ML20236R027

Summary of 871029 Meeting w/C-E in Bethesda MD Re Executive Overview of CESSAR-DC Sys 80+ Design Certification Program. List of Attendees & Viewgraphs Encl

ML20236R027
Person / Time
Issue date:	11/10/1987
From:	Vissing G Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
PROJECT-675A NUDOCS 8711230034
Download: ML20236R027 (60)

Text

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NUCLEAR REGULATORY COMMISSION p

W ASHINGTON, D. C. 20655 8

%,.... +,e November 10, 1987 Project No. 675 MEMORANDUM FOR:

The record TROM:

Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate-Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

SUMMARY

OF MEETING WITH COMBUSTION ENGINEERING FOR AN EXECUTIVE OVERVIEW OF THE SYSTEM 80+ DESIGN PROGRAM OCTOBER 29, 1987 INTRODUCTION A meeting of the NRR executives with representatives of Combustion Engineering (CE) was held at the NRC offices in Bethesda, Maryland, on October 29, 1987.

The purpose of the nieeting was for CE to present an executive overview of the CESSAR-DC System 80+ Design Certification Program. provides a list of those in attendance. Enclosure 2 provides the status of the program to date. Enclosure 3 provides the viewgraphs which CE used to discuss their proaram.

DISCUSSION The propcsed Licensing Review Bases was submitted on July 2,1987. The staff provide comments and it was resubmitted on October 29, 1987. This document is process oriented.

It has no design information.

Chapter 1, Introduction, was submitted in September and it is under review.

Section 10, Power Conversion, which will contain many of functional interface requirements was scheduled for submittal for the end of October. Also, Section 17, QA, was scheduled for submittal for the end October. We have had six meetings with the staff beginning with the Executive Briefing of April 2, 1987, and including meetings on PRA, approach to severe accidents and arproach to GSI and USI resolution. The next major meeting will be with the staff on November 19, 1987.

The System 80+ for design certification will be built upon the current System 80 design which has a FDA.

This FDA is not presently forward referencable to the only plant which has a Preliminary Design Approval (PDA), WNP-3. There are three open issues remaining to be resolved.

Also the FDA needs to be amended i

to incorporate the requirements of the Severe Accident Policy.

'(CEhas proposed that the Severe Accident Policy be an interface requirement for this first amendment of FDA-2.) Their goal is to have an amended FDA-2 with the three open issues resolved for WNP-3 and which will be forward referencable to i

871.1230034 B71110 PDR PROJ 675A PDR 1

i 1

% i I

WNP-3, the only plant which holds a PDA. FDA-2 would again be amended for design certification of System 80+ design to satisfy tha Severe Accident Policy, approve revisions to the System 80 design which CE propose and to completely close out the three open issues on the current design.

The current System 80+ design will include changes to the current System 80 I

I design which CE desire to improve safety and reliability and to accommodate the EPRI ALWR requirements and which NRC mandated through the Safety Goal

.l Policy, the Severe Accident Policy and the Standardization Policy. The j

changes are not considered to be great. CE has characterized the System 80+

to be a revision of System 80.

i The staff will receive a total CESSAR for review and may find better ways to l

design areas which have been accepted for System 60. However, CE believes l

l that the staff should be limited in their resolution of these types of concerns to only those releted to the three open issues.

Concern was expressed about interface requirements because it was this area which was most difficult to resolve for System 80. CE indicated that the interface requirements will be defined in much more detail.

If the staff j

would have problems in any area, CE invited questions which would resolve the 1

concerns.

Concern was also expressed & bout the capability to know every component which would effect a plant trip.

CE's response was to resolve these concerns through staff questions.

Concern was expressed on the capability to l

have a PRA through interface requirements. CE indicated that the interface requirements will also be quantified in PRA.

l Concern was expressed about the efficiency of the review process for System 80+.

The scope of the System 80+ was limited such that it would seem to take an additional two years of review for an operating license application. The l

l scope of the System 80+ includes: NSSS, Containment, Control Room, and Emergency Feedwater System. With such a limited scope, concern was expressed if this is what the Comission intended in the Standardization Policy Statement. The scope may float and if it does, design certification could also float.

CE was concerr.ed about the need for NRC criteria for severe accident issues, i

USis, GSIs and EPRI requirements.

i The viewgraphs provide descriptions of improvements and changes from the System 80 design. There will be no PORY but the system will have an improved depressurization system through motor operated valves. The pressurizer will be larger which will provide more time for response to transients. Most components including the steam generator will be able to be replaced. The systems will have a 60 year life with replacement. Much of the containment i

has not been determined yet. The RWST (500,000 gal) will be located in I

containment. Hydrogen burn issue must be resolved. The size of containment j

has not been decided or the method of removing heat. Containment vents have j

not been considered yet; however, this is an issue which will be considered.

The staff may need to do independent analyses on degraded core issues or accept the CE anlayses.

CE will use the MAAP code.

1 l

l i

j I

4 I

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The staff indicated that-the System 80+ design must be a safer plant then

-l d

currently built. The hearing for design certification will be a highly contested hearing. The licensing' review basis document must address the design assumptions much like the GE LRB and must address all other innportant -

issues.

