ML20056E151
| ML20056E151 | |
| Person / Time | |
|---|---|
| Site: | 05200001, 05200002, 05200003, 05200004 |
| Issue date: | 08/17/1993 |
| From: | Stewart Magruder Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9308200124 | |
| Download: ML20056E151 (44) | |
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- August 17, 1993 l Docket Nos.52-001, 52-002,52-003, and 52-004 APPLICANTS: GE Nuclear Energy (GE), ABB-Combustion Engineering (ABB-CE), and Westinghouse Electric Corporation PROJECTS: GE Advanced Boiling Water Reactor (ABWR) and Simplified Boiling Water Reactor (SBWR), CE System 80+, and Westinghouse AP600
SUBJECT:
SUMMARY
OF MEETING HELD ON AUGUST 2, 1993, ON DESIGN CERTIFICATION REVIEWS On August 2,1993, a public meeting was held in Rockville, Maryland, between representatives of the U.S. Nuclear Regulatory Commission (NRC), GE, ABB-CE, Westinghouse, the Department of Energy (DOE), and the Advanced Reactor Corporation (ARC). The purpose of the meeting was to discuss the status of the design certification reviews for each of the evolutionary and passive reactor designs. Enc 70sure 1 is a list of those who attended the meeting.
l Dr. Murley of the NRC staff opened the meeting with a brief discussion of his recent trip to the Far East, and asked the industry representatives how they propose to handle the construction process for the new plants under 10 CFR Part 52. Specifically, he raised the issue of inspection activities during l
(and perhaps before) construction considering the fact that inspections, tests, analyses, and acceptance criteria (ITAAC) findings need to be abso-lutely final when they are made.
l l- D. Crutchfield of the NRC staff provided highlights of policy issues and the .-
status for each design from the NRC perspective. Specifically, he indicated that the staff had recently received the staff requirements memorandum (SRM) related to SECY-93-087, " Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor Designs," and that the Commis-sion for the most part agreed with the staff's positions included therein. A copy of the SRM would be made avaliable to each vendor in the near future. He also indicated that the Commission paper on the regulatory treatment of non-safety systems has been circulated and would soon be with the Commission.
For the ABWR, he indicated that the recent joint effort on the ITAAC was quite successful and resulted in the resolution of most of the 850 comments about GE's ITAAC submittal. Inputs for the final safety evaluation report (FSER) have been received by the project staff and are being assembled into the FSER.
The final inputs are expected not later than the end of September based on the final certified standard safety analysis report (SSAR) to be submitted by GE l on August 31, 1993.
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, s August 17, 1993 For the ABB-CE System 80+, he indicated that the tracking system for open items had been updated for consistency and that the number of open items had been reduced from about 500 to about 150. A meeting will be conducted on August 16, 1993, to discuss the status of all outstanding design issues, and a decision will be made about the start date for the ABB-CE ITAAC review.
For the Westinghouse AP600 design, he stated that the test matrix letter had been received and was under review. Further, all requests for additional information (RAls) had not been issued by June 30, 1993, but the schedule for the draft safety evaluation report (DSER) was not expected to be affected.
For the SBWR, he stated that progress was slow because of the ABWR review effort, but that the DSER date should not be significantly affected.
W. Russell provided a discussion of the highlights of the ABWR ITAAC meeting and stated that the "roadmap" issue discussed in a June 20, 1993, letter from the staff to NUMARC had been resolved. The first part of the resolution is that GE will provide a discussion in Section 14.3 of the SSAR describing the 1 process and the rationale that n s utilized to identify Tier 1 design certifi- .
cation information. The process wil! be illustrated using specific examples !
from selected safety analyses.
The second part of the resolution is that GE will provide a listing in Chapter 19 of the SSAR of the specific insights and key assumptions from various safety analyses that were identified as Tier 1 information by this process, without giving specific references to where the insights and analysis assump-tions are verified by the ITAAC. The safety analyses were previously agreed upon with GE, and include probabilistic risk analyses (FRA), severe accident analyses, and integrated plant safety analyses (e.g., design basis accidents, core cooling, shutdown risk). For the PRA and severe accident analyses only, the listing should show where each of the key assumptions and insights had been captured in the design in either the Tier 1 design information, the
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technical specifications (including administrative controls), the design and ~
operational reliability assurance programs, emergency procedures guidelines, and combined license (COL) action items.
Both the discussion in Chapter 14.3 and the listing in Chapter 19 would be retained in the SSAR and, subsequently, in the design control document (DCD).
The staff will review both the process description and examples, and write an SER for Chapter 14.3 that will describe the process and its results. The SER will also describe the NRC Tier 1 review process and the basis for the staff's conclusion that the ABWR ITAAC meet the "necessary and sufficient" standard of 10 CFR Part 52.
In a separate submittal, GE will provide a matrix of assumptions and insights from key analyses, with a cross reference to the specific ITAAC that verify '
them. This submittal would not be included in either the SSAR or DCD.
