ML20151C059
| ML20151C059 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 07/12/1988 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151C055 | List: |
| References | |
| R-097-A-007, R-97-A-7, NUDOCS 8807210211 | |
| Download: ML20151C059 (11) | |
Text
, . .
8 o g UNITED STATES
[ g NUCLEAR REGULATORY COMMISSION .
5 : j WASHINGTON, D. C. 20555 l
- %y ,f l
J GEORGIA INSTITUTE OF TECHNOLOGY DOCKET NO. 50-160 ;
AMENDlfENT TO FACILITY OPERATING LICENSE' l Amendment No. 7 ;
License No. R-97 j i
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
1 A. The applications for amendment to Facility Operating License No. R-97 filed by the Georgia Institute of Technology (the licensee), dated August 6,1987, as supplementad, and rfarch 1,1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the applications, the provisions of the Act, and the regulations of the Comission; 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 set forth in 10 CFR Chapter I; 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 amendnent 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).
8807210211 880712 PDR ADOCK 05000160 P PNU
l l
- 2. Accordingly, paragraph 2.B.(2) of Facility Operating License No. R-97 is l hereby amended to read as follows: l 1
(2) Pursuant to the Act and 10 CFR Part 70, "Domestic Licensing of l Special Nuclecr Material," to receive, possess and use at any one time in connection with operation of the reactor up to 13.5 kilograms of contained uranium 235.
- 3. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of License No. R-97 is hereby amended to read as follows:
(2) Technical Specifications l
The Technical Specifications contained in Appendix A, as revised i through Amendment No. 7, are hereby incorporated in the license.
The Georgia Institute of Technology shall operate the facility in accordance with the Technical Specifications.
- 4. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
. -~ _
E' &
Lester S. Rubenstein, Acting Director Standardization end Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation p n xkTechnical I Specifications Changes l Date of Issuance: July 12, 1988
ENCLOSURE TO LICENSE AMENDMENT NO. 7 FACILITY OPERATING LICENSE NO. R-97 DOCKET NO. 50-160 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Pages Insert Pages.,
20 20 20a 23 23 24 24 39 39 40 40 41 41 41a
\ l
\.
1 1
1
)
3.5 RADI0 ACTIVE EFFLUENTS l
APPLICABILITY This specification applies to the controlled release of radioactive ,
liquids and gases from the reactor site. l OBJECTIVE l
To define the limits and conditions for the release of radioactive effluents to the environs to assure that any radioactive effluents are as l low as practicable and would not result in radiation exposures greater i than a few percent of nattr/al background expos s es and, in any event, !
within the limits of 10 CFR Part 20 for instantaneous release rates.
1 SPECIFICATIONS
- a. Liquid Effluents (1) The concentration of gross radioactivity, above background, in .
liquid effluents discharged from the Reactor Building to the l sanitary sewer shall not exceed 3 x 10-6 microcuries/ml, l excluding tritium, unless the discharga is controlled on a radionuclide basis in accordance with Appendix B, Table II, Column 2 and Note 1 thereto of 10 CFR Part 20.
(2) The concentration of tritium in liquid effluents discharged to the sanitary sewer shall not exceed 1 X 10 -I microcuries/ml. l (3) If any of the limits of Specification a(1) or (2) are exceded, normal orderly shutdown of the liquid waste system shall be initiated and liquid discharge from the facility shall not be resumed until the ause of the excessive discharge rate is identified and corrected.
(4) The annual total quantity of gross radioactivity to be released in liquid effluents from the reactor facility shall not exceed one curie to the sanitary sewerage system.
(5) Before discharging any liquid waste from any of the holdup tanks, the following shall be performed:
- 1. Isolate ti.e tank to be cmptied so that no liquid waste can be added during discharge.
Amendment No. 7
-20a-
- 2. Obtain a sample and analyze for content si ra/loactivity. l
'f the radioactivity in that sample is within the limits l vf specifications 3.5.a.'l and 3.5.a.2, release to sanitary I severage system may begin. The process of discharging the !
