ML20149F488

Summary of 940726 Meeting w/ABB-CE in Rockville,Md Re Form & Content of Design Control Document for ABB-CE Sys 80+ Std Plant Design

ML20149F488
Person / Time
Site:	05200002
Issue date:	08/04/1994
From:	Stewart Magruder Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9408100310
Download: ML20149F488 (17)

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f nauqjo UNITED STATES

,, g y g NUCLEAR REGULATORY COMMISSION 5 e p WASHINGTON, D. C. 20555 4, ,8 August 4, 1994 f Docket No.52-002 APPLICANT: ABB-Combustion Engineering, Inc. (ABB-CE)

PROJECT: CE System 80+

SUBJECT:

PUBLIC MEETING 0F JULY 26, 1994, REGARDING THE FORM AND CONTENT OF THE DESIGN CONTROL DOCUMENT FOR THE ABB-CE SYSTEM 80+ STANDARD PLANT DESIGN On July 26, 1994, a public meeting was held at the U.S. Nuclear Regulatory Commission (NRC) headquarters in Rockville, Maryland, between representatives of ABB-CE and the NRC.

Enclosure 1 is a list of attendees and Enclosure 2 is the hand-out material presented by ABB-CE at the meeting.

The purpose of the meeting was to solicit ABB-CE's ideas on the form and content of the design control document (DCD) for the System 80+ standard plant design. The NRC is planning on publishing generic guidance on the DCD soon and used this meeting to discuss various options with ABB-CE. Major topics of discussion during the meeting included:

The treatment of proprietary references Whether or not to include Emergency Operations Guidelines (E0Gs) in the DCD Defining the scope of Tier 2*

The treatment of Combined License (COL) Information Items The treatment of the information contained in Chapter 19 of ABB-CE's Cembustion Engineering Standard Safety Analysis Report Design Certifica-cion (CESSAR-DC)

The treatment of conceptual design material The schedule for completing the DCD The NRC committed to provide a prompt response to ABB-CE's questions regarding (1) the protection of proprietary references, (2) the need to include EOGs in iOh g\,

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NRC RLE CENTER COPY  !

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August 4, 1994 the DCD, and (3) the treatment of conceptual design material. In addition, the NRC emphasized the importance of careful editing of the probabilistic risk assessment material in Chapter 19 to ensure that important design information is not deleted.

ShNaNL.'NahudN,ProjectManager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/ enclosures:

See next page DISTRIBUTION w/ enclosures:

Docket File PDST R/F DCrutchfield RArchitzel PDR PShea JNWilson SMagruder RWeisman, 0-15 B18 Distribution w/o enclosures:

WRussell/FMiraglia WTravers RBorchardt MFranovich 1Wambach TBoyce ACRS (11)

HTovmassian DTang RWeisman 0FC: LA:PDST:ADAR PM:PDST:ADAR SC:PQh:ADAR NAME: PShea ): ' " SMagruder: Ig RAr[tzel DATE: 08/b/94 08/1/94 08/Y/94 OfflCIAL RECORD COPY:

DOCUMENT NAME: MSUM0726.SLM 1

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the DCD, and (3) the treatment of conceptual design material. In addition, the NRC emphasized the importance of careful editing of the probabilistic risk assessment material in Chapter 19 to ensure that important design information is not deleted.

M Y. tt Stewart L. Magruder, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nt. clear Reactor Regulation

Enclosures:

As stated cc w/ enclosures:

See next page i

l ABB-Combustion Engineering, Inc. Docket No.52-002 cc: Mr. C. B. Brinkman, Director  !

Nuclear Systems Licensing .

ABB-Combustion Engineering, Inc.

Post Office Box 500 1000 Prospect Hill Road )

Windsor, Connecticut 06095-0500 l

l Mr. C. B. Brinkman, Manager Washington Nuclear Operations ABB-Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330  !

Rockville, Maryland 20852 ,

Mr. Stanley R. Ritterbusch, Manager Standard Plant Licensing ABB-Combustion Engineering, Inc.

Post Office Box 500 1000 Prospect Hill Road Windsor, Connecticut 06095-0500 l Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C. 205B5 Mr. Steve Goldberg Budget Examiner ,

725 17th Street, N.W. )

Washington, D.C. 20503 Mr. Joseph R. Egan, Esquire Egan & Associates, P.C.

2300 N Street, N.W., Suite 600 Washington, D.C. 20037-1128 Dr. Regis A. Matzie, Vice President Nuclear Systems Development ABB-Combustion Engineering, Inc.

Post Office Box 500 1000 Prospect Hill Road Windsor, Connecticut 06095-0500 Mr. Ernest L. Blake, Jr.

Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W. ,

Washington, D.C. 20037 i Mr. Ronald Simard, Director Advanced Reactor Programs l Nuclear Energy Institute  :

1776 1 Street, N.W., Suite 400 l Washington, D.C. 20006-3708 i

ABB-CE SYSTEM 80+

DESIGN CONTROL DOCUMENT FORM AND CONTENT MEETING ATTENDEES July 26,1994 Name Oraanization T. Wambach NRC T. Boyce NRC J. Wilson NRC S. Ritterbusch ABB-CE C. Brinkman ABB-CE R. Borchardt NRC P. Lang DOE D. Finnicum ABB-CE J. Longo ABB-CE H. Tovmassian NRC D. Tang NRC M. Franovich NRC S. Magruder NRC R. Weisman NRC M. Rowden Fried, Frank J. Beard GE R. Bell NEl Enclosure 1

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SYSTEM 80+ DCD .

PROPOSED DISCUSSION TOPICS

e OBJECTIVE J

e PRODUCE DCD MEETING LEGAL REQUIREMENTS WITH MINIMAL CHANGES TO EXISTING TEXT e TREATMENT OF DCD TOPICS eREFERENCES eEOGs e TIER 2*

e COL INFORMATION ITEMS e CHAPTER 19

SUMMARY

e CONCEPTUAL DESIGN MATERIAL e FORMATTING, ETC.

oSCHEDULE l e NRC RESPONSE i A ED ED l gz-a: 7%EpED

SYSTEM 80+ DCD PROPRIETARY REFERENCES e TREATMENT OF CESSAR-DC PROPRIETARY REFERENCES e SECONDARY REFERENCES NOT A FEDERAL REGISTER ISSUE L

e PREFERRED TREATMENT - RETAIN ALL PROPR!ETARY REFERENCES e ALTERNATIVE TREATMENT - DELETE ALL REFERENCES (Note - this was the initial staff position on references in the DCD.)

e NRC GUIDANCE NEEDED 4

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SYSTEM 80+ DCD EOGs e TREATMENT OF EMERGENCY OPERATIONS GUIDELINES e EOGs ARE NOT A PART OF CESSAR-DC e EOGs ARE OPERATIONAL VERSUS DESIGN e EOGs ARE GUIDELINES e EOGs WILL CONTINUE TO EVOLVE AS NEW INFORMATION IS DEVELOPED e ABB-CE INTENDS TO REFERENCE THE EOGs AND NOT INCLUDE

THEM IN THE DCD l

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SYSTEM 80+ DCD .

TIER 2*

e INDUSTRY - NRC MEETING AGREEMENT

. TIER 2* CONCEPT IS RETAINED

. DC APPLICANTS DIRECTED TO REVIEW THE STAFF'S FSER TIER

, 2* ISSUES AND PROPOSE CLARIFICATIONS e TREATMENT OF TIER 2*

. ABB-CE WILL REVIEW AREAS OF CESSAR-DC STAFF HAS '

CALLED UNREVIEWED SAFETY QUESTIONS AND PROPOSE A NARROWER AND MORE SHARPLY DEFINED SET OF TIER 2*

. ABB-CE WILL OBTAIN STAFF AGREEMENT l  :

. DCD WILL BE PUBLISHED WITH TIER 2* ITEMS DELINEATED ,

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SYSTEM 80+ DCD .!

COL INFORMATION ITEMS l

! e INDUSTRY - NRC MEETING AGREEMENT e COL ACTION ITEMS ARE FOR COL APPLICANTS INFORMATION

. i e COL ACTION ITEMS ARE NOT REQUIREMENTS e COL ACTION (EMS ARE PAGE HOLDERS FOR COL SAR e TREATMENT OF COL ACTION ITEMS e DCD INTRODUCTION WILL STATE THAT COL INFORMATION ITEMS ARE NOT REQUIREMENTS 1

e SIMILAR STATEMENT WILL APPEAR IN TEXT IN FRONT OF COL INFORMATION ITEM DISCUSSIONS

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SYSTEM 80+ DCD .

CHAPTER 19

e INDUSTRY - NRC MEETING AGREEMENT e NUMARC PROPOSAL FOR CHAPTER 19 IS ADEQUATE ASSUMING

, THAT THERE WILL BE A REQUIREMENT FOR COL HOLDER TO i UPDATE AND USE THE PRA l e STAFF PROPOSAL FOR COL- HOLDER'S USE OF PRA WILL BE i ADDRESSED IN A SEPARATE COMMISSION PAPER WHICH WILL PROPOSE A GENERIC RULE REQUIRING COL HOLDER TO MAINTAIN AND USE PRA e TREATMENT OF CHAPTER 19 e USE

SUMMARY

TREATMENT PER NUMARC PROPOSAL e SECTION 19.1 - INTRODUCTION e SECTION 19.8A - SHUTDOWN RISK EVALUATION REPORT e SECTION 19.15 -

SUMMARY

INCLUDING PRA INSIGHTS A BR ED se-m:_ 7%EDED

SYSTEM 80+ DCD .