J. Quirk provided a oiscussion of the status of the ABWR review (Enclo-sure 2.) He asked about the status of the two significant open items from the ,
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l August 17, 1993 ITAAC meeting: Tier 1 treatment of the "2 over 1" seismic category issue and the treatment of codes and standards in Tier 1. For the first item, W. Russell indicated that the staff had requested that GE reference a specific ,
EPRI report which discusses how to conduct a walkdown of a plant to determine l if there are any areas where the failure of seismic Category 2 equipment after l a design basis earthquake could affect the safe operation of seismic Cate- !
gory I equipment located below. The proposed resolution is that GE should specify as a COL action item that the applicant should describe how he would implement the inspection requirements included in the EPRI document, and ;
should develop an ITAAC to verify that all requirements were met. For the i item regarding codes and standards, the staff had asked that GE include in i Tier 1 certain civil codes such as AISC and ACI codes that are related to seismic Category I structures. The proposed resolution is that such informa-tion is not practical for Tier 1 treatment, and only key characteristics from the codes need to be included in the Tier 1 document. The codes and standards themselves will only be included in Tier 2.
Several questions were raised about the requirements for the DCD and the date it is due to the staff. The staff indicated that it would provide a letter with the proposed contents of the DCD and that the document will be required about five months before the final design approval (FDA) is issued to allow ,
sufficient time for staff review. l R. Matzie provided a discussion of the ABB-CE System 80+ review (Enclosure 3).
He highlighted the significant progress made since the last meeting, the remaining open issues, and provided ABB-CE's detailed plan for completion of the review. He also raised several concerns, including (I) concerns that questions from NRC contractors are coming late in the review process due to ,
lack of NRC control over the contractor, and (2) the date that ABB-CE needed !
to provide the DCD to the NRC staff. j W. Russell responded to the first concern by stating that some portions of the staff's review had been delayed while asking for specific information on where
._ ABB-CE perceived NRC contractors were not being controlled by the staff. He _
also stated that he intended to review every open item during the August 16, l 1993, senior management meeting (SMM) with ABB-CE to verify that the ITAAC review could start after the meeting.
l B. McIntyre provided a discussion of the status of the Westinghouse AP600 review (Enclosure 4). He discussed the status of the staff's RAls and emphasized the importance of working together with the staff. He suggested that bi-monthly SMMs, similar to those held with GE and ABB-CE, should start in the next three to feur months.
Dr. Murley noted that testing was important to the staff's review and that the tests would probably generate additional RAls. He also stated that he believed that the two most important issues for the AP600 review were:
l (1) computer code verification from the test program, and (2) implementation of the regulatory treatment of non-safety systems issues.
l I
August 17, 1993 ,
P. Marriott provided a discussion of the status of the SBWR review (Enclo- ;
sure 5). He emphasized that, although there have been some delays in the staff's review effort, GE is actively working on the project with sufficient :
resources separate from those assigned to the ABWR. He discussed a suggested
" schedule challenge" to accelerate the FDA review schedule for the design, ,
based on the similarity of several system designs with those of the ABWR. In GE's opinion, the review could be shortened. The staff made no commitments to change its approved schedule at this time.
(Original signed by T. J. Kenyon for)
Stewart L. Magruder, Project Manager l
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 l
DISTRIBUTION w/ enclosures:
Docket File PDST R/F PShea l PDR MFranovich SNinh l
DISTRIBUTION w/o enclosures:
TMurley, 12G18 DCrutchfield WRussell :
RBorchardt TBoyce MFinkelstein, 15B18 MCallahan, 17A3 DTang TKenyon !
GBagchi, 7H15 DJeng, 7H15 HBrammer, 7H15 ,
TPolich, 10A19 MCase, llH21 CPoslusny '
SMagruder RHasselberg MMalloy CMcCracken, 8DI JMoore, 15B18 TGody, 17G21 ACRS (11) MPratt, 7E4 EJordan, MNBB3701 WTravers L s ;
0FC: LA:PDST:ADAR PM: RI}Sf:dOAR (A) M ST:ADAR NAME: PShea O G SMaNder:sg TEsIik !
DATE: 08/d/d3 08/ f}/93 08/\1/93 0FFICIAL RECORD COPY:
DOCUMENT NAME: DOESUM.SLM 1
I l
l
l GE Nuclear Energy Docket No.52-001 j i
4 cc: Mr. Patrick W. Marriott, Marager Mr. Joseph Quirk Licensing & Consulting Services GE Nuclear Energy '
GE Nuclear Energy. General Electric Company l 175 Curtner Avenue 175 Curtner Avenue, Mail Code 782 i San Jose, California 95125 San Jose, California. 95125 Mr. Robert Mitchell j General Electric Company j 175 Curtner Avenue !
San Jose, California 95125 :
l Mr._L. Gifford, Program Manager ;
Regulatory Programs :
GE Nuclear Energy l 12300 Twinbrook Parkway Suite 315 i Rockville, Maryland 20852 j Director, Criteria & Standards Division Office of Radiation Programs :
U.S. Environmental Protection Agency !
