ML19325C839

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Forwards 801020 Ltr Documenting Change of Licensee for Nuclear Science Ctr Reactor,Agreement Ltr Re Occupational Safety Advice & Revised Tech Spec Page 46
ML19325C839
Person / Time
Site: 05000128
Issue date: 10/13/1989
From: Feltz D
TEXAS A&M UNIV., COLLEGE STATION, TX
To: Michaels T
Office of Nuclear Reactor Regulation
Shared Package
ML19325C849 List:
References
NUDOCS 8910170318
Download: ML19325C839 (2)


Text

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' TEXAS ENGINEERING EXPERIMENT STATION

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TEXAS A&M UNIVERSITY

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ooLLEGE STATION TEXAS 77943 3576 I*

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13 October 1989 g g _

NUCLEAR SCIENCE CENTER 409'8454551 Mr. Theodore 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 v U.S. Nuclear Regulatory Commission

. Mail Stop 11H3 Washington, D.C. 20555 Attn:. ' Document Control Desk

.Ref: Docket No. 50-128 License R-83

Dear Mr. Michaels:

l In response to your telephone call of 12. October 1989 a copy of a letter dated 20 ' October 1980 provides documentation of the' change of the licensee for the Nuclear- Science Center Reactor (NSch) naming the Texas Engineering Experiment Station ao the licensee. The USNRC acknowledged at that time the stated changes to the . license _ renewal application, the technical spec 111 cations, and the SAR.

Subsequent documents issued by the 'USNRC headquarters regarding' R-83 amendments do not indicate this change.and the typographical error has gone unnoticed until your observation. I trust this item is now resolved.

i Also please find enclosed a copy of the agreement letter regarding occupational

safety advice and assistance provided the Texas Engineering Experiment Station (licensee) by the Safety and Health office of the Te::aa A&M University Sy stem.

As per your request I have enclosed- a. retype of page 146 of the Technical Specifi-

. cations with the only changes being the spelling out of the Nuclear Science Center (NSC) and the^ Nuclear Science Center Reactor (NGCR).

As I indicated to you the internal TEES organizational reactor administration structure is not part of the' license amendment, however, it will be described in

.the Standard Operating Procedures for the NSCR. These procedures will be reviewed by the Reactor Safety Board as well as any changes to the structure, h010 8

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.W. Theodore Michaels Page 2.,.

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If I can provide additional information please call me. Your prompt attention to the R-83 license amendment submittal of 4 september 1989 is very much appreciated.

[kNicerely.

T ,

[

nald E. Feltz ti Director DEF/ym

-Enclosure oc: Jon A. Reuscher, Nualear Science Center f

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