ML19210C796
| ML19210C796 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 10/31/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210C792 | List: |
| References | |
| R-083-A-007, R-83-A-7, NUDOCS 7911200118 | |
| Download: ML19210C796 (7) | |
Text
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NUCLEAR REGULATORY COMMISSION E'
WASHINGTON. D. C. 20555 j
TEXAS A & M UNIVERSITY DOCKET NO. 50-128 AMENDMENT TO FACILITY LICENSE Amendment No. 7 License No. R-83 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Texas A & M University (the licensee) dated February 6,1979, as supplemented May 15, June 13 and August 21,.
1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comi.ssion; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be
' conducted in compliance with the Commission's regulations; 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.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and F.
Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in,10 CFR Section 2.106 (a)(2).
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility License No. R-83 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 7, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendinent'is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 31, 1979 13/3 25'7 o
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Attachment to License Amendment No. '7
[i Facility License No. R-83 Docket No. 50-128 1
e Appendix A is revised as follows:
REMOVE PAGES INSERT REVISED PAGES, 15 15
,l 15a (new page) 16 16 17 17
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3.6 LIMITATIONS ON EXPERIMENTS Acolicability This specification applies to experiments installed in the reactor and its experimental facilities.
Objective The objective is to prevent damage to the reactor or exces-sive release of radioactive materials in the event of an experiment failure.
Soecifications The reactor shall not be operated unless the following condi-tions governing experiments exist.
a.
Non-secured experiments shall have reactivity worths less than 1 dollar.
b.
The reactivity worth of any single experiment shall be less than 2 dollars.
c.
Explosive materials in quantities greater than five (5) pounds shall not be allowed within the reactor building.
Irradiation of explosive materials shall be restricted as follows:
(1)
Explosive materials in quantities greater than 25 milligrams shall not ba irradiated in the reactor pool.
Explosive materials in quantities less than 25 milligrams may be irradiated provided the pressure produced upon detonation of the explosive has been calculated and/or experimentally demonstrated to be less than the design pressure of the container.
(2) Explosive materials in quantities greater than 25 milligrams shall be restricted from the upper research level, demineralizer room, cooling equipment room and the interior of the pool containment. structure.
(3) Explosive materials in quantities greater than five (5) pounds shall not be irradiated in experimental facilities.
(4) Cumulative exposures for explosive materials ig2quantjties greater than 25 milligrams shall not exceed 10 n/cm for neutrons or 25 roentgen for gamma exposures.
d.
Experiment materials, except fuel 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) possible accident conditions in the ex::eriment shall be limited in activity such tnat if 100% of =e gaseous Amendment No. 7 l}/j
,
activity or radioactive aerosols produced escaped to the reactor room or the atomsphere, the airborne concentration af radioactivity averaged over a year would not exceed tie limit of Appendix B of 10 CFP. Part 20. e. In calculations pursuant to d. above, the following as3umptions shall be used: (1) If the effluent from an experimental facility exhausts through a holdup tank which closes automatically on high radiation level, at least 10% of th gaseous activity or aerosols produced will escape. (2) If the effluent from an experimental facility exhausts through a filter installation designed for greater than 99% efficiency for 0.3 micron particles, at least 10% of these vapors can escape. (3) For materials whose boiling point is above 130 F and where vapors formed by boiling this material can escape only through an undisturbed column of water above the coro, at least 10% of these vapors can escape. f. Each fueled experiment shall be controlled such that the total inventory of iodine isotopes 131 through 135 in the experiment is no greater than 1.5 curies. g. If a capsule fails and releases material which could damage the reactor fuel or structure by corrosion or other means, removal and physical inspection shall be performed to determine the cor. sequences and need for corrective action. The results of tne inspection and any corrective action taken shall be reviewed by the Director or his designated alternate and determined to be satisfactory before operation of the reactor is resumed. Bases a. This specification is intended to provide assurance that tru worth of a single unfastened experiment will be limited to a value such that the safety limit will not be exceeded if the positive worth of the experiment were to be suddenly inserted (SAR II, pg. 24). b. T1e maximum worth of a single experiment is limited so that its removal from the cold critical reactor will not result in the reactor achieving a power level high enough to exceed the core temperature safety limit. Since experiments of such worth must be fastened in place, its removal from the reactor operating at full power would resylt in a relatively slow power increase such that the reactor protective systems would art to prevent high power levels from being attained (SAR II, pg.21). !3/3 lua Amendment No. 7 - 15a -
c. This specification is intended to prevent damage to the reactor or reactor safety systems resulting from failure of an experiment involving explosive materials. 1. This specification is intended to prevent damage to the reactor core and safety related reactor components located within the reactor pool in the event of failure of an experiment involving the irradiation of explosive materials. Limited quantities of less than 25 milligrams and proper containment of such experiments provide the required safety for in pool irradiation. 2. This specification is intended to prevent damage to vital equipment by restricting the quantity a;1o location of explosive materials within the reactor building. Explosives in quantitier exceeding 25 milligrams are restricted from areas containing the reactor bridge, reactor console, pool water coolaat and purification systems and reactor safety related equipment. 3. The failure of an experiment involving the irradiation of up to five (5) lbs. of explosive material in an experimental facility located external to the reactor pool structure will not result in damage to the reactor or the reactor pool containment structure. 4. This specification is intended to prevent any increase in the sensitivity of explosive materials due to radiation damage during exposures. d. This specification is intended to reduce the likelihood that airborne activities in excess of the limits of Appendix B of 10 CFR Part 20 will be released to 'tne atmosphere outside the facility boundary of the NSC. e. The 1.5-curie limitation on iodine 131 through 135 assures that in the event of failure of a fueled experiment leading to total rele se of the iodine, the exposure dose at the exclusion area boundary will be less than that allowed by 10 CFR Part 20 for an unrestricted area. f. Operation of the reactor with the reacto' fuel or structure damage is prohibited to avoid release of fission products. 4.0 SURVEILLANCE REQUIREMENTS 4.1 GENERAL Apolicability This specification applies to the surveillance requirements of any system related to reactor safety. bI Amendmeat No. 7
0_bjective b The objective is to verify the proper operation of any system related to reactor safety. Specifications Any additions, modifications, or maintenance to the ventilation system, the core and its associated support structure, the pool or its penetrations, the pool coolant system, the rod drive mechanism, or the reactor safety system shall be made and tested in accordance with the specifications to which the systems were originally designed and fabricated or to specifi-cations approved by the Reactor Safety Board. A system shall not be considered operable until after it is successfully tested. Bases This specification relates to changes in reactor systems which could directly affect the safety of the reactor. As long as changes or replacements to these systems continue to meet the original design specifications, then it can be assumed that they meet the presently accepted operating criteria. 1373
- 02 Amendment No. 7
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