401 M Street, S.W. !
Washington, D.C. 20460 ;
Mr. Sterling Franks U.S. Department of Energy i NE-42 !
Washington, D.C. 20585 i Mr. Steve Goldberg l Budget Examiner i 725 17th Street, N.W. i Room 8002 1 Washington, D.C. 20503
._ Mr. Frank A. Ross U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874 Mr. Raymond Ng 1776 Eye Strebt, N.W.
Suite 300 Washington, D.C. 20006 Marcus A. Rowden, Esq. ;
Fried, Frank, Harris, Shriver & Jacobson i 1001 Pennsylvania Avenue, N.W.
Suite 800 l Washington, D.C. 20004 i Jay M. Gutierrez, Esq.
Newman & Holtzinger, P.C.
1615 L Street, N.W. -l Suite 1000 Washington, D.C. 20036 l.
1 1
2er- . r o * .,e..- -- -<- --m.< ,or-,
-.e , - .w -e - - - -
- 'ABB-Combustion Engineering, Inc. Docket No.52-002 4
cc: Mr. C. B. Brinkman, Acting Director Nuclear Systems Licensing ABB-Combustion Engineering, Inc. l 1000 Prospect Hill Road l Windsor, Connecticut 06095-0500 !
i Mr. C. B. Brinkman, Manager. i Washington Nuclear Operations [
ABB-Combustion Engineering, Inc. i
)
12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Stan Ritterbusch Nuclear Systems Licensing ABB-Combustion Engineering, Inc.
1000 Prospect Hill Road ,
Post Office Box 500 ,
Windsor, Connecticut 06095-0500 l Mr. Sterling Franks U.S. Department of Energy NE-42 ,
Washington, D.C. 20585 l Mr. Steve Goldberg i Budget Examiner i 725 17th Street, N.W. i Washington, D.C. 20503 l Mr. Raymond Ng 1776 Eye Street, N.W. i Suite 300 i Washington, D.C. 20006 l
.._ Joseph R. Egan, Esquire _ !
Shaw, Pittman, Potts & Trowbridge i' 2300 N Street, N.W.
Washington, D.C. 20037-1128 Mr. Regis A. Matzie, Vice President !
Nuclear Systems Development l ABB-Combustion Engineering, Inc. j 1000 Prospect Hill Road l Post Office Box 500 l Windsor, Connecticut 06095-0500 j 1
1
' Docket No.52-003 Westir.ghouse Electric Corporation 0 ;
cc: Mr. Nicholas J. Liparulo Nuclear Safety and Regulatory Analysis !
Nuclear and Advanced Technology Division l Westinghouse Electric Corporation .
P.O. Box 355 }
Pittsburgh, Pennsylvania 15230 l Mr. B. A. McIntyre I Advanced Plant Safety & Licensing Westinghouse Electric Corporation .
Energy Systems Business Unit !
Box 355 t Pittsburgh, Pennsylvania 15230 l Mr. John C. Butler !
Advanced Plant Safety & Licensing l Westinghouse Electric Corporation l Energy Systems Business Unit :
Box 355 !
Pittsburgh, Pennsylvania 15230 !
Mr. M. D. Beaumont Nuclear and Advanced Technology Division '
Westinghouse Electric Corporation One Montrose Metro ,
11921 Rockville Pike l Suite 350 i Rockville, Maryland 20852 Mr. Sterling Franks U.S. Department of Energy '!
NE-42 ;
Washington, D.C. 20585 l
Mr. S. M Modro - '
EG&G Idaho Inc.
Mr. Steve Goldberg Budget Examiner i 725 17th Street, N.W. '
Room 8002 i
Washington, D.C. 20503 '
Mr. Frank A. Ross l U.S. Department of Energy, NE-42 i Office of LWR Safety and Technology !
19901 Germantown Road Germantown, Maryland 20874 i
l
. General Electric Company Docket No.52-004 0
cc: Mr. Patrick W. Marriott, Manager Licensing & Consulting Services GE Nuclear Energy 175 Curtner Avenue San Jose, California 95125 Mr. Laurence S. Gifford GE Nuclear Energy 12300 Twinbrook Parkway Suite 315 Rockville, Maryland 20852 Director, Criteria & Standards Division Office of Radiation Programs U.S. Environmental Protection Agency 401 M Street, S.W.
