ML20112E385

Proposed Tech Specs,Replacing Term AO W/Term RO & Including New Info Organization for Mgt & Operation of Reactor

ML20112E385
Person / Time
Site:	Neely Research Reactor
Issue date:	12/18/1984
From:	Neely Research Reactor, ATLANTA, GA
To:
Shared Package
ML20112E380	List: ML20112E379 ML20112E385
References
NUDOCS 8501150123
Download: ML20112E385 (10)

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Table of Contents Page 1.0 Definitions ......................................... 1 2.0 Safety Limits and Limiting Safety System Settings . .. 6 2.1 Safety Limits .................................. 6 2.2 Limiting Safe ty Sys tem Settings . . . . . . . . . . . . . . . . 8 3.0 Limiting Conditions for Operation ................... 9 3.l~ Reactivity Limits .............................. 9 3.2 Reactor Safety System .......................... 10 3.3 Containment Building .......................... 14 3.4 Limitations of Experiments ..................... 17 3.5 Radioactive Effluents .......................... 20 3.6 Primary Coola n t Sy s tem . . . . . . . . . . . . . . . . . . . . . . . . . 23 3.7 Emergency Cooling System ....................... 24 3.8 Fuel Handling and' Storage ...................... 26 4.0 '

Surveillance Requireronts .......................... 28 4.1 Reactivity Limits .............................. 28 14.2 Re'actorcSafety System .......................... 29

'4.3 Con tai nmen t B uilding . . . . . . . . . . . . . . . . . . . . . . . . . . 33 4.4 P r ima ry Coo la n t S y s t em . . . . . . . . . . . . . . . . . . . . . . . . . 34

4. 5 Emergency Cooling Sys tem . . . . . . . . . . . . . . . . . . . . . . . 35 5.0 Design Features .................................... 37 5 .~ 1 Site Description .............................. 37 5.2- Fuel Elements .................................. 37 6 . 10 Admi ni s tra t ive Co n tr o l s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38 6.1 Organization ................................... 38 6.2 Nuclear Saf eguards Committee . . . . . . . . . . . . . . . . . . 40 6.3- Administrative Controls of . Experiments . . . . . . . . . 41

-- 6.4 Procedures ..................................... 42 6.5 Operating Records .............................. 43 6.6 -Action to be Taken in the' Event of a Reportable Occurrence ...'.................................. 44 ,

6.7 ' Reporting Requirements.......................... 44 I

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, 1.10 Heactor Secured - Reactor secured is defined as follows:

a. The reactor is shutdown as detined in Detinition 1.9 b.- Subcriticality of the cold xenon free core by at i least one dollar has been confirmed.

c. tJo operation is in progress which involves uoving fuel elements within the reactor vessel, the inser-tion or removal of experiments from the core, or control rod maintenance.

1.11. True value - The true value of a process variable,is its actual value at any instant.

1.12 Measured value - The measured value of a process variable is the value of the variable as it appears on the output of a measuring channel.

1.13 Measuring Channel - A measuring channel is the combina-ticn of sensor, lines, amplifiers, and output devices which are connected for the purpose of measuring the value of a process variable.

1.14 Reportable Occurrence - A reportable occurence is any of

• the following:

a. A safety system setting less conservative than the limiting setting established in the Technical Specifications.

b. Operation in violation of a limiting condition for operation established in the Technical Specifica-tions.

c. A safety system component malfuliction or other component or system malfunction which could, or threatens to, render the safety system or the engineered safeguard systems incapable of perform-ing their intended safety functions.

d. Release of fission products from a failed fuel element.

e. An uncontrolled or unplanned release of radioactive material from the restricted area of the facility.

f. An uncontrolled or unplanned release of radioactive material which results in concentrations of radio-active materials within the' restricted area in excess of the limits specified in Appendix B, Table 1 of 10'CFR 20. .

9 An uncontrolled or unanticipated change in reactiv-ity in excess of 0.005 ok/k.

h. An observed ' inadequacy in the implementation of administrative or procedural controls such that-the-inadequacy causes or threatens to cause the exist-ence or development of an unsafe condition in connection with the operation of the plant.

