, Water Systems 3/15/83

• Emergency Electrical Power 4/15/83

• Reactor Vessel / internals / Core Design -

5/15/83

• Reactor Coolant System 6/15/83

• Integrated Control / Protection System 9/15/83 1

• Plant Layout 11/15/83

• Advanced' Steam Generator Design

'I 1/15/83 e Nuclear Power Block Definition 7/15/83 j

e Systems Interactions Program 2/83 - 3/84 e Other System / issue Modules j

• Schedules are Flexible

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SUMMARY

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SUMMARY

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WHAT DO WE WANT

• To get started -

i e NRC agreement with approach and schedule

• NRC resource allocation

• Organized. review

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ENCLOSURE 4 o

DISTRIBUTION LIST FOR PROJECT 668.WESTINGHOUSEADVANCEDSWR RECIPIENT 1.TR ENCL

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l AD/SA 1

0 BC SSPB 1

0 LA SSPB 1

0 PM G. Meyer 1

1 ELD 1

0 NRR/DE/MEB 1

1 NRR/DL/DIR 1

0 NRR/DSI/AEB 1

1 NRR/DSI/ASB 1

1 NRR/DSI/CPB 1

1 NRR/DSI/CSB 1

i NRR/DSI/ETSB 1

1 NRR/DSI/ICSB 1

1 NRR/DSI/PSB 1

1 NRR/DSI/RSB 1

1 NRR/DSI/RAB 1

1 NRR/DE/CEB 1

1 NRR/DE/HGEB 1

1 NRR/DE/SEB 1

1 NRR/DE/GSB 1

1 NRR/DE/EQB 2

2 NRR/DE/MTEB 1

1 NRR/ DST /RRAB 2

2 s

NRR/ DST /DIR L

1 Reg File 1

1 RM/DDAMI/MIB 1

0 ACRS 10 10 NRC PDR 1

0 NSIC ?

1 0

NTIS ?

1 0

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