Washington, D.C. 20460 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C. 20585 Mr. Jeffrey C. Baechler GE Nuclear Energy 175 Curtner Avenue, MC-782 San Jose, California 95125 Mr. Frank A. Ross Program Manager, ALWR Office of LWR Safety & Technology U.S. Department of Energy NE-42 19901 Germantown Road '
Germantown, Maryland 20874 _
l l
, t I
O i LIST OF ATTENDEES DOE / VENDOR /NRC MEETING AUGUST 2, 1993 l MME ORGANIZATION -
E. C. Brolin DOE ;
W. Pasedag DOE C. Thompson DOE !
S. Frantz Newman & Holtzinger !
J. A. Beard GENE J. Quirk GENE j D. McGoff DOE -
R. P. Mcdonald ARC l P. Marriott GENE B. McIntyre Westinghouse :
i R. A. Matzie ABB-CE D. Crutchfield NRC ,
W. T. Russell NRC T. E. Murley NRC R. W. Borchardt .NRC ;
T. Boyce NRC !
M. Finkelstein NRC .;
M. Callahan NRC :
R. Ng NUMARC l l
D. Tang NRC !
T. Cook DOE l T. Meisenheimer Bechtel i T. Kenyon NRC i G. Bagchi NRC D. Jeng NRC !
H. L. Brammer NRC l T. Polich NRC -
i M. Case NRC ,
C. Poslusny NRC i S. Magruder NRC i T. Anderson Westinghouse !
R. Hasselberg NRC .
D. Stellfox McGraw-Hill !
M. Malloy NRC !
C. McCracken NRC' !
l C. Brinkman ABB-CE :
T. Rudek ABB-CE P. Lang DOE-G. Vine EPRI ,
J. Trotter EPRI ;
3 Enclosure 1 I
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., , . . , . . _ , . . . . - - , , _ , , . . . _ , _ - . ~ . , . . . - . - . , . . . .
'--------------------------v- .
I GE NUCLEAR ENERGY l
ABWR Program Overview 4
J. F. QUIRK t ABWR Project Manager 9
2 a '
3 August 2,1993 4
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SUMMARY
- DFSER issued by NRC 10/20/92
- - 754 design-related issues
- 174 ITAAC-related issues
- All design-related DFSER issues addressed by GE 4/30/93
- All design-related DFSER issues closed by NRC 7/8/93
) l 7/31/93
. Final SSAR submitted to NRC i
APR1/JFO-721/93 '
1
______.-t_.____._____.____________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _________._.m : ____ u___ __ _ _ _ _ . _ _ _ _ _ _ _ ___ _ _ _ _ _ __ _ ______.._______ _
DESIGN RELATED ISSUE RESOLUTION / CLOSURE ACTIVITY .
900 - -
m.32 800 --
dups 700 -_
N W -
Am.29 e
3 600 - -
g J -
z 500 - -
Am.28 O
P 3 ~
.2 O
f4 400 - -
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$ 300 - - A e dments
~ Am.26 200 - - Am.25
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- Am.24 100 --
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O I g ' 8 Nov.92 Dec-92 Jan-93 Feb-93 Mar-93 Apr-93 May.93 Jun.93 Jul.93 Aug-93
i .
TIER 1/ITAAC STATUS Snapshot Summary Two years of multi-party interactions on Tier 1 form, scope and content l
- Major GE submittal May 1992
- GE/NRC agreements now in place
- January-March 1993 meetings
! - Revised ABWR Tier 1 material now resubmitted
- Resolves all DFSER ITAAC -related issues
- - NRC review complete
- Final Tier 1 submittal scheduled for August 31,1993 i
ARPt/JFO-7/21/93 1
i
i .
ABWR FDA Schedule 1993 1994 Finish Jun Jul Activity Sep Oct Nov Dec Jan Feb Mar Apr May Date Jan Feb Mar Apr May Jun Jul Aug DFSER issue Resolution 7/8/93 MW ME SSAR/ Tier 1 Verification 7/31/93 M EM E-7/31/93 .
.E
- ! E SSAR (Reissued)
Tier 1 Document 8/31/93 E NRC SSAR and Tier 1 9/30/93 E Verification
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E Conforming Changes to SSAR 11/12/93 FSER (SSAR) 12/17/93 E -
EMME " - ME ACRS Review 1/29/94 EMEEEEEEEE E ~' f# EE FDA Preparation & Issuance 5/31/94 Initiate Certification Process AL 6/1/94 (including DCD)
' 7/9/93
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Major Acconiplishments Since Last -
Meeting -
8 IMPLEMENTED JOINT NRC/ABB-CE TRACKING SYSTEM e COMPLETED INTEGRATED REVIEW AND DATABASE l
e RESOLVED ABOUT 300 OPEN QUESTIONS i
e PROVIDED TWO CESSAR-DC AMENDMENTS (5400 PAGES)
DOCUMENTING THESE RESOLUTIONS
- e DEDICATED NRC TECHNICAL MANAGER ASSIGNED FOR CLOSURE l OF DESIGN CERTIFICATION e COMPLETED TIER 1 DESIGN DESCRIPTIONS AND ITAAC SUBMITTAL i A ER ED
- Nuc ear Systems '
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Overview of ARC Question Status .
e Current Status:
1217 Technically Resolved Questions 157 Open DSER Questions 293 Open Follow-On Questions (Post DSER?
1667 Total
! ~
! Nuclear Systems A It 59 7%IDED
~
System 80+ DSER .
l and Follow-On Questions , . . . . . . . . . . - . - -
l 1400 l l
1200 -
1000 -
Total Questions 800 -
400 -
, 200 i i I I i I i I i g
Sep. Oct. Nov. Dec. Jan. Feb. Mar. Apr. May Jun. Jul.
