View source for NUREG-1338, Responds to Ltr to Wd Travers, Re Small,Modular, pebble-bed Reactor Design.Some Background Info & Guidance on Licensing gas-cooled Reactor Designs Can Be Found in NRC Staff repts;NUREG-1226,NUREG-1338 & NUREG-1512

{{Adams
| number = ML20196G416
| issue date = 11/22/1998
| title = Responds to Ltr to Wd Travers, Re Small,Modular, pebble-bed Reactor Design.Some Background Info & Guidance on Licensing gas-cooled Reactor Designs Can Be Found in NRC Staff repts;NUREG-1226,NUREG-1338 & NUREG-1512
| author name = Collins S
| author affiliation = NRC (Affiliation Not Assigned)
| addressee name = Kadak A
| addressee affiliation = MASSACHUSETTS INSTITUTE OF TECHNOLOGY, CAMBRIDGE,
| docket = 
| license number = 
| contact person = 
| case reference number = RTR-NUREG-1226, RTR-NUREG-1338, RTR-NUREG-1512
| document report number = NUDOCS 9812080003
| title reference date = 11-06-1998
| package number = ML20196G421
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| page count = 3
}}

=Text=
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November 22, 1998 f
A Dr. Andrew Kadak                                          .
Department of Nuclear Engineering,24-207 Massachusetts Institute of Technology 77 Massachusetts Avenue Cambridge, Massachusetts 02139-4307

==Dear Dr. Kadak:==

I am responding to your letter to Dr. William D. Travers, dated November 6,1998, regarding a small, modular, pebble-bed reactor design. You requested information or regulatory guidance on licensing such a design. As noted in your letter, the current Nuclear Regulatory Commission              l (NRC) regulations provide a process in 10 CFR Part 52 for licensing next-generation (advanced) reactor designs. Specifically, Section 52.47(b)(2) provides a process for licensing              i an advanced design or unique design features by testing.                                                    i l
Some background information and guidance on licensing gas-cooled reactor designs can be found in NRC staff reports: NUREG-1226," Development and Utilization of the NRC Policy Statement on the Regulation of Advanced Nuclear Power Plants"(June 1988), and NUREG-1338," Draft Preapplication Safety Evaluation Report for the Modular High-Temperature Gas-Cooled Reactor"(March 1989). Also, Chapter 21 of NUREG-1512," Final Safety Evaluation Report Related to Certification of the AP600 Standard Design"(September 1998), contains the NRC staffs evaluation of the testing programs performed by Westinghouse for the AP600 standard design. The enclosed notice explains how these reports can be obtained.
Mr. Jerry Wilson is the cognizant member of my staff who can answer questions on the licensing process under 10 CFR Part 52. Please contact him by telephone at 301-415-3145 or by e-mail at jnw@nrc. gov if you have any further questions on this matter.
Sincerely.
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