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. PRESIDENT OF GEORGIA TECH 1r VICE PRESIDENT FOR RESEARCH

" 1r 1r RADIOLOGICAL NUCLEAR SAFETY  : DIRECTOR  : SAFEGUARDS OFFICER NUCLEAR RESEARCH CENTER COMMITTEE ir REACTOR SUPERVISOR gr REACTOR ENGINEER 1P

'l REACTOR

,i. OPERATING

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FIGURE 6.1 Georgia Tech Organization for ll ~ Management and Operation of GTRR 3

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e. An operator or senior operator licensed pursuant to q 10 CFR 55 shall be present at the controla unless

. the reactor is shutdown as defined in these specifi-cations, l

j- 6.2 NUCLEAR SAFEGUARDS COMMITTEE

a. A Nuclear Safeguards Committee shall be established by the President of the Institute and shall be

responsible for maintainin:j health and safety stan-

! dards associated with operation of the reactor and

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lts associated facilities.

b. The Nuclear Safeguards Committee shall be composed of five or more senior technical personnel who col-lectively provide experience in reactor engineering, reactor operations, chemistry and radiochemistry, instrumentation and control systems, radiological safety, and mechanical and eiactrical systems. The

,, Reactor Supervisor and Radiological Safety Officer

! shall be ex officio members of the Committee. No j . more than a minority of the Committee members shall

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i be from the GTRR staff.

c. The Committee shall meet quarterly and as circum-

- stances warrant. Written records of the proceed-

,ings, including any recommendations or occurrences, i shall be distributed to all Committee members and the President, Georgia Tech.

d. The quorum shall consist of not less than a majority of the full Committee and shall include the chairman

j. or- his designated alternate.

i The Nuclear Safeguards Committca shall:

e.

(1) Review and approve proposed experiments and tests F utilizing the reactor facility which are signifi-cantly different'from tests and experiments previously performed at the GTRR.

(2) Review reportable occurrences.

(3) Review and approve proposed operating procedures and proposed changes to operating procedures which change the original intent of the operating proce-dure in a non-conservative manner.

(4) Review and approve proposed changes to the Technical .

Specifications and proposed amendments to facility license.and review proposed changes to the facility made pursuant to'10 CFR 50.59(c).

(5) Au'dit reactor operations and reactor operational re-cords for compliance with internal rules, proce-dures, and. regulations and with licensed provisions including Technical Specifications.

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(G) Audit existing operating procedures for adequacy and to assure that they achieve their intended purpose in light of any changes since their imple-mentation.

(7) 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 CF EXPERIMENTS

a. Evaluation by Safety Review Group (1) No experiment shall be performed without review and approval by the Nuclear Safeguards Coumittee.

Repetitive experiments with common safety considera-tions.may be reviewed and approved as a class.

(2) Criteria'for review of an experiment or clata of experiments shall include (a) applicable regulatory positions including those in 10 CFR Part 20 and the

, technical specifications ano (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 considera-tions, as well as those which govern the quality assurance program required under 50.34.

(3) Records shall be kept of the Nuclohr Safeguards Committee's review and authorization for each experiment or class of experiments.

b. Cperations Approval-

-(l) Every experiment shall have the prior explicit

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written approval of the Licensed Eenior Operator in charge of reactor operations. _

(2) Every person who is-to carry out an experiment shall e be certified by the Licensed Senior Operator'in charge of reactor operations as to tne sufficiency of his knowledge'and training in procedures. required for the' safe conduct of the experiment.

c. Procedures for Active Conduct of Experiments 4_.

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(1) Detailed' written procedures shall be provided for T the use or operation of.each experimental facility.

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p (3) Actions to be taken to correct specifle and foreseen b potential malfunctions of systems or components, in-cluding responses to alarms, suspected prima.y l'

system leaks and abnormal reactivity changes.

(4) Emergency conditions involving potential or actual release ot radioactivity.

I (5) Preventive or corrective maintenance operations

]!- which could have an effect on the sately of the reactor.

! (6) Radiation and radioactive contamination control.

l (7) Surveillance and testing requirements.

} (8) A site emergency plan delineating the action to be taken in the event of emergency conditions and F~

accidents which result in or could lead to the

. release of radioactive materialb in quant'ities that

.could endanger the health and safety of employees or the public. Periodic evacuation drills for facility personnel shall be conducted to assure that facility personnel are familiar with the emergency plan.

(9) Physical security of the facility and associated

. special nuclear material.

~6.5 OPERATING RECORDS a.-- The following records and logs shall be prepared and retai'ned at the facility for at least five years:

[_, (1) Normal facility operation and maintenance.

(2) Reportable occurrences.

(3) Tests, checks, and measurements documenting com-pliance with surveillance requirements.

! -(4) Records of experiments performed.

! .b. The following records and logs shall be prepared and

! retained at the facility for the life of the facility:

i J' (1) Gaseous and liquid waste released to the environs.

(2) Offsite environmental monitoring surveys.

(3)- Radiation exposures for all GTRR personnel.

(4) Fuel inventories and transfers.

(5)' Facility _ radiation and contamination surveys.

(6)' -Updated, corrected, and as-built facility drawings. .

(7) Minutes'of Nuclear-Safeguards Committee meetings.

(8) Records of radioactive shipments.