92 92 92 92 93 93 93 93 93 93 93 4
A ED ED MEDED
1 .
Remaining Open Questions by .
Technical issue issue # Title #Dpen Questions 1 Piping Design 27 2 Structural Design 21 3 Environmental / Seismic Qualification of Equipment 7 4 in-Service Testing 26 5 in-Service Inspection 2 6 Materials & Chemistry 3
- 7 Process and Post Accident Sampling 2 1 8 1&C Design 2 l
9 Electrical System Stability and Isolation 10 10 Fire Protection Adequacy 4 l
11 Fuel Handling Criticality Analysis 6 I
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i Nuclear Systems A It Et ,
7%BDED 1
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Remaining Open Questions by .
Technical Issue (Cont.)
Issue # Title #Qpen Questions 12 Sabotage Vulnerability Analysis 11 13 HVAC Filters 2 ,
14 Cooling Water System Operability 3 15 Diesel Generator and Radwaste 15 .
16 Turbine Plant ASTM Standard 1 17 Radiation Protection 18 4
18 Startup Testing 3
! 19 Containment Bypass 3 20 Safety Analysis Assumptions 4 i
- 21 ECCS Vessel Bypass 1 22 Radiological Source Term 2
! Nuclear Systems A It II i 7%BDED i
Remaining Open Questions by .
- Technical Issue (Cont.)
Issue # Title # Open Questions l
23 Technical Specifications 4 24 Emergency Procedure Guides 4 25 Human Factors Engineering 159 26 PRA Assumptions 28 27 Reliability Assurance Program 1 28 Seismic Magins Analysis 3 i 29 Shutdown Risk 41
- 30 Severe Accident Audit 4 i
31 Hydrogen Analysis Audit 17 32 S.Acc. Design Alternatives 1 l 33 Scope of Design and EPRI URD 3
- Compliance 34 DD/ITAAC Review 1 l
! Nuclear Systems A It BR l 7%EDID
I ABB-CE PLANNING SCHEDULE FOR COMPLETION OF NRC REVIEW OF SYSTEM 80+ ,
1993 1994
, l_D Action Perty Activity Junl Jul j AuglSeplOct lNovlDec Jen lFebl Mar l AprlMaylJunl Jul l AuglSepl Oct lNovlDec 1 ABB CE&NRC Complete Technical Resolution of Open items pgyg g,g]
1.1. ABB CE&NRC Close Open item 1: Piping Design gpfgr@ sj 1.2 ABB CE&NRC Close Open item 2:Strucutural Design w/ygg wggdgl 11 EEDCE&NRY Close Open item 3: Environmental / Seismic Qualification of Equipment em gem 1.4 ABB CE&NRC Close Open item 4;In-Service Testing upssy - J 1.5 ABB CE&NRC Close Open item S:In-Servico lnspection gryn e il 1.6 ABB CE8.bRC Close Open item 6.Meterials and Chemistry Aspfg g 51 1.7 ABB CE&NRC Close Open item 7; Process and Post-Accident Sempimg System , qq cgyt 1.9 ABB CE&NRC Close Open item 9:l&C Design g ejg3- .w l 1.10 ABB CE&NRC Close Open item 10.Elecincel System Stability and Isolation e,q,;M l
_ . . _ - ..-_ _ m,~
1.11 ADB CE&NRC Close Open item 11: Fire Protection Adequecy ggone tj 1.15 ~ ABB CEINRC Close Open item 12 fuel Handling Certify Analysis 4?ggpA mj 1.13 ABB CE&NRC Close Open item 13:Sebotage Vutnerubility Analysis g# egg.j wf f 1.14 ABB CE&NRC Close Open item 14:HVAC Filtere we gj 1.15 ABB CE&NRC Close Open item 15. Cooling Water System Operability M ;ts fj 1.16 ABB CE&NRC Close Open item 16; Diesel Generator end Redweste (:eejp g ynge.:wgj l.5'7 EbbCE5URC Close Open item 17: Turbine Plant ASTM standard g gy g,gl 1 ili3 ' AB5 CE&NRC Close Open item 18:Rediation Protection gygpf Ed]
... .. . ~ . _ . - -
1.19- ABB CE&NRC Close Open item 19:Startup Testing .am 7]
1.20 ABB CE&NRC Close bpoh item 20; Containment Bypass egym )j
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l'.25 dE U U5b d Close Open item 21;Selety Analysis Assumptions typm;p4 $1