)

J

,s j

g Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate

Enclosures:

As Stated i

l l

l l

l

November 10, 1987 s The staff indicated that the System 80+ design must be a safer plant then currently built. The hearing for design certification will be a highly contested hearing. The licensing review basis document must address the design assumptions much like the GE l_RB and must address all other important issues.

original signed by Guy 3. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate

Enclosures:

As Stated DISTRIBUTION:

': Central File ' "

' Local ~PDR" PDSNP Reading LRubenstein GVissing EHylton 0GC-BETH EJordan JPartlow NRC Participants ACRS(10)

HBClayton, RI i

I

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l

t' November 10, 1987

+.

, l The staff indicated that the System 80+ design must be a safer plant then currently built. The hearing for design certification will be a highly l

contested hearing. The licensing review basis document must address the 4

design assumptions much like the GE LRB and must address all other important issues.

j origjnal signed by 3

Guy 5. Vissing, Project Manager-q Standardization and Non-Power Reactor Project Directorate 1

Enclosures:

l As Stated DISTRIBUTION:

Central File Local PDR PDSNP Reading LRubenstein GVissing EHylton I

OGC-BETH l

EJordan JPartlow j

NRC Participants l

ACRS(10)

HBClayton, RI

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i Encl o'sure ' l -

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ATTENDANCE LIST l

E MEETING OF CE WITH NRR EXECUTIVE STAFF CONCERNING

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CESSAR-DC SYSTEM 80+ DESIGN CERTIFICATION PROGRAM OCTOBER 29, 1987' I

1 l

NAME ORGANIZATION

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Guy 5. Vissing NRR/PD5NP Ashok Thadani NRR/ DEST-Conrad McCracken NRR/ECEB Don McPherson NRR Frank Miraglia NRR Larry Shao NRR.

R. Starostecki NRR T. E. Murley NRR i

D. Crutchfield NRR-J. Richardson NRR.

J. Norberg NRR/ DEST Frank Rosa

' DOE Michael D.-Green CE Greg-Snipes Duke' Power j

George Davis CE Regis Matzie CE-Mark Rubin NRR/ DEST l

Paul Leech NRR/PDSNP Dino Scaletti NRR/PDSNP Dean Houston MRC/ACRS Staff Charles Brinkman CE Bethesda A. Edward Scherer CE' q

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REVIEW STATUS

~~~

SYSTEM 80+ DESIGN ' #:

ITEM SUBMITTAL DATE RAI

RESPONSE

LICENSING BASIS GUIDELINES 7/2/87 7/19/87 10/30/87T SECTION 1, INTRODUCTION 9/18/87 11/20/87T 1/10/88T SECTION 10, POWER CONVERSION 10/30/87T 12/15/87T 2/01/87T SECTION 17, QA 10/30/87T 12/15/87T 2/01/87T l

EETINGS

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4/2/87 EXEClITIVE BRIEFING - KICKOFF OF SYSTEM 80+ DESIGN 6/2/87 SCOPE OF PRA FOR SYSTEM 80+

8/3/87 EXECUTIVE BRIEFING - APPROACH TO SEVERE ACCIDENTS 8/12/87 STAFF BRIEFING - APPROACH TO SEVERE ACCIGNT ISSUE l

8/25/87 PRA ftTHoDOLOGY FOR SYSTEM 80+ DESIGN 9/17/87 APPROACH TO GSI AND USI RESOLUTION 10/29/87 EXECUTIVE O/ERVIEW OF SYSTEM 80+ DESIGN

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i CESSAR DESIGN CERTIFICATION PROGRAM SYSTEM 80+ KICKOFF MEETING EXECUTIVE

SUMMARY

DATE: OCTOBER 29, 1987 COMBUSTION ENGlHEERING, INC.

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CESSAR DESIGN CERTIFICATION EEDGB8M SYSTEM 80+ KICK 0FF MEETING l

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EXECUTIVE

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OCTOBER 29, 1987

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COMBUSTION ENGINEERING, INC.

COMBUSTION ENGINEERING

1 AGENDA SYSTEM 80+ KICK 0FF MEETING -

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OCTOBER 29, 1987 1:00 - 1:20 PROGRAM OVERVIEW A. E. SCHERER AND SCHEDULE l

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i ACTIVITIES T0-DATE AUGUST 30, 1985

- REQUEST FOR FORWARD REFERENCEABILITY MARCH 24, 1987

- PROGRAM INTRODUCTION TO NRC MANAGEMENT JUNE 2, 1987

- KICK 0FF MEETING FOR SYSTEM 80+ PRA JULY 2, 1987

- SUBMITTAL OF DRAFT LRB DOCUMENT AUGUST 12, 1987

- KICK 0FF MEETING FOR SYSTEM 80+

DEGRADED CORE ANALYSIS AUGUST 25, 1987

- MEETING ON PRA METHODOLOGY SEPTEMBER 17, 1987

- KICK 0FF MEETING FOR RESOLUTION OF USIs/GIs SEPTEMBER 18, 1987

- SUBMITTAL OF CESSAR-DC CHAPTER 1 SEPTEMBER 18, 1987

- C-E PROPOSAL FOR DUAL DOCKETS SEPTEP'BER 18, 1987

- REQUEST FOR CLOSE0VT OF ATWS ISSUE SEPTEMBER 18, 1987

- REQUEST FOR CLOSE00T OF AUXILIARY PRESSURIZER SPRAY ISSUE SEPTEMBER 18, 1987

- REQUEST FOR CLOSE0VT OF SG TUBE VIBRATION ISSUE OCTOBER 13, 1987

- NRC RESPONSE ON DUAL DOCKETS coassusnomhancemasatus

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