ML20237G283

Proposed Tech Specs,Changing D2 Concentration in Helium Sweep Sys to Concentration in Cover Gas Sweep Sys

ML20237G283
Person / Time
Site:	Neely Research Reactor
Issue date:	08/06/1987
From:	Neely Research Reactor, ATLANTA, GA
To:
Shared Package
ML20237F958	List: ML20237F955 ML20237G283
References
NUDOCS 8708130386
Download: ML20237G283 (6)

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3.5 RADIOACTIVE EFFLUENTS APPLICABILITY I

This specification applies to the controlled release of radioactive liquids and gases from the reactor site.

OBJ ECTIVE i

To define the limits and conditions for-the release of radioactive ]

effluents to the environs to assure that any radioactive effluents are as low as practicable and would not result in radiation exposures greater than a few percent of natural background exposures and, in any event, within the limits of 10 CFR Part 20 for instantaneous release rates. I SPECIFICATIONS

a. Liquid Effluents (1) The concentration of gross radioactivity, above background, in liquid effluents dischar6ed from the Regetor Building to the sanitary sewer shall not exceed 3 x to microcuries/ml, excluding tritium, unless the discharge is controlled on a radionuclides 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 efflyents discharged to the sanitary sewer shall not exceed 1 x 10 microcuries/ml.

(3) If any of the limits of Specification a(1) or (2) are exceeded, normal orderly shutdown of the liquid waste system shall be initiated and liquid discharge from the facility shall not be resumed until the cause 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 the tank to be emptied so that no liquid waste can be added during discharge.

2. Obtain a sample and analyze for content of radioactivity.

If the radioactivity in that sample is within the limits of specifications 3.5.a.1 and 3.5.a.2, release to sanitary sewerage system may begin. The process of discharging the liquid waste from that tank shall be stopped at a point past the halfway mark, but before the tank is~ emptied, to analyze another sample. If results of the second analysis are within specified limits, release of the rest of the liquid i 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 /> after the stoppage for the second analysis.

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(6) Equipment installed for the control and treatment of liquid effluents shall be maintaincd and operated.

5708130386 070806 PDR- ADOCK 05000160 '

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NEW appropriate data-is. collected.for determining the nearest real cow. The formula prescribed in the specification for release of particulate with halflives' greater than eight days takes.into consideration the additional reduction of MPC limits by- the factor of 700 for possible 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.

3.6 PRIMARY COOLANT SYSTEM-APPLICABILITY This specification appliei to the limiting conditions for the primary coolant system pH, resistivity, flow distribution level and D 2

concentration.

OBJECTIVE ,

i 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. Th3 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 pcsitions contain fuel elements, grid plugs or experimental facilitiea f<a operation in the forced convection mode,

d. The reactor vessel- coolant level is within 12 inches of the overflow standpipe level. i

c. The D n entration in the cover gas sweep system is less than 2% by 2

volume,

f. The concentrations of radioactive caterials in the secondary coolant system are less than the values listed in 10 CFR 20, Appendix B, Table II, column 2.

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NEW 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 i corrosion of the aluminum components of the primary coolant system and the  !

fuel element cladding.

l The requirement that all grid positions be occupied will prevent the degradation of calculated flow rates due to flow bypassing the active 1

fueled region through an unoccupied grid plate position.

Ihe limiting value for reactor vessel coolant level is somewhat arbitrary I since the core is in no danger of melting so long as it is covered.

However, a drop of vessel coolant level indicates a malfunction of the reactor system and possible approach 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 disassociation of D 0,2 deuterium and oxygen gas will build up in the cover gas sweep system. If this D Bas gwere to 2

reach an(yyplosive concentration (about 7.8% by volume ai 25 C in helium), damage to the primary system could occur. To assure a substantial margin of safety, a limit of 2% is set.

REFERENCES (1)" Flammability 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 specifications 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.

OFFICE OF THE _ , , _ . _ _ _ _ _ _ _ . _ _ _ j PRESIDENT I l

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OFFICE OF THE l VICE PRESIDENT FOR l RESEAPCH l

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NUCLEAR SAFEGUARDS OFFICE OF THE COMMITTEE NNRC DIRECTOR (CHAIRMAN: RADIATION SAFETY OFFICER)

MANAGER OF MANAGER OF MANAGER OF COORDINATOR OF' Tl:E OFFICE OF REACTOR HOT CELL EXPERIMENTAL RADIATION OPERATIONS OPERATIONS RESEARCH l SAFETY FIGURE 6.1: GEORGIA TECH ORGANIZATION FOR MANAGEMENT AND OPERATION OF GTRR

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e. An operator or senior operator licensed pursuant to 10 CFR 55 shall be present at the controls unless the reactor is shutdown as defined in these specifications..

l -6.2 NUCLEAR SAFEGUARDS COMMITTEE-

a. A' Nuclear Safeguards. Committee 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 senior technical personnel who collecti" sly provide experience in reactor engineering, reactor operations, chemistry and radiochemistry, instrumentation and control systems, radiological safety, radiation protection, and mechanical and electrical' systems'.

c. The Committee shall meet quarterly and as circumstances warrant.

Written records of the proceedings, including any recommendations or occurrences, shall be distributed to all Committee members and the President's office,

d. The quorum shall consist of not less than'a majority of the full committee and shall include the chairman or his designated alternate.

e. The Committee'shall:

1 Review and. approve proposed experiments and tests utilizing the reactor facility which are significantly different from tests and experiments previously performed at the GTRR.

2. Review reportable-occurrences.

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3. Review and' approve proposed operating procedures and proposed d changes to operating procedures. Minor modifications to operating procedures which do not change the original intent of the operating procedure may be approved- by the Director of NNRC on a temporcry basis. The Committee shall consider for approval such minor modifications at its next scheduled meeting. All minor-  ;

modifications must be approved by the Committee. j

'l 4 Review and approve proposed changes to the facility made pursuant .j to 10 CFR 50.59(c). i

5. Review and approve proposed changes to Technical Specifications excludfrq organizational structure. The responsibility and authority for organizational structure resides with the President ,

of the Institute.

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NEW p 6 Audit reactor operations and reactor operation records for compliance with internal rules, procedures, ar.d regulations and with licensed provisions including Technical Specifications.

7. Audit existing operating procedures for adequacy and to assure that they achieve their intended purpose in light of any changes since their implementation,

8. Audit plant equipment performance with particular attention to operating anomalies, reportable occurrences, and the steps taken to identify and correct their causes.

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 Committee. Repetitive experiments with common safety considerations may be reviewed and approved as a class.

(2) Criteria for review of an experiment or class of 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 operations, including those which govern requirements for encapsulation, venting, filtration, shielding, and similar experiment design considerations, as well as those which govarn the quality assurance program required under 50.34 (3) Records shall be kept of the Nuclear Safeguards 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. '

(2) 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 of the experiment.

c. Procedures for Active Conduct of Experiments (1) Detailed written procedures shall be provided for the use or operation of each experimental facility.  ;

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