-114,,1d vaste from that tank shall be stopped at a point past the discharge halfely mark, but before the tank is 75% dischc"ged, to analyze another sample. If results of the second anaIysis are within specified limits, release of the rest of the liquid waste may resume. The time for completing the second discharge shall be 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the
, start.
(6) Equipment installed for the control and treatment of liquid effluents shall be maintained and operated.
/
I l
l l
l l
I Amendment No. 7 l
1 appropriate data is collected for determining the nearest real cow. 1 The formula prescribed in the specification for release of I particulates with half lives greater than eight days takes into consideration the additional reduction of MPC limits by the factor of 700 for poseible ecological chain effects.
Isolation of the exhaust effluent stack is initiated by high radiation in the off-gas system. Such isolation is required for abnormally high gross radioactivity releases either due to abnormal reactor operation or reactor accident.
l I
3.6 PRIMARY COOLANT SYSTEM APPLICABILITY This specification applies to f ne limiting conditions for the primary coolant system pH, resisth.ty, flow distfibution, level and D2 concentration.
OBJECTIVE To assure adequate reactor core cooling and to protect the integrity of the primary coolant system.
SPECIFICATIONS The reactor shall not be critical unless:
- a. The primary coolant pH is between 4.5 and 7.5.
- b. The primary coolant resistivity is at a value greater than 200,000 ohm-cm except for periods of time not to exceed seven days when the resistivity may fall to 70,000 ohm-cm.
- c. All grid positions contain fuel elements, grid plugs or experimental facilities for operation in the forced convection mode.
- d. The reactor vessel coolant level is within 12 inches of the overflow standpipe level.
- e. The D2 e ncentration in the cover gas sweep system is less than 2% by volume. The cover gas shall be helium or nitrogen.
- f. The concentrations of radioactive materials in the secondary coolant system are less than the values listed in 10 CFR 20, Appendix B. Table II, column 2.
Amendment No. 7
- r. 24-1 BASIS Experience at GTRR and other facilities has shown that the maintenance of primary coolant system water quality in the ranges specified in Specification 3.6.a and 3.6.b will minimize the amount and severity of corrosion of the aluminum components of the primary coolant system and the fuel clement cladding.
The requirement that all grid positions be occupied will prevent the degradation of calculated flow rates due to flow bypassing the active fueled region through an unoccupied grid plate position.
The limiting value for reactor vessel coolant level is somewhat arbitrary since the core is in no danger of melting so long ss it is l covered. However, a drop of vessel coolant level /indicstes a malfunction of the reactor system and possible approacn to uncovering the core. Therefore a measurable value, well above the core is chosen. Determination of the worth of the top reflector drain requires operation of the reactor at low power levels without a restriction on reactor vessel coolant level.
Because of radiolytic disassociat{an of D 0,2 deuterium and oxygen gas will build up in the cover gas sweeo system. If this 02 gas were to l reach an explcsive concentration (about 7.8% by voluma at 25*C in J helium),III damage to the primary system could occur. To assure a substantial margin of safety, a limi' of 2% is set.
REFERENCES III "Flamability of Deuterium in Oxygen-Helium Mixtures," USAEC Report No. TID 20898, Explosives Research Center, Bureau of Mines, June 1964.
3.7 EMERGENCY COOLING SYSTEM APPLICABILITY These specificotions apply to the emergency core cooling system.
OBJECTIVE To assure that the fuel elements are adequately cooled to prevent fission product release in the event of loss of primary coolant from the reactor vessel.
Amendment No. 7
I l l . .
\ .
t
- , l Office of the !
President l
Nuclear Office of the Vice Safeguards '
President for Committee (Chr:
Research , Radiation Safety Officer) l s r , I l
&R g Office of the mumuwd faferfPybeY) 3 NNRC Director Supervision, Acmin. Reporting
< , < , r , , ,
hfanager of hianager of Coordinator of Afanager, Office Reactor Gamma Radiation Experimental of Radiation Operations Operations Research Safety ,
' > < > u > < >
1 Figure 6.1 Georgia Tech Organization for Management and Operation of GTRR.
Amendment No. 7
l l
l l
~
1 l
1
- e. An operator or senior operator licensed pursuant to 10 CFR 55 l shall be present at the controls unless the reactor is shutdown l as defined in these specifications.
l 6.2 NUCLEAR SAFEGUARDS COMMITTEE
- a. A Nuclear Safeguards Comittee shall be established by the President of the Institute and shall be responsible for maintaining health and safety standards associated with operation of the reactor and its associated facilities.
