NUREG-0982, Responds to Noted Interest in Obtaining Documentation Re Licensing & Safety Criteria for Test & Research Reactors (non-power Reactors).Forwards NUREG 0982 & NRC Rules & Regulations.W/O Encl
| ML20046C311 | |
| Person / Time | |
|---|---|
| Issue date: | 05/14/1993 |
| From: | Mendonca M Office of Nuclear Reactor Regulation |
| To: | Nikolsky R RUSSIA |
| References | |
| RTR-NUREG-0982, RTR-NUREG-982, RTR-NUREG-BR-0073, RTR-NUREG-BR-73, RTR-NUREG-CR-5756 NUDOCS 9308100123 | |
| Download: ML20046C311 (3) | |
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Rostislav V. Nikolsky, Head Department for the Supervision of Research Reactor Nuclear and Radiation Safety l
(RF Gosatomnadzor)
The Federal Supervision of j
Nuclear and Radiation Safety 1
Taganskaya ul., 34 109147, Moscow Russia l
Dear Dr. Nikolsky:
During your trip to our offices, you mentioned your interest in obtaining documentation related to licensing and safety criteria for test and research t
reactors (non-power reactors).
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One topic of particular interest was the 2 megawatts (MW) power level
' i criteria. Above this power level,.we perform our inspection program annually and below this value, every 2 years.
In searching our literature, I have not '
come up with a definitive document that outlines our bases for this criteria.
However, from this literature search and discussions with other experienced individuals in the non-power reactor field, I have found that the 2 MW value was apparently based on the potential for decay heat to cause fuel damage in the event of a loss of Coolant Accident.
I I would also like to mention that our inspection schedules are flexible. - For-example, more frequent inspections may be judged to be' appropriate for facilities with specific problems where the ret causes are not identified and corrected, for facilities with greater potential: for radiation exposures
.i (e.g., non-routine experiments), or for facilities with greater potential for i
fuel damage (e.g., a non-pulsing research reactor with an excess reactivity value much greater than the delayed neutron ' fraction). Conversely for reactors with low potential. safety significance or good performance, we can j
inspect less frequently.
In summary, although we are consideringLthe use of -
probabilistic techniques.for determining inspection frequency (such as the study we provided you on non-power reactor probabilistic risk assessment, NUREG/CR-5756, SAIC-90/1402), the 2 MW value in conjunction with judgment has provided a reasonable NRC inspection program over an extended period of time.
i Another topic of' interest was the _use of the 10 MW power level.to differentiate test reactors from research reactors. As we had discussed when you were here, this value has been used for a considerable time period. Since-our' discussion I learned that the value was established by the Joint' Committee fg.[.<j(,f,J.J/C).
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Rostislav V. Nikolsky May 14, 1993 on Atomic Energy of the U.S. Congress.
I could not find clear-cut documentation on the bases of the value at this time.
However, further information on the differences for regulation of test versus research reactors is best presented in the Project Manager Handbook (NUREG/BR-0073) Chapter 4, that we provided you on your trip.
You also inquired about documentation related to the use of containments for non-power reactors. Again as we discussed, the use of containments is based on the need to maintain acceptable radiological dose consequences for accident conditions. An example of the documentation for the use of containment is our Sa'ety Evaluation Report (Enclosure 1) on the license renewal for the State University of New York at Buffalo.
We touched on the possibility of getting you a recent copy of NRC regulations, which I have provided as Enclosure 2.
This is the latest version that I have available to me at this time.
On behalf of Dr. Weiss, Messrs. Adams and Michaels, as well as myself, I want to express our pleasure in having the opportunity to talk to you on topics of non-power reactor safety.
If you have any further questions, requests, or information that you wish to share with us, please do not hesitate to contact us.
We look forward to further cooperation with you and your organization in ensuring the continued safe operations of non-power reactors.
Sincerely, Original signed by:
Marvin M. Mendonca, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosures:
1.
Safety Evaluation Report i
NUREG-0982 2.
NRC Rules and Regulations DISTRIBUTION w/o enclosures:
' Central file,)
ONDD r/f EHylton ACRS (10)
PDR BGrimes MMendonca AAdams i
TMichaels SWeiss OGC GFowler, 0IP JWechselberger, ED0
- See previous concurrence ONPD(tA ONDD:PM ONDD:PM*
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f Rostislav V. Nikolsky
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on Atomic Energy of the U.S. Congress.
I could not find clear-cut documentation on the bases of the value at this time. However, further information on the differences for regulation of test versus research reactors is best presented in the Project Manager Handbook (NUREG/BR-0073) Chapter 4, that we provided you on your trip.
You also inquired about documentation related to the use of containments for non-power reactors. Again as we discussed, the use of containments is based on the need to maintain acceptable radiological dose consequences for accident conditions. An example of the documentation for the use of containment is our Safety Evaluation Report (Enclosure 1) on the license renewal for the State University of New York at Buffalo.
We touched on the possibility of getting you a recent copy of NRC regulations, which I have provided as Enclosure 2.
This is the latest version that I have available to me at this time.
On behalf of Dr. Weiss, Messrs. Adams and Michaels, as well as myself, I want to express our pleasure in having the opportunity to talk to you on topics of non-power reactor safety.
If you have any further questions, requests, or i
information that you wish to share with us, please do not hesitate to contact us. We look forward to further cooperation with you and your organization in ensuring the continued safe operations of non-power reactors.
Sincerely, i
b%
Marvin M. Mendonca, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosures:
1.
Safety Evaluation Report NUREG-0982 z
2.
NRC Rules and Regulations l
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