ML20113H890
| ML20113H890 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 07/29/1992 |
| From: | ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE |
| To: | |
| Shared Package | |
| ML20113H886 | List: |
| References | |
| NUDOCS 9208060112 | |
| Download: ML20113H890 (8) | |
Text
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l 6.0 ADMINISTRATIVE CONTROLS bgc !
6.1 Organization 30 f i
, 6.1.1 Structure 30 i 6.1.2 Responsibility 31 i j 6.1.3 Staffing 31 -
6.1.3.1 Selection of Pers6nnel 31 6.1.3.2 Operations 31 l 6.1.4 Training of Personnel 32 [
j! 6.2 Review and Audit The i actor s and Radiation Facility Safety l l Committee (R RFSC) 32 6.2.1 Composition and Qualifications ".
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l 6.2.1.1 Composition 12 1 6.2.1.2 Qualifications 33 l
6.2.2 Function and Authority 33
! 6.2.2.1 Function 33
} 6.2.2.2 Authority 33 l l 6.2.3 . Charter and Rules 33 !
6.13 1 Alternates 33 >
- 6.2.3.2- M eeting Frequency 33 l 6.2.3.3- Ouorum 33 6it.b' Voting Rules 33
- 6.2.5.5 Minutes 34 f 6.2.4 Review Function 34 l 6.2.5 Audit Function 34 l 6.3 Procedures 35 i 6.4 Review and Approval of Expe
- iments 35 p 6.5 Required Actions 36 4
j 6.5.1 Actions To Be Taken in Case of Safety Limit Violation 36 -
l- 6.5.2 Reportable Occurrences 37 l 6.6 Reports 37 l 6.6.1 Operating Reports ~ 37 l 6.7 Records
- -40 6.7.1' RecordsTo Be Retained For A Period of At Least
[ Years or As Required by 10 CFR Regulations _
40
. 6.7.2 Records To Be Retained For At least One 3 ;omplete
! Training Cycle _ .
41 i 6.7.3 Records To Be Retained For The Life of The Facility l l
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i be working, or prevent the inadvertent movement of the core into the lead j shield doors. !
Specification Facility interlocks shall be provided so that
- a. The reactor caanot be operated unless the shield doors within the reactor h pool are either fully opened or fully closed.
- b. The reactor cannot be operated unless the exposure room plug door f adjacent to the reactor core position is fully closed and the lead shield ;
doors are fully closed; or if the lead shield doors are fully opened, both l exposure rooms plug doors must be fully closed. ;
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- c. The lead shield doors cannot be opened to allow movement into the !
exposure rcom projection unless a warning horn has sounded in that l t
exposure room, or unless two licensed operators have visually inspected the room to insure that no personnel remain in the room prior to i securing the plug door. !
i liash l These interlocks prevem the operation and movement of the reactor core into -!
an area until there is assurance that inadvertent exposures will be eliminated. j 3.3 COOLANT SYSTEMS ,
i Applicability
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Es specificat' refers to operation of the reactor with respect to temperature and condition of the pool water, i Objective f
- a. To insure the effectiveness of the resins in the water purification system j
- b. To prevent activated contaminants from becoming a radiological hazard.
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- c. To help preclude corrosion of fuel eladding and other components in the i primary system. i Snecifications !
- a. The reactor shall not be operated above a thermal power of 5 kilowatts when the purification system input water temperature exceeds 60 C.
- b. The reactor shall not be operated if the conductivity of the water is greater than l 6
2 micrombos/cm (or less than 0.5 x 10 ohms cm resistance) at the output of- l' the purification system, averaged over one week.
c.
The reactor shall not be operated if the conductivitg' of the bulk water is greater than 5 micromhos/cm (or less than 0.2 x 10 ohms-cm resistance) j averaged over 1 week.
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. personnel of any existing or impending danger from radiation, to give sufficient time to evacuate the facility and take necessary steps to prevent the spread of radioactivity to the surroundings. The automatic closure of the ;
ventilation system dampers provides reactor room isolation from the outside environment, in the event of airborne rad,oactivity within the reactor room from fission products decay.
3.5.2 EFFLUENTS
ARGON 41 DISCllAllGE LIMIT Anolicability This specification applies to the concentration of argon 41 that may be discharged from the TRIGA reactor facility.
Objective To insure that the health and safety of the public are not endangered by the discharge of argon 41 from the TRIGA reactor facility. !
SEcrifical10A ,
- a. An environmental radiation monitoring program shall be maintained to determine effects of the facility on the environs.
- b. If a dosimeter reading for any designated environmental monitoring station indicates that a probable exposure of 400 millirem above background has been reached during the year as a result of reactor operations, then reactor operations that generate and release to the unrestricted environment measurable quantitles of argon 41 shall be curtt, . ) to 2 megawCt hours per month for the remainder of the calet year.
