ML20236P701
| ML20236P701 | |
| Person / Time | |
|---|---|
| Issue date: | 10/23/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | Hauber R NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA) |
| Shared Package | |
| ML20236P698 | List: |
| References | |
| NUDOCS 8711180114 | |
| Download: ML20236P701 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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October 23, 1987 o...+
MEMORANDUM FOR: Ronald D. Hauber Assistant Director-International Programs Office of. Governmental &
Public Affairs-FROM:
Lester S. Rubenstein, Director Standardization and Non Power a
Reactor Project Directorate Division of. Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation
SUBJECT:
STAFF VISIT TO JAPAN Lester Rubenstein and Dino Scaletti of NRR plan'to' visit Japan in Decembe' r in order to meet with the entities directly. involved in the Japanese Advance Boiling Water Reactor (ABWR) design and licensing. process. By these' meetings, j
the NRC staff hopes to gain a better understanding of the General Electric-j Company's ABWR design and discuss mutual licensing and-review policies and problems. This should facilitate the NRC review and design certification process as it relates to the ABWR and other future designs.
It is requested that meetings be scheduled beginning the week of December 7,
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1987: one day with.the Ministry of Trade and Industry (MITI), one half day I
each with Toshiba and Hitachi, one day with Tokyo Electric Power Company, at least one half of this day to be spent touring the future ABWR site and I
viewing the construction process of a plant presently under construction, j
A list of general discussion topics is attached.
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Leste
. Rubenstein Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III. IV, V and Special. Projects Office of Nuclear Reactor Regulation cc:
D. Crutchfield F. Miraglia j
CONTACT:
D.-Scaletti PDSNP Ext. 28282 i
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Agenda for Staff Visit to Japan
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General topic for discussion:
MITI The staff would like to discuss the regulatory philosophy of MITI
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as it relates to future designs'such as the' Advanced Boiling Water Reactor.
l Does MITI have a policy similar to that of NRC's.that wouldi encourage nuclear utilities and designers to develop standardize 1
1 designs? If.not, what are MITI's-Views on Standardization?-
Will the ABWR design be4 approved for use-at other than the i
Kashiwazaki-Kariwa site?
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The staff is interested in.MITI's perspective as to the design differences between the: version'of the ABWR undergoing a design approval review'in the USA and the version planned for construction j
by TEPC0 in Japan.
What is the expected schedule for the TEPCO application;to construct and operate and the subsequent MITI. review schedule?' A discussion of the type of review required for construction and operation..
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Is the MITI approval process a one step process,'i.e; one step i
licensing? If so what analyses, test and inspections:are necessary for determining operational readiness?c What NRC/MITI interactions if any should be expected during the course of the NRC and MITI reviews of the respective designs?
l What are the differences between the NRC's-(10 CFR'50. Appendix B) l and the Japanese Electric Association's -(JEAG 4101-1985) Quality Assurance (QA) Criteria? How is design, construction and operation experience factored into QA requirements and programs? How is GE addressing JEAG 4101-1985 for their portion of the'ABWR design. What design audit QA requirements have been used by TEPC0/MITI during the GE/Hitachi/Toshiba design proce.ss?
l; How are the problems of design backfits handled on plants, in.the i
design process, under construction and in operation?.Who detennine
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backfit requirements?
j What are the Japanese requirements related to fire protection?
i Toshiba 1
and Define the portions of the ABWR design for.which you are J
Hitachi responsible. How do those portions differ between the version undergoing design certification review in the USA and the version to be constructed by TEPCO?
How does your design QA program meet the NRC requirements identified
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in 10 CFR 50 Appendix B? How is design construction and operational experience factored into the design QA program?
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L How are nuclear power plant designers:in Japan such-as Toshiba, i
Hitachi and General Electric dealing with the issue of severe reactor accidents, i.e. accidents greater than design bases?; What are the.
postulated reactor accidents that control the design of a nuclear power plant?
It is our understanding that the Japanese version of.the ABWR has convergence of electric safety trains.. If so how does this effect safe shutdown off the reactor in the case of fires?
How and where do the electrical trains coverage? ' What is the industries' philosophy related to fire' protection?.
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What is the design rational for the reduced containment l volume in the ABWR as compared to the MARK IIf and the MARK III containment designs?
What is the stage of design completion at this point? -To what.
degree are changes made in'the design-throughout the construction process - Has a scale model of the ABWR been constructed!
Are there portion of the~ design that are considered company
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proprietary information for Toshiba..Hitachi or GE?
Tokyo Electric Power Company What is the ABWR Construction and Operation Schedule?
What are the limitation on a licensed utilitiy's to make design.
changes once a license to operate has been granted?
i Who will be the major constructor of the ABWR plant? Turn key?
Visit the site of the future ABWR, Kashiwazaki-Kariwa.. What is i
the number of units to be' constructed? Visit a plant under -
construction.
What are TEPC0's plans related to a probabilistic risk assessment for the ABWR?
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