ML20236Q579

Proposed Tech Specs,Revising Mark F Triga TS to Be Consistent W/Mark I Reactor TS

ML20236Q579
Person / Time
Site:	General Atomics
Issue date:	07/16/1998
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20236Q578	List: ML20236Q575 ML20236Q579
References
NUDOCS 9807200349
Download: ML20236Q579 (2)

Text

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8.0 , ADMINISTRATIVE REQUIREMENTS 8.1 Organization i

The facility shall be under the supervision of the Physicist-in-Charge or his designated alternate, who shall be a licensed senior operator of the facility. He shall be responsible to a Vice President whose duties include responsibility for research and development, or his designated alternate, for safe possession of the reactor and its associated equipment.

8.2 Criticality and Radiation Safety Committee

a. There shall be a Criticality and Radiation Safeguards Committee (CRSC) which shall review activities of the facility to assure criticality and radiation l 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 the responsibility for reviewing facility operations shall not have thereon person (s) who are directly involved with that facility.

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

1. Hold meetings or audits at least annually; special meetings may be called by subcommittees of the CRSC or by the Chairman of the CRSC at times when such meetings are deemed appropriate.

2. Have a quorum when a majority of the members attend.

3. Prepare minutes or audit findings of the CRSC meetings by Chairman or his designee. Evidence of approval of the participating members of the CRSC shall be obtained before distribution.

c. The Criticality and Radiation Safety Committee, or subcommittee, shall review and approve safety standards associated with possession of the Facility. The CRSC or a subcommittee thereof shall audit the Facility annually, but at intervals not to exceed fifteen (15) months,

d. The responsibilities of the Committee or designated subcommittee thereof include, but are not limited to, the following:

1. Review and approval of experiments utilizing the reactor facilities in accordance with Section 10.1;

2. Review and approval of all proposed changes to the facility, procedures, and Technical Specifications; j 7(a)

Amendment No. 44 DR j P

3. Determination of whether a proposed change, test, or experiment would constitute an unreviewed safety question or a change in the Technical )

Specifications; l 4. Review of Facility records;

5. Review of abnormal performance of plant equipment and other anomalies; and

6. Review of unusual or abnormal occurrences and incidents which are i Reportable Occurrences under 10 CFR 20 and 10 CFR 50.

1 8.3 Written Procedures l Written instructions shall be in effect for the following items. The instructions shall be adequate to assure the safe possession of the reactor but shall not preclude the use of independent Judgment and action should the situation require such.

a. Testing and calibration of instrumentation, controls, and radiation monitors necessary to meet the requirements of the Technical Specifications.  !

b. Emergency and abnormal conditions including provisions for evacuation,  !

reentry, recovery, and medical support.

c. Fuel element and experiment loading or unloading.

d. Maintenance of systems necessary for assuring the integrity of the fuel or otherwise maintaining the reactor in POLA status. l

e. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormal reactivity changes. '

Changes which alter the original intent of the above procedures shall be made only with the approval of the Criticality and Radiation Safety Committee (CRSC). Temporary changes to the procedures that do not change their original intent and do not constitute an unreviewed safety question (as defined in 10CFR50.59) may be made by the Physicist-in-Charge. All such temporary changes shall be documented and subsequently reviewed by the CRSC.

9.0 REACTOR OPERATIONS 0.1 Maximum Operating Power Level 9.1.1 The operating power level of the reactor shall not be intentionally raised above 1500 kilowatts except for pulsing operations (see Specification 9.2).

i l 8 Amendment No. 44

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