CONCEPTUAL MATERIAL e NRC STAFF POSITION e CONCEPTUAL MATERIAL SHALL BE DELETED FROM THE DCD e SECTIONS REPLACED WITH STATEMENT " INTENTIONALLY BLANK" e ABB-CE TREATMENT PREFERENCE e DCD STATEMENT IN INTRODUCTION EXPLAINING THAT CERTAIN SECTIONS CONTAIN CONCEPTUAL MATERIAL WHICH IS IN PLACE FOR COMPLETENESS AND IS NOT A REQUIREMENT e CLEARLY DEllI4EATE CONCEPTUAL MATERIAL USING BRACKETS e THIS PROCESS MINIMlZES THE TEXTUAL CHANGES Ak Et Et gamm: P%EpEp

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I SYSTEM 80+ DCD .

FORMATTING, ETC.

t e THREE SECTIONS e INTRODUCTION t e CERTIFIED DESIGN MATERIAL l e APPROVED DESIGN MATERIAL eHEADERS e SYSTEM 80+ DESIGN CONTROL DOCUMENT .

1 eFOOTERS

! e INTRODUCTION REV.0 l e CERTIFIED DESIGN MATERIAL REV.0 '

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SYSTEM 80+ DCD .

FORMAT, ETC. (CON'T) e SECTION NUMBERING eIDENTICAL TO PRESENT CDM AND CESSAR-DC SECTIONS e liiTERNAL REFERENCES e DELETE REFERENCES TO DELETED MATERIAL IN CESSAR-DC e PAGE NUMBERING e GOAL IS TO MAINTAIN SAME PAGE NUMBERS e MAY REQUIRE USE OF ALPHABETIC SUFFIXES e STYLE -TEXT - ETC.

e NO CHANGE FROM CDM AND CESSAR-DC PROPOSED e CONSIDERATION OF NEW WORD PROCESSOR PROGRAM l A ER ER l p.1-1 P%EEEE l

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TREATMENT OF PRA SECTIONS IN DCD PRA WRITEUP SECTION TITLE STATUS COMMENT 19.1 Introduction RETAIN 19.2 Methodology Delete Reference to Section 19.2 in  !

CESSAR-DC 19.3 Initiating Event Delete Contains only calculations of Evaluation initiating event frequencies from generic data, i 19.4 Accident Sequence Delete Risk insights captured in 19.15 Determination 19.5 Data Analysis Delete Contains only documentation of failure rates used in the detailed analyses 19.6 Systems Analyses Delete Systems descriptions contained in other sections. Risk insights captured in 19.15 19.7 External Events Delete Risk insights captured in 19.15 Analysis 19.8 Shutdown Risk Delete Risk insights captured in 19.15 Assessment 19.8A System 80+ Shutdown RETAIN Contains the deterministic Risk Evaluation shutdown risk evaluation. Edit Report 19.9 Accident Sequence Delete Contains primarily core damage Quantification frequency calculations. Core damage frequency is not part of DCD. Risk insights captured in 19.15 19.10 Sensitivity Analyses - Delete Risk insights captured in 19.15 j level 1 19.11 Severe Accident Delete . Risk insights captured in 19.15 Phenomemology and and ITAACs Containment Performance for the System 80+ PWR

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i TREATMENT OF PRA SECTIONS IN DCD PRA WRITEUP SECTION TITLE STATUS COMMENT j Delete Contains primarily probability  !

19.12 Containment '

Response Analysis calculations. Risk insights captured in 19.15 19.13 Consequence Analysis Delete Contains large release frequency ,

calculation. Risk insights (

captured in 19.15 i 19.14 12 vel II and Ixvel III Delete Risk insights captured in 19.15  :

Sensitivity Analyses 19.15 Summary of PRA- RETAIN Reorganize to emphasize the [

Based Design Insights design related insights for level  !

1, level 2, level 3, shutdown risk i and external events analyses.

Delete probabilities. Summarize  ;

severe accident insights.

19.16 References Delete l 1

19A Design Alternatives Delete The conclusions of this analysis l are captured in the design as  ;

for the System 80+

described in other sections of the i Nuclear Power Plant DCD. [

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