- b. The Committee shall be composed of five or more senior l technical personnel who collectively provide experience in reactor engineering, reactor operations, chemistry and radiochemistry, instrumentation and control Aystems, radiological safety, radiation protection, and mechanical and l electrical systems. No more than a minority of the Comittee members shall be from the GTRR staff.
- c. The Comittee shall meet quarterly and as circumstances warrant. Written records of the proceedings, including any recommendations or occurrences, shall be distributed to all Comittee members and the President's Office. I
- d. The quorum shall consist of not less than a majority of the Comittee membership and shall include the chairman or his designated alternate. The operating staff may not constitute a majority of those present.
- e. The Comittee shall:
(1) Review and approve determinations that proposed chanjes in equipment, systems, tests, experiments, or procedures do not involve an unreviewed safety question pursuant to 10 CFR 60.59(a).
(2) Review reportable occurrences.
(3) Review and approve proposed operating procedures and proposed changes to operating procedures. liinor modifications to operating procedures tihich do not change the original intent of the operating procedure may be approved by the Director of NNRC on a temporary basis, l The Committee shhll consider for approval such minor modifications at its next scheduled meeting.
Amendment No. 7 i
~41-(4) Review and approve proposed changes to Technical Specifications and license excluding organizational-structure. The respoiisibility and authority for organizational structure resides with the President of the Institute.
(5) Review and approve proposed experiments and tests utilizing the reactor facility which are significantly different from tests and experiments previously performed at the GTRR.
(6) Review and approve proposed changes to the facility made pursuant to 10 CFR 50.59(c).
(7) Review violations of Technical Specifidations, license, or internal procedures or instructions having safety significance.
(8) Review operating abnormalities having safety significance.
(9) Review audit reports.
(10) Audit reactor operations and reactor operation records for compliance with internal rules, procedures, and regulations and with licensed provisions including Technical Specifications at least once per calendar year (interval between audits not to exceed 15 months).
(11) Audit the retraining and requalification progran for the operating staff, at least once every other calendar year (interval between audits not to exceed 30 months).
(12) Audit the results of action taken to correct those deficiencies that may occur in the reactor facility equipment, systems, structures, or methods of operations that affect reactor safety, at least oilce per calendar yedt (interval between audits not to exceed 15 months).
Amendment No. 7
. -41a-6.3 ADMINISTRATIVE CONTROLS OF EXPERIMENTS
- a. Evaluation by Safety Review Group (1) No experiment shall be performed without review and approval by the Nuclear Safeguards Ccmmittee. Repetitive i experiments with common safety considerations may be !
reviewed and approved as a class.
(2) Criteria for review of an experiment or class of i experiments shall include (a) applicable regulatory positions including those in 10 CFR Part 20 and the technical specifications and (b) in-house safety criteria and rules which have been established for facility I operations, including those which govern requirements for encapsulation, venting, filtration, shielding, and similar experiment design considerations, as well as those which govern the quality assurance program required under 50.34. i (3) Records shall be kept of the Nuclear Safeguards l Committee's review and authorization for each experiment !
or class of experiments. !
- b. Operations Approval (1) Every experiment shall have the prior explicit written approval of the Licensed Senior Operator in charge of reactor operations. j (z) Every person who is to carry out an experiment shall be )
certified by the Licensed Senior Operator in charge of reactor operations as to the sufficiency of his knowledge and training in procedures required for the safe conduct I of the experiment. I i
- c. Procedures for Active Conduct of Experiments l (1) Detailed written procedures shall be provided for the use or operation of each experimental facility.
4 Amendment No. 7
_ - . _