ML20154B473

Amend 44 to License R-67,replacing Criticality Safeguards Committee with Criticality & Radiation Safety Committee, Decreasing Frequency of Audits from Quarterly to Annually & Changing Administrative Requirements Section of TSs

ML20154B473
Person / Time
Site:	General Atomics
Issue date:	10/01/1998
From:	Weiss S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20154B471	List: ML20154B466 ML20154B473 ML20154B485
References
R-67-A-044, R-67-A-44, NUDOCS 9810050223
Download: ML20154B473 (5)

Text

.

eam y 1 UNITED STATES y

j 2

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20046 4 001

%***** /  !

1 l

GENERAL ATOMICS DOCKET NO. 50-163 AMENDMENT TO FACILITY LICENSE Amendment No. 44 License No. R-67 l

l j

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that A. The application for an amendment to Facility License No. R-67 filed by General  ;

Atomics (the licensee) on July 16,1998, conforms to the standards and  ;

requirements of the Atomic Energy Act of 1954, as amended (the Act), and the l regulations of the Commission as stated in Chapter I of Title 10 of the Code of FederalRegulations (10 CFR);

B. The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l

C. There is reasonable assurance that (i) tne activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) such activities will be conducted in compliance with the regulations of the Commission- 1 i

D. The issuance of this amendment will not be inimical to the common defense and I security or to the health and safety of the public; i E. This amendment is issued in accordance with the regulations of the Commission as stated in 10 CFR Part 51, and all applicable requirements have been satisfied; and F. Prior notice of this amendment is not required by 10 CFR 2.105, and publication of notice for this amendment is not required by 10 CFR 2.106, 9810050223 981001 PDR ADOCK 05000163 P PDR ,

4 1 2

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph C.2. of Facility '

License No. R-67 is hereby amended to read as follows:

2. Technical Soecifications i

The Technical Specifications contained in Appendix A, as revised through Amendment No. 44, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION l

Seymour H.' Weiss, Director Non-Power Reactors and Decommissioning ,

Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation i

i i

Enclosure:

' Appendix A, Technical Specifications Changes Date of Issuance: October 1, 1998 4

E 4 4 i

l I

'u c- --. n

- -, .mi.y

~

ENCLOSURE TO LICENSE AMENDMENT NO. 44 FACILITY LICENSE NO. R-67 DOCKET NO. 50-163 Replace the following pages of Appendix A, " Technical Specifications," witn the enclosed pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of change .

Remove lDsmi 7(a) 7(a)

., 8 8 8

4 T'

a 4

=

d 1

i i

l l

8.0 ADMINISTRATIVE REQUIREMENTS 8.1 Organization 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 j for research and development, or his designated alternate, for safe possession l of the reactor and its associated equipment. l 8.2 Criticality and Radiation Safety Committee l

a. There shall be a Criticality and Radiation Safeguards Committee (CRSC) which shall review activities of the facility to assure criticality and radiation safety. This Committee shall be composed of at least four l 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 l 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 l 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 appmve safety standards associated with possession of the Facility. The CRSC or a subcommittee thereof shall audit the Fru 'y 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:

I

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

2. Review and approval of all proposed changes to the facility, procedures, and Technical Specifications; 7(a) Amendment No. 44

5

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

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 Reportable Occurrences under 10 CFR Part 20 and 10 CFR Part 50.

8.3 Written Procedures 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 judgmeat 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,

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

Changes which alter the originalintent 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 l change their original intent and do not constitute an unreviewed safety question (as defined in 10 CFR 50.59) 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 9.1 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).

8 Amendment No. 44