ML20245D354
| ML20245D354 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 04/21/1989 |
| From: | Michaels T Office of Nuclear Reactor Regulation |
| To: | Danielle Sullivan NEW YORK, STATE UNIV. OF, BUFFALO, NY |
| References | |
| NUDOCS 8904280260 | |
| Download: ML20245D354 (3) | |
Text
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i6 April 21, 1989 Docket No. 50-57 Mr. Daniel W. Sullivan, Jr., Associate Director Buffalo Materials Research Center State University of New York Rotary Road Buffalo, New York 14214
Dear Mr. Sullivan:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGE REQUEST In order for us to complete our review of the Technical Specification change request of December 20, 1988, we need additional information as indicated in the enclosure. Please feel free to call me on 301-492-1102 if you have any questions regarding this request.
Sincerely,
/s/
Theodore S. Michaels, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated DISTRIBUTION:
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WASHINGTON, D. C. 20555 April 21, 1989 Docket No. 50-57 Mr. Daniel W. Sullivan, Jr., Associate Director Buffalo Materials Research Center State University of New York Rotary Road Buffalo New York 14214
Dear Mr. Sullivan:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL-SPECIFICATION CHANGE REQUEST In order for us to complete our review of the Technical Specification L
change request of December 20, 1988, we need additional infomation as indicated in the enclosure. Please feel f ree to call ine on 301-492-1102 if l
l you have any questions regarding this request.
Sincerely, h D. )
l Theodore S. Michaels, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated l-t
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' ENCLOSURE i-REQUEST FOR ADDITIONAL INFORMATION BUFFALO MATERIAL RESEARCH CENTER RADIATION PROTECTION BRANCH 450.1 Sumarize the assumptions, parameters and calculational methods you-used to determine your design basis accident doses' for the proposed reactor building leak rate increase.
450.2 Provide a reference or_ a general description of any digital computer program or analog simulation you used in the analysis.
450.3 Provide the release rate of radioactive materials as a function of time to the environment via various leakage paths from the reactor building for your design basis accident.
-450.4 Provide a discussion of the extent of system interdependency (reactor building isolation system and other engineered safety features) contributing directly or indirectly to controlling or limiting leakages from the reactor building or other sources such as air purification and cleanup systems for your design basis accident.
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