, 1.23 ABB CE&NRC Close Open item 23:ECCS Vessel Bypass wm .- ;j t l.25 ABBCE&NRC Close Open item Sltediological Source Term en n , ' ml 1.26 ABB CE&NRC Close Open item 26: Technical Specifications ppgg4 gg
, 1.38 ABB CE&NRC Close Open item 28. Emergency Procedure Guides egg, m ;j
_=: . . . . . . _ . s 1.29 ABB CE&NRC . Close Open item 29: Human Factors Engineering wg3y ggg 1.30 ABB CE&NRC Close OpenItem 30;PRA As'sumptions , gy,g s 9. l Page 1 t
_.c___.-__. _____.___._m__m.__. _________.m. _ ___._ ___.___.,--__o em ,-. - _ ..m_- . . , . , , . . . - . . , --. .,,a . . . ,. .-.m , . . w -. , . ---i._,m .-. . .-, ,. . ~,..m..--
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ABB-CE PLANNING SCHEDULE FOR COMPLETION OF NRC HEVIEW OF SYSTEM 80+ ,
1993 1994 =
10 Actmn Party Activity . Jun l Jul l AuglSeplOct lNovlDec Jen lFebl Mar l Apr lMeyl Jun l Jul l AuglSepl Oct lNovj Dec 1.31 ABB CE&NRC Close Open item 31:Reliebihty Assurance Program ;7,gg 9 3l 1.32 ABB CE&NRC Close Open item 32: Seismic Margins Analysis wg,g, p .gye 3
- 1.33 ABB CkIUtic ~ Close Open item 33
- Shutdown Risk ggu,w puj
{ ,
l.30 A'BB dEENikb Close Open item 34; Severe Accident Audit re#+r,,p;;. Argypj 1.35 ABdUk&'NRC Close Open item 35: Hydrogen Anetysis Audit f g ;pp , g. ]
l 1.35 ABBCk& Rb' Close Open item 37:S. Acc. Design Alternatives pg;3 - tl 1.38 ABB CEkNRb CloN Open item 38: Scope of Design & URD Compliance ggara, 3yl
~
US^ BB CE&NRC Close Open item 39:DD/IT A AC Review 'g,sF'd ?t4Md 2 ABBb5~ Prepere CESS AR-DC Amendments incorporating issue Resolutions aggppg , egr l 3 000 CE Complete Tier 1 design descriptions & ITA AC pm:g gyggs gsppMpg]
t 3.1 ABB CE Review allITA AC for consistency with NRC guidance 3ggpq c,. gl 32 NRC NRC review ITA AC gg 3.3 ABB CE Respond to ITA AC comments
+
3.4 ABB CE&NRC Resolve ITA AC Comments ;S 3.5 ABBCE *repare certified ITA AC @ pag {
3.6 - ABB CE Prepare CESSAR-DC Amendment to reflect ITAAC resolutions [gggprog l
. 4 ABB CE Prepare Amendments to CESS AR DC g 4
5- NRC P.M. Completes FSER and issues to Comrnssion [pppg;gg t
l 0, ABB CE&NRC Support ACRS Review w;ggq ggggy - n w y ,: p;cf g g p egg gy g j 7 NRC Commission issues Decision 1,k Nse ee ;l l -
8 NRC Prepere guidance on DCD g j 9 ABB CE Prepare initial drott of DCD [y gpg,;y,p y g g j 10 ABB CE Prepara linel draf t of DCD . [$segepap w m: .e :t ii NRC Perform consistency teview of DCD [ .. _ ,, 9 l i 12 NRC NRC issues FDA l cpv r1 IJ ABB CE Recommended Statement of Consideration for ANPR pgg w e ge]
. . . _ . . . . . _ . . . ~ . _
, 14 NRC' Issue Advanced Notice on Proposed RulemakingMeneric) pp- pgggpp+s g WNW Page 2 m _. . _ .
.- .. = . - . -_ . . . _ . - =- .. . .- .. . . . . .
3 i
ABB-CE PLANNING SCHEDULE FOR COMPLETION OF NRC REVIEW OF SYSTEM 80+ ,
1993 1994 10 ' Action Party ActMty Jun l Jul ; AuglSep l Oct lNov]Dec Jen lFebl Mar l Ape lMaylJunl Jul l AuglSepl Oct lNovlDec 15 NRC Conduct Workshop and Finaliae Certification Rule (Generic) p. ugggw ggyg.gy:q ,gygy,gj f
16 NRC Prepare Rule for System 80 + p vg&s aer ;wegm 3 17 NRC Rulemaking Proceeding F- ;< J 18 dCE&NRC Management Meetings (4 wk intervals) g gggyg .gg;<ge,pqfyg g,ggg,7;yyggjygg , ogg g;gg,p.g:j;g.y.yy g yg .;-
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Potential Thrhats to System 80+ .
