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*Does not include 800 high school students (400 User days) on Environmental Research field classes.

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FROM WESTINGHOUSE HANFORD NO.4

PAGE 1 (WED 03.12.'86 12:56

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FROM WESTINGHOUSE HANFORD NO.4

PAGE 2

(WED >03.12. '86 13:08 pastinghouse lantord

19. 10 NA 1000, In 80

March 11, 1986

Ms. Marilyn Lloyd
Chairman, Subcommittee on
Energy Research and Production
Coamittee on Science & Technology
V.S. House of Representatives
Dear Ms. Lloyd:

Your March 3, 1986 letter to me asked a number of questions
related to the Fiscal Year 1987 Department of Energy Nuclear
Fission R&D budget request. I w pleased to submit my answers
to those questions, presented in the attachments to this letter.
Please contact me if you need any further information.
Very truly yours,

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: FROM WESTINGHOUSE HANFORD NO. 4

PAGE 3 (WED)03. 12. '86 13:03

QUESTIONS FOR MR. NOLAN

Q.1 In the first page of your testimony you describe the remarkable achieverents

of the fast Flox Test Facility over the course of its operating 1ste to date. You also note that the results derived from these successfol tests are available for development la licensing of advanced design Le plants, and I quote your vorde.

- Have you any Indication that the NRC would accept these datı as suitable

. for licensing advanced desigo LR plants?

We have every reason to believe that NRC would fully accept the Fast Flux
Test Facility (FFTF) core component assembly performance data for licensing
purposes since they were obtained on full-sized components in a completely
representative Liquid Metal Reactor (LMR) environment. Historically, NRC
has always preferred this type of data over that from smaller specimens
although they certainly use the latter information as well. A classic
examp

fuel assembly and control assembly data in the
NRC licensing process is that involving the Clinch River Breeder Reactor
(CRBR). After completing all NRC, ACRS and public hearings on the
construction permit for CRBR, NRC stated that all requirements for a con-
struction partit had been satisfied in their Memorandum of Findings, LBP-
84-4, CRBR Plant, Atonic Safety and licens ing.Board, January 20, 1984. The
documentation supplied by CRBR to NRC included specific reference to a number
of FFTF core components, linking the performance of these assemblies to the
CRBR operating permit. Similar activities are now getting started between
NRC and the innovative reactor designers, General Electric and Rockwell
International, for their PRISM and SAFR concepts, respectively. The FFTF
core component data will become an inherent part of those licensing
activities as they progress to the stage of considering the reactor core
itselt.

A final point worth noting is that all of the FFTF fuel and absorber assembly
irradiations were and are conducted under the discipline of the FFTF Final
Safety Analysis Report (FSAR) which was thoroughly reviewed by NRC. Although
FFTF was not formally licensed, it was fully subjected to the NRC technical
review process. These components that have performed so well and which have
provided such a high quality storehouse of information, along with the
advanced tests either under frradiation now or to be inserted in the FFTF
by the end of FY-86 have been and will continue to be an integral part of
any licensing activities for LIRS.

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