ML20196F236

Forwards Pages with Revised Organization Chart for Proposed Revised Tech Specs & for Decommissioning Plan

ML20196F236
Person / Time
Site:	General Atomics
Issue date:	06/22/1999
From:	Asmussen K GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:	Alexander Adams NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
38-67-3100, TAC-M98498, TAC-M98499, NUDOCS 9906290165
Download: ML20196F236 (5)

Text

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GENERAL ATCHHCE June 22,1999

. 38/67-3100 Via Express Delivery Service Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Mr. Alexander Adams, Jr.

Subject:

Docket Nos. 50-89 and 50163; License Nos. R-38 and R 67 Respectively: Submittal of Pages with Revised Organization Chart for Proposed Revised Technical Specifications and for Decommissioning Plan (TAC Nos. M98498 and M98499)

Dear Mr. Adams:

General Atomics recently submitted revised proposed Technical Specifications for its TRIGA*

, Mark I and Mark F non-power reactors. Those proposed revisions included an organization chan which was consistent with the organization chart GA had previously provided in it's TRIGA* Reactor Facility I Decommissioning Plan. Pursuant to our recent telephone conversation, GA revised those organization

, charts. Accordingly, please replace the previously submitted pages on which those organization charts appear in the Mark I and Mark F Technical Specifications and the Decommissioning Plan with the corresponding enclosed revised pages.

If you should have any questions regarding this submittal, please do not hesitate to con act me at (619)455-2823.

Very truly yours, swer bi&l 2.

fp - S) ' Keith E. Asmussen, Director Licensing, Safety and Nuclear Compliance hb

Enclosures:

1) Revised page no. 4 of GA's Mark I Technical Specifications (3 copies)

2) Revised page no. 6 of GA's Mark F Technical Specifications (3 copies)

3) Revised page no. 2-17 of GA's TRIGA* Reactor Facility Decommissioning Plan (3 copies)

! e cc: Mr. Ellis W. Merschoff, Director, NRC, Region IV (w/o enclosures) kh 9906290165 990 22 PDR ADOCK 05000009 l P PDR 1

l 3550 otNERAL ATOMICS COURT, SAN OLEGO, CA 92121-1194 P O. BOX 856D8. SAN DIEGO, CA 92186 9784 1619)455 3000 L _ _ _ _ _ ___

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altemate, for safe possession of the reactor and its associated equipment and for limiting exposure of personnel and dispersal of radioactive material. The reactor shall be related to the Corporate structure as shown in the following chart:

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_ _ ._ _ _. _. _ runesonal W 7.2 Criticality and Radiation Safety Commmee

a. There shall be a Criticality and Radiation Safety Committee (CRSC). The CRSC or a subcommittee thereof shall review activities of the facility to assure criticality and radiation safety. This Committee shall be composed of at least four members selected by the Cognizant Vice President, or a designee, considering their experience and education with regard to the various aspects of nuclear physics, chemistry, radiological health and statistics, as well as appropriate experience in other disciplines such as metallurgy and engineering.

Subcommittees shall be appointed by the Chairman of the CRSC. The subcommittee assigned ine responsibility for reviewing facility operations shall not have thereon person (s) who are directly involved with the facility.

b. The Criticality and Radiation Safety Committee shall be in accordance with a written charter including provisions for:

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These systems shall be calibrated annually and their set points verified monthly. For periods of time for maintenance or repair to the above systems, or during periods of other forced outages, the intent of this specification shall be satisfied if the installed system (s) is replaced with appropriate altemative or portable radiation monitors.

Following maintenance or modification of the radiation monitoring systems, the affected system shall be verified to be operable before returning it to routine operation.

7.0 FUELSTORAGE 7.1 All fuel elements or control elements with fuel followers shall be stored in a safe geometry (k,less than 0.8 under all conditions of moderation).

7.2 Irradiated fuel elements and control elements with fuel followers shall be stored in an array which will permit sufficient natural convection cooling by water or air such that the temperature of the fuel element will not exceed design values.

8.0 ADMINISTRATIVE REQUIREMENTS 8.1 Organization The facility shall be under the supervision of the Physicist-in-Charge or his designated attemate, both of whom shall be licensed senior operators of the facility. The minimum qualification for the Physicist-in-Charge shall include a Bachelor's degree or equivalent academic education and three years experience in activities related to reactor operations. He shall be responsible to a Vice President whose duties include responsibility for research and development, or his designated attemate, for safe possession of the reactor and its associated equipment and for limiting exposure of personnel and dispersal of radioactive material. The reactor shall be related to the Corporate structure as shown in the following chart:

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