Schedule w Lack of policy guidance e Design control document e Extent of roadmaps e Tier 1 design descriptions and ITAAC e Competition for NRC Resources e Technical issues e Severe accident analyses (H2 control and core concrete interaction) e Human Factors Engineering e New unscreened questions at late date A ER ER N uclear Systems 7%B555
- 0. r imteire
Recommended Resolution
~
Management Process l
o Same concerted review and resolution process by NRC staff as was applied recently to ABWR o Manage consultants toward closure of open items i e Raise potential subsequent and/or follow-on technical l questions with their bases to senior management level before issue j
l e Joint NRC/ DOE /ABB-CE Agreement to Schedule for l Design Certification (including groundrules and '
! assumptions)
I e
i - A ER ER j \luclear Systems pggyHp
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l
1 Requested Closure Meetings .
L l
4 Reactor Systems Branch I Scheduled, e8/5 Containment Bypass) e 8/9 Safety Assessment Branch I Scheduled, PRA)
! e 8/9-8/12 Plant Systems Branch (Scheduled) s 8/10-8/12 Technical Specification Branch (Unscheduled)
- 8/10-8/11 Human Factors Engineering I Unscheduled) e 8/10-8/11 Civil and Geosciences Branch I Scheduled, Containment Design) e 8/12 Containment Systems Branch I Scheduled,
! Hydrogen Analysis Review?
! e 8/12 Reactor Systems Branch I: Unscheduled,
- Safety Anaysis, EPGs?
l e 8/13 Containment Systems Branch (Unscheduled, l Hydrogen and Core-Concrete Interaction) e 8/13 Mechanical Engineering I Unscheduled, Piping?
! A It It Nuclear Systems pggygy L . . . . . . _
1 .
AP600 DESIGN CERTIFICATION PROGRAM 8 DOEllNDUSTRY/NRC DESIGN CERTIFICATION PROGRAM STATUS AUGUST 2,1993 BRIAN A. MclNTYRE, MANAGER ADVANCED PLANT SAFETY AND LICENSING WESTINGHOUSE ELECTRIC CORPORATION E
n C
onasm.wem ,
- }
I .
APPROACH
- Work with the NRC staff to improve the process of AP600 Design Certification through a mutally agreed-upon schedule.
in particular:
o incorporate a status tracking system to which we commit ,
ourselves.
o incorporation of identified areas of schedular improvement into the schedule.
o Establishing regular AP600 project review meetings in which we manage the process of design certification.
4 0219BAM.WPF/2 t
_ . - - . - - _ . - , _ _ . . . _ _ _ . . . _ . - _ . _ _ _ . _ _ ._m-. - . - . - _ . .- - - -_ _ . -_ ___ _ _ _ _ -_ -. ... - _ - _ _ _ _ __ _ _ _ - -
ACTIONS SINCE LAST MEETING 3%
- URD VOLUME lil FSER COMPLETED
-INTENSIVE APPROACH CONTINUED WITH NRC/ACRS
- MMI DESIGN, ITAAC AND RAI RESPONSES
-INFORMATION MANAGEMENT SYSTEM
- TESTING OVERVIEW
- TESTING AND ANALYSIS STATUS (ACRS)
- CONTROL ROOM HABITIBILITY AND RAI RESPONSES
- 270 AP600 RAls FROM STAFF
- 41 AP600 RAls TO STAFF
-IDENTIFICATION OF TECHNICAL ISSUES (SECY-93-087)
- DETAILED INTEGRATED SCHEDULE DRAFTED AND DELIVERED 0219B AM.WPF/3 ,
e REQUESTS FOR ADDITIONAL INFORMATION $
- 1116 RECEIVED
- 815 RESPONSES
-INPUT NOT RECEIVED IN SEVERAL AREAS
- FUEL
- PASSIVE SAFETY SYSTEMS (SEPTEMBER) i 4 0213B AM .WPFl5 ,
i '
s e
CRITICAL ISSUES AND STATUS 8
- REMAINING RAl's (JUNE 30,1993)
- PRA RECEIVED
- RSB - SEPTEMBER 1993
- FEEDBACK ON WESTINGHOUSE RESPONSE ACCEPTABILITY
- PRESENTLY BEING OBTAINED VIA MEETINGS
- TESTING ,
- AGREEMENT IN PRINCIPLE LETTER RECEIVED
- NRC TESTING FOCAL POINT IDENTIFIED
- WEEKLY PHONE CALLS
- AP600 RTNSS RESOLUTION IMPLEMENTATION TO NRC IN SEPTEMBER 1993
- INDUSTRY REVIEW GROUP FORMED 0219BAM.WFFIG 9
1 .
s e
OTHERISSUES 8
- TECHNICAL ISSUE RESOLUTION
- COMMISSION SRM Wh'TTEN (SECY-93-087)
- WILL ALLOW AP600 TO GO FORTH CONFIDENTLY
- SEISMIC
- DIGITAL BACKUP - NONSAFETY
- NRC STAFF RESOURCES
- RAI DEVELOPMENT
- ISSUE RESOLUTION
- INTERACTION AMONG PROJECTS 1
0219BAM.WPF/7
,- . _ . . . ,__ . _ - . _ . . , _ _ . _ , . . ~ . . _ _ _ , _ _ _.
1 .
