NRC-88-3365, Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 1989

Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 1989

ML20206F209
Person / Time
Site:	05000601
Issue date:	11/01/1988
From:	Johnson W WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Murley T Office of Nuclear Reactor Regulation
References
NS-NRC-88-3365, NUDOCS 8811210025
Download: ML20206F209 (2)

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November 1, 1988 NS NRC 88 3365 Dr. Thomas E. Hurley, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Hall Station PI-137 Washington, DC 20555

SUBJECT:

Design Approval / Certification Programs for Advanced Westinghouse PWRs

Dear Dr. Hurley:

In anticipation of increasing demands for new electrical generating capacity in the next decade and beyond, Westinghouse is developing the design of Standard Nuclear Power Plants suitable for both domestic and foreign applications. The i development programs for these plants includes a U.S. NRC safety review leading l

to design approval and certification. This is considered essential to ensure the acceptability of the nuclear option in the U.S. and the competitiveness of the U.S. standard design in the international marketplace.

Westinghouse is currently proceeding with design approval and certification programs for two new nuclear plant designs: SP-90, an advanced 1300 MWe pressurized water reactor being developed since 1982 in conjunction with Hitsubishi Heavy Industries under the sponsorship of five major Japanese utilities, and AP-600, an advanced 600 MWe pressurized water reactor design, incorporating passive safety features in a walk-away safe design, under the sponsorship of the DOE and with the support of EPRI.

The AP 600 design has progressed tn the point where the principal design features have been selected and the total plant configured in an integrated, complete plant design. Since the passive plant concepts provide a new approach to the design of safety systems, a safety review interaction with NRC staff has been requested at a relatively early stage of design. This interaction should focus on the fundamental safety characteristics of the design and provide the framework to make appropriate design and/or regulatory changes during the ongoing development program. The scope of the requested NRC safety review of the AP 600 plant design was provided in letter NS-NRC-87 3281, on November 30, 1987. Following the early NRC review, Westinghouse intends to pursue design certification. It is requested that this safety review be initiated in March _

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Dr. Thomas E. Murley -

2- November 1,1988  !

NS-NRC 88 3365 i'

1989 so that an early reading of NRC staff views is secured prior to the commitment of resources into the ongoing development effort.  ;

The SP 90 plant is also currently being evaluated by NRC staff for Preliminary Design Approval. Completion of the NRC safety review and receipt of the SER is '

anticipated during the first qurter of 1989. Following completion of the PDA, and pending a final design project, Westinghouse plans to complete and submit an FDA application as the next step towards design certification. -

On November 12, 1987, I and members of my staff met with you to discuss the I Westinghouse standard plant programs. At that meeting we agreed that seriedic l meetings were approariate and I believe that this is a good time to sc1edule -

another meeting witi you and your staff to continue discussion of the l Westinghouse standard plant programs. I will plan to contact you '.o n.nedule a meeting.

i Sincerely, j l ,

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l W.Y .

J. Jo nson, ' '.LuuauaA' Manager IN j J

Nuclear Safety Department  ;

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