ML12166A536

Amendment 10 to Facility License R-23, Power Uprate to 5 Watts

ML12166A536
Person / Time
Site:	Texas A&M University
Issue date:	01/18/1973
From:	Skovholt D US Atomic Energy Commission (AEC)
To:	Luedecke A Texas A&M Univ
Boyle P
References
Download: ML12166A536 (4)

Text

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UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON, D.C. 20545 November 16, 1971 Docket Nos.

and 50-128 Texas A&M University ATTN:

A. R. Luedecke Executive Vice President College Station, Texas 77843 Change No.

1 Facility License No.

R-23 Change No.

10 Gentlemen:

Facility License No.

R-83 We have reviewed your letter dated October 11, 1971, requesting changes in the Technical Specifications for Facility Licenses Nos. R-23 and R-83 to reflect the change in name of the "Reactor Safety Advisory Committee" to the "Reactor Safety Board".

SSince the requested change is solely a name change and does not involve a change in the composition or function of the group, we have concluded that there is reasonable assurance that the health and safety of the public will not be endangered.

Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, the Technical Specifications of Facility Licenses Nos.

R-23 and R-83 are hereby changed to reflect the name of "Reactor Safety Board" in lieu of "Reactor Safety Advisory Committee" and "Committee" where they appear in the sections of the Technical Specifications listed below:

1. Sections 6.l.b and 6.2.b of the Technical Specifications for License No. R-23, and

2.

Sections E.4 and 5, 1.2 and 4, and Jl and 2 of the Technical Specifications for License No.

R-83.

Sincerely, Donald J.4kovholt Assistant Director for Reactor Operations Division of Reactor Licensing

UNITED STATES ATOMIC ENERGY CM SItfr WASHINGTON. D.C. 20545 January 18, 1973

/Y0/17",,

Docket No. 50-59 Texas A&M University ATTN:

Mr. A. R. Luedecke Executive Vice President College Station, Texas 77843 Gentlemen:

In accordance with your application dated September 27, 1972, Amendment No.

10 to Facility License No. R-23 is enclosed.

This amendment authorizes operation of your AGN-201 reactor at power levels up to 5 watts (thermal) and redesignates the reactor as Model AGN-201M.

Prior to operation of the reactor at 5 watts, the modifications shall have been completed as described in your application dated September 27, 1972, and evaluated by us in our Safety Evaluation dated December 13, 1972.

Your proposed changes to the Technical Specifications for operation at 5 watts have been reviewed pursuant to Section 50.59 of 10 CFR Part 50.

We have determined that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the reactor in the manner proposed.

Consequently, the Technical Specifications of Facility License No. R-23 are hereby changed as set forth in the enclosed Change No. 2.

As required by Commission regulations, the enclosed Notice of Issuance of Facility License Amendment has been filed with the Office of the Federal Register for publication.

Sincerely, nald J' Skovholt Assistant Director for Operating Reactors Directorate of Licensing Enclosures and cc:

See next page m

Texas A&M University

-2 January 18, 1973

Enclosures:

1.

Amendment No. 10

2.

Change No. 2

3.

Federal Register Notice cc w/enclosures:

Honorable Preston Smith Governor of Texas Austin, Texas 78711 J. E. Pevy, M. D.

Commissioner of Health State Department of Health 1100 West 49th Street Austin, Texas 78785 Mr. J. B. Roberts, Chairman Industrial Accident Board State Finance Building Austin, Texas 78701 Mr. Martin C. Wukasch, Director Division of Occupational Health and Radiation Control Texas State Department of Health Austin, Texas 78756 Mr. D. A. Anderson Mayor, City of College Station College Station, Texas 77843

CHANGE NO. 2 TO THE TECHNICAL SPECIFICATIONS LICENSE NO.

R-23 TEXAS A&M UNIVERSITY DOCKET NO.

50-59

1. Revise page 2 paragraph 3.3 to read:

3.3 Each of the safety channels in Table I shall be operating whenever any control or safety rod is not in its fully withdrawn position.

Each of the operating safety channels shall sound an alarin,-ano cause reactor shutdown if the limiting safety system setting is reached.

2.

Change Table I to read as follows:

TABLE I Nuclear Instrumentation Function Low count rate Low power High power Short reactor period Safety Channel Nuclear Safety No. I Nuclear Safety Nos. 2 & 3 Nuclear Safety Nos. 2 & 3 Nuclear Safety No.

2 Limiting Safety System Setting Z 10 cps loss of signal (ZlXlO-1 2 amps) 6200% of licensed power 5 second minimum period 0