STATUS OF ACTIONS TO IMPROVE SCHEDULE 8
- FEEDBACK ON ACCEPTABILITY OF RAI RESPONSES
- SECOND ROUND RAls AND TOPICAL MEETINGS
- AP600 SSAR AND PRA IN Wordperfect FORMAT
- TEXT EXAMPLE PROVIDED TO NRC
- DETAILED SCHEDULE WITH STATUS TRACKING SYSTEM
- EXAMINED WHAT CAN BE ACCOMPLISHED SIMULTANEOUSLY
- REDUCED WESTINGHOUSE TIME TO RESPOND TO DSER
- USED LESSONS LEARNED FROM EVOLUTIONARY PLANT PROGRAMS
- REGULAR PROJECT REVIEW MEETINGS INCLUDED
- MUTUAL COMMITMENT TO MEET SCHEDULE 0219BAM.WPF/8
S .
INTEGRATED SCHEDULE Ig
- EXPANDS ON SECY-93-097 ACTIVITIES TO INCLUDE:
- ADDITIONAL LEVEL OF-DETAll
- TESTING PROGRAM
- KEY POLICY / TECHNICAL ISSUES
- DOE COMMENTS INCORPORATED
- DELIVERED TO NRC
- KEY MILESTONES
- SER - 10/95
- FDA - 11/95
- NEXT STEP IS INDUSTRY AGREEMENT 0219BAM WPF/4 9
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KEY SCHEDULE ASSUMPTIONS 8
- URD VOLUME Ill FSER ISSUED IN NOVEMBER,1993
- LAST RAI RECEIVED IN SEPTEMBER,1993
- DSER ISSUED PRIOR TO FINAL TESTING REPORTS
- HIGH LEVEL OF ACRS INVOLVEMENT MAINTAINED
- WESTINGHOUSE AND NRC COMPUTER MODELS OF TESTING FACILITIES READY TO ACCEPT DATA FROM QUICK LOOK REPORTS
- FOURTH STAGE ADS TESTING NOT REQUIRED FOR DESIGN CERTIFICATION
- FSER CONTAINS NO OPEN ITEMS 0219BAM WPFt10 ,
l
L CONCLUSIONS 8
- MORE PROGRESS HAS BEEN MADE MOVING TOWARD PROCESS THAT WILL DETERMINE:
- CRITICAL ACTIONS .
- RESPONSIBILITIES
- DATES FOR RESOLUTION
- WITH AGREED - UPON SCHEDULE, PERFORMANCE WILL ULTIMATELY DETERMINE ACHIEVEMENT 0219B AM.WPFI9
_____a
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_.. _ ___-u___ _ _ . _ _ - - _ _
O GENuclear Energy SBWR Program Overview P.W. Marriott SBWR Project Manager August 2,1993 n
8
.k U1
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i .
SBWR Program Overview
- Certification
- NRC declared SSAR complete
- Heavy GEand NRC emphasis on ABWR
- Round Zero RAI responses submitted on schedule
- Design, Analysis & Testing
- Integrated systems tests (PANDA) on schedule
- PCCS/IC tests (PANTHERS) delayed 2 months
- PCCS/IC test (GIRAFFE) report submitted to NRC Cost optimization program well underway Regulatory treatment of non-safety systems program under development
- Transfer of URD self-assessment program initiated i
PWM930728
SBWR Program Overview (cont.)
- Program Planning
- Integrated schedule planning with DOE and NRC underway
- FDA stretchout discussions with DOE and EPRI underway
- RelatedPrograms
- Team has responded weH to ARC FOAKE decision - strong consensus to move ahead
- Commercial engineering program planning underway Discussing SBWR adaptations with overseas utilities 1
PWM930728
FDA Challenge Schedule
- Evaluation of NRC's proposed schedule led to establishment of a 1
" Challenge" schedule for FDA issuance
- Reasonable to advance date by 6-1/2 months from 5/30/96 to 11/15/95 based on following considerations:
- Utilization of A8WR experience in preparing the SSAR itself
- No RAls on identical ABWR/S8WR systems and issues Fewer RAls on similar systems and issues Recent familiarity of NRC personnel for review of Advanced BWRs Resolution of many ALWR issues through utility requirements documentreview Resolution of key passive plant issues, like RTNSS, through review of the AP-600 1
~
PWM930728
' ~~
FDA Challenge Schedule (cont.)
NRC GE Original Proposed Delta Schedule Proposed Duration Duration Delta Month Activity Descriotion Date Date by NRG - b1GE Duration Cumulative FMIssues RAI 10f2583 1025B3 0.3 0.3 0.0 0.0 GEResponds to RAI 012 184 01/31N4 3.0 3.0 0.0 0.0 NRC Staffissues DSER to PM 062084 0520B4 5.0 4.0 1.0 1.0 PM!ssues DSER to GE 09/3084 08/1584 3.0 2.5 0.5 1.5 GEResponds to DSER 03/3085 12/1584 6.0 4.0 2.0 3.5 NRC StaliIssues FSER to PM 07/2885 03/1585 4.0 3.0 1.0 4.5 PMissues FSER to GE 1020B5 052185 3.0 2.5 0.5 5.0 FinalDesign Approval 052086 11/1585 7.0 5.5 1.5 6.5 FDA Schedule can be shortened by 6-12 Months GE willing to work with_W to optimize utilization of NRC resources t
PWM930728
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