ML20147C420: Difference between revisions

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| number = ML20147C420
| number = ML20147C420
| issue date = 11/13/1978
| issue date = 11/13/1978
| title = Recommends Approval of Amend Appl to lic#SNM-123 to Allow an Addl 30g Pu as a 2-curie Pu-Be Neutron Source
| title = Recommends Approval of Amend Appl to Lic SNM-123 to Allow an Addl 30g Pu as a 2-curie Pu-Be Neutron Source
| author name = Delaney J
| author name = Delaney J
| author affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
| author affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)

Latest revision as of 05:23, 8 August 2022

Recommends Approval of Amend Appl to Lic SNM-123 to Allow an Addl 30g Pu as a 2-curie Pu-Be Neutron Source
ML20147C420
Person / Time
Site: 07000144
Issue date: 11/13/1978
From: Delaney J
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 7812180261
Download: ML20147C420 (1)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION g j WASHINGTON, D. C. 20555 e

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DOCKET NO.: 70-144 APPLICANT: The Pennsylvania State University (PSU)

SUBJECT:

AMENDMENT APPLICATION DATED OCTOBER 20, 1978

Background

The subject October 20, 1978, application requests that Special Nuclear Material License SNM-123 be amended to allow the use of an additional 30 grams of Pu as a 2-curie Pu-Be neutron source.

Discussion PSU is currently licensed to possess 165 grams of Pu in the form of Pu-Be ne'Jtron Sources. They request authorization to receive an additional 30 grams Pu as Pu-Be neutron Sources.

Radiation Safety An increase f *om 165 to 195 grams of Pu in Pu-Be neutron sources does not require any modification of the PSU radiation safety program.

The existing program is satisfactory.

Nuclear Safety The quantity of special nuclear material licensed under SNM-123 is insufficient to attain a critical mass.

Recommendation It is recommended that the amendment application be approved.

hs J. C. Delan Fuel Processing & Fabrication Branch Division of Fuel Cycle and Material Safety f f Approved by [b # . 4dd

~ W. T. Crow 7 812180 2G( t