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Or i-l G.6 ACTION TO BE TAKEN IN Tile EVENT OF A REPORTABLE OCCultRENCE

In the event of a reportable occurrence, as defined in i these Technical Specifications, the following action shall be taken

a. All reportable occurrences shall be promptly repor-tcd to the Reactor Supervisor or his designated alternate.

i b. All reportable occurrences shall be reported to the Nuclear Regulatory Commission in accordance with Section 6.7 of these specifications.

c. All reportable occurrences shall be reviewed by the Nuclear Safeguards Committee.

6.7 REPORTING REQUIREMENTS The following information shall be submitted to the U.S.N.R.C. in addition to the reports required by Title

• 10,-Code of Federal Regulations.

a. Annual Operating Reports A report covering the previous year shall be sub-mitted to the office of the Regional Administrator, Region II, with a copy to the Director, Office of Nuclear' Reactor Regulation, by March 1 of each year.

It shall include the following:

(1) Operations Summary A summary of operating experience occurring during the reporting period including:

(a) changes"in facility design,.

(b) performance characteristics (e.g.,

equipment and fuel performance),

(c) changes in operating. procedures which e relate to the safety of~ facility operations, (d) results of surveillance tests and inspec- .

tions required by these technical specifi-cations, (e) a brief summary of these changes, tests, and experiments which required authoriza-tion from the Commission pursuant to 10 CFR 50.59 (a) , and

-(f) changes in the plant operating staff serv-

- ing in the following positions:

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1. Director, Nuclear Research Center II ' .2. Reactor Supervisor

3. Reactor Engineer w.i.

4. Radiological Satety Officer

5. Nuclear Safeguards Committee members -

(2)' Power Generation A tabulation of the thermal output of the facility during the reporting period, t

(3) ' Shutdowns A listing of unscheduled shutdowns which have oc-curred during the reporting period, tabulated ac-cording to cause, and a brief discussion of the preventive actions taken to prevent recurrence.

(4) Maintenance A discussion of corrective maintenance (excluding preventative maintenance) performed during the 're-porting period on safety related systems and components.

(5) Changes, Tests and Experiments t

A brief description and a summary of the safety -

evaluation for those changes, tests, and experi-ments which were carried out without prior Commission approval, pursuant to~the requirements of 10 CFR Part.50.59(b).

(6). Radioactive Effluent Releases ,

'A. statement'of the quantities of radioactive effluents released from the plant, with. data summarized following the general format of USNRC

• Regulatory Guide 1.21:

(a)- Gaseous Effluents

1. Gross Radioactivity Releases

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a. Total gross rad'ioactivity (in curie's),

primarily noble and activation gases.

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program, indicate the likelihood of public intakes in excess of 1% of those that could result froa continuous exposure to the concentration values listed in Appendix B, Table II, 10 CPR Part 20, estimates of the likely resultant exposure to individuals and to population groups and assumptions upon which estimates are based shall be provided.

(8)- Occupational Personnel Radiation Exposure A summary of radiation exposures greater than 500 mrem (50 mRea for persons under 18 years of age) received during the reporting period by facility personnel (f aculty, students, or experiments) .

b. Non-Houtine Reports (1) Reportable Occurrence Reports Notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the Office of the Regional Administrator,. Region II, with a copy to the Director, Office of Nuclear Reactor Regulations

'followed by a written report within 10 days to the Office of the Regional Administrator, Region II, with a copy to'the Director, Office of Nuclear Reactor Regulations in the event of the reportable occurrences as defined in Section 1.0. The written report on these reportable occurrences, and to the extent possibic, the preliminary telephone and telegraph notification shall:

(a) describe, analyze, and evaluate safety impli-

"' Cations,-

(b) outline ttur measures taken to assure that the cause of the condition is determined, (c)' -indicate the corrective action-(including any changes made to the procedures and to the quality assurance program) taken to prevent

.[ repetition of the occurrence and of similar .

L , occurrences involving similar components or I'

systems, and

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(d) evaluate the safety implications of the inci-dent in light of the-cumulative experience obtained from the record of previous failures F and malfunctions of similar systems and com-I ponents.

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(2) Unusual Events i A written report shall be totwarded within 30 dayu 3

to the OfLice of the Regional Administrator, Region l II, with a copy to the Director, Ottice of IJuclear Reactor Regulations in the event of:

(a) Discovery ot any substantial errors in the transient or accident analyses or in the i methods used for such analysca, as described I in the Safety Analysis Report or in the bases for the Technical Specifications.

(b) Discovery of any substantial variance from per-formance specifications contained in the

.f Technical Specifications or in the safety 1 Analysis Report.

(c) Discovery of any condition involving a possible single failure which, for a system designed against assumed single failures, could result in a loss of the capability of the system to

, perform its safety function.

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