ML20197H804
| ML20197H804 | |
| Person / Time | |
|---|---|
| Site: | University of California-Davis |
| Issue date: | 12/09/1998 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20197H788 | List: |
| References | |
| R-130-A-001, R-130-A-1, NUDOCS 9812140176 | |
| Download: ML20197H804 (5) | |
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p om4 p 1 UNITED STATES j
g NUCLEAR REGULATORY COMMISSION o, f WASHINGTON, D.C. 20566-0001
- '+9. . . . . ,o DEPARTMENT OF THE AIR FORCE AT McCLELLAN AIR FORCE BASE DOCKET NO. 50-607 AMENDMENT TO FACILITY OPERATING LtCENSE Amendment No.1 License No. R-130
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that A. The application for an amendment to Facility Operating License No. R-130 filed by the Department of the Air Force at McClellan Air Force Base (the licensee) on November 18,1998, conforms to the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as stated in Chapter i of Title 10 of the Code of federa/ Regulations (10 CFR):
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance that (l) the 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; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; 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 was not required by 10 CFR 2.105, and publication of notice for this amendment is not required by 10 CFR 2.106.
9812140176 981209 PDR ADOCK 05000607 P PDR s
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(ii) of Facility Operating License No. R-130 is hereby amended to read as follows:
2.C.(ii) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.1, are hereby incorporated in the license. The licensee shall operate 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 W
Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Encloture:
Appendix A, Technical Specifications Changes Date of issuance:
_ . . _ -______...__m...--
. i ENCLOSURE TO LICENSE AMENDMENT NO.1 i s
i FACIL!TY OPERATING LICENSE NO. R-130 ,
DOCKET NO. 50-607 ;
Replace _the following pages of Appendix A, " Technical Specifications," with the enclosed
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. pages. The revised pages are identified by amendment number and contain vertical lines ;
indicating the areas of change. ;
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- c. This specification is intended to prevent damage to vital equipment by restricting the quantity of explosive materials within the reactor tank (SAR Chapter 13, Section 13.2.6.2). -
- d. The failure of an experiment involving the irradiation of 3 lbs TNT equivalent or less in any radiography bay external to the reactor tank will not result in r damage to the reactor controls or the reactor tank. Safety Analyses have been performed (SAR Chapter 13, Section 13.2.6.2) which show that up to six (6) lbs of TN' equivalent can be safely irradiated in any radiography bay. Therefore, the three (3) lb limit gives a safety margin of two (2).
3.8.3 Failure and Malfunctions Applicability. This specification applies to experiments installed in the reactor, in-tank experiment facilities, and radiography bays.
Objective. The objective is to prevent damage to the reactor or significant releases of radioactive materials in the event of an experiment failure.
Specifications.
- a. All experiment materials which could off-gas, sublime, volatilize, or produce aerosols under (1) normal operating conditions of the experiment or reactor, (2) credible accident conditions in the reactor, or (3) where the possibility exists that the failure of an experiment could release radioactive gases or aerosols into the reactor building or into the unrestricted area, the quantity and type of material in the experiment shall be limited such that the airborne radioactivity in the reactor room or the unrestricted area will not result in exceeding the applicable dose limits in 10 CFR Part 20, assuming '
100% of the gases or aerosols escape.
- b. In calculations pursuant to (a) above, the following assumptions shall be used:
(1) If the effluent from an experiment facility exhausts through a stack which is closed on high radiation levela, at least 10% of the gaseous activity or aerosols produced will escape.
(2) If the effluent from an experiment facility exhausts through a filter installation designed for greater than 99% efficiency for 0.3 micron and larger particles, i at least 10% of these will escape.
(3) For materials whose boiling point is above 130'F and where vapors formed by boiling this material can escape only through an undistributed column of water above the core, at least 10% of these vapors can escape.
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- c. If a capsule fails and releases material which could damage the reactor :
fuel or structure by corrosion or other means, an evaluation shall be made to determine the need for corrective action. Inspection and any corrective action taken shall be reviewed by the Facility Director or his designated alternate and determined to be satisfactory before operation of the reactor is resumed.
Basis
- a. This specification is intended to reduce the likelihood that airborne radioactivity in the reactor room or the unrestricted area will result in exceeding the applicable dose limits in 10 CFR Part 20.
- b. These assumptions are used to evaluate the potential airborne radioactivity release due to an experiment failure (SAR Chapter 13, Section 13.2.6.2).
- c. Normal operation of the reactor with damaged reactor fuel or !
structural damage is prohibited to avoid release of fission products. Potential damage to reactor fuel or structure must be brought to the attention of the Facility Director or his designated alternate for review to assure safe operation of the reactor (SAR Chapter 13, Section 13.2.6.2).
4.0 Surveillance Requirements.
General. The surveillance frequencies denoted herein are based on continuing operation of the reactor. Surveillance activities scheduled to occur during an operating cycle which can not be performed with the reactor operating may be deferred to the end of the operating cycle. If the reactor is not operated for a reasonable time, a reactor system or measuring channel sun'eillance requirement may be waived during the associated time period. Prior to reactor system or measuring channel operation, the surveillance shall be performed for each reactor system er measuring channel for which surveillance was waived. A reactor system or measuring channel shall not be considered operable untilit is successfully tested.
4.1 Reactor Core Parameters.
4.1.1 Steady State Operation.
Applicability. This specification applies to the surveillance requirement for the power level monitoring channels.
Objective. The objective is to verify that the maximum power level of the reactor does noc exceed the authorized limit.
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