- c. If a dosimeter reading for any designatede' nvironmental monitoring-station indicates that an exposure of 500 millitem'above background has been reached during the year as a result of reactor operations, reactor operations that generate and release measurable quantities of argon 41 ;
shall be ceased for the remainder of the calendar year.
Ilash Since argon 41 does not represent an uptake or bloaccumulation problem, only the direct exposure modality is pertinent with regard to limiting reactor operations. Since direct plume shine may be more controlling than ,
immersion conditions, cumulative exposure is the more appropriate quantification of this limit than the concentration limit values in_ Appendix B,.
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. l 4.5 11 ADIATION MON 1TOltlNG SYSTEM Annlicability This tpecification applies to surveillance requirements for the area i radiation monitoring equipment and the air particulate monitoring system.
Objective The objective is to assure that the radiation monitoring equipment is operating and to verify the appropriate alarm settings.
Specification .)
The area radiation monitoring system and the air particulate monitoring system shall be channel tested quarterly, but at intervals not to exceed 4 months. They ,
shall be verified to be operable by a channel check daily when the reactor is in -
operation, and shall be calibrated annually, not to exceed 15-months. ;
13 asis Experience has shown that quarterly verification of area radiation monitoring and ,
air monitoring system set points in conjunction with a quarterly channel test is adequate to correct for any variation in the system due to a change of operating characteristics over a long time span. Annual calibration insures that the units are within the specifications demanded by the extent of use.
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- b. Performance, training, and qualifications of the reactor facility operations staff,
- c. Results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems, or methods of operation that affect safety.
- d. Facility emergency plan and implementing procedures,
- c. Facility security plan and implementing procedures.
- f. Any other area of Facility operations considered appropriate by the RRFSC or the Director /ACRRI.
- g. Reactor Facility ALAR A Program. This program may be a section of the total AFRRI program.
6.3 PR OCEDUl!ES-6.3.1 Written instructions for certain activities shall be approved by the Reactor Facility Director and reviewed by the Reactor and Radiation Facility _ Safety Committee (RRFSC). The proccdures shall be adequate to assure safe operation of the reactor, but shall r;ct preclude the use of independent judgment and action as deemed necessary. These activities are as follows:
- a. Conduct ofirradiations and experiments that could affect the operation and safety of the reactor,
- b. Reactor staff training program,
- c. Surveillance, testing. and calibration ofinstruments, components, and systems involving nuclear safety,
- d. Personnel radiation protection consistent with 10 CFR 20.-
- e. Implementation of required plans such as the Security Plan and
-Emergency Plan.
- f. Reactor core loading and unloading.
- g. Checkout startup, standard operatians, and securing the facility.
6.3.2 Although substantive changes to the above procedures shall be made only with approval by the Reactor Facility Director, temporary changes to the .
procedures that do not change their original intent may be made.by the ROS.
All such temporary changes shall be documented and subsequent _ly reviewed and approved by the Reactor-Facility Director.
6.4 REVIEW AND APPROVAL OF EXPERIMENTS 6.4.1 Before issuance of a reactor authorization, new experiments shall be reviewed for radiological safety and approved by the following:
- a. Reactor Facility Director 35
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- b. Safety and llealth Department ;
- c. Reactor and Radiation Facility Safety Committee (RRFSC) ,
6.4.2 Prior to its performance, an experiment shall be included under one of the following types of authorizations:
- a. Soccial Reactor Authorization for new experiments or experiments not l included in a Routine Reactor Authorization. These experiments shall be performed under the direct supervision of the Reactor Facility Director or designee.
- b. Routine Reactor Authorizatlon for experiments safely performed it least once. These experim'..is may be performed at the discretion of the Reactor Facility Director and coordinated with the Safety and licolth ,
Department when appropriate. These authorizations do not require ,
additional RRFSC review. -
- c. Reactor Parameters Authori7ation for routine measurements of reactor parameters, routine core measurements, instrumentation and calibration checks, maintenance, operator training, tours, testing to verify reactor ,
outputs, and other reactor testing procedures. This shall constitute a single authorization. These operation
- may be performed under the authorization of the Reactor Faci' 4 L " uc c: the Reactor Operations Supervisor.
6.4.3 Substantive (reactivity worth more than e. $N 6 emhecs M previously approved experiments shall be made only after uview by the RRFSC and after approval (in writing) by the Reactor Facil ty Director or designated alternate Minor changes that do not significant y alter the experiment (reactivity worth of less than +/ $0.25) may be approved by the ROS.
Approved experiments shall be carried out in accordance with established i procedures.
6.5 REOUIRED ACTIONS 6.5.1 ACTIONS TO H]iTAKEN IN CASE OF SAFETY LIMIT VIOLATION
- a. The reactor shall be shut down immediately, and reactor operation shall not be resumed without authorization by the NRC.
- b. The safety limit violation shall be reported to the Regional L -Administrator of NRC Region I (or designate); the Director, AFRRI; and the RRFSC not later than the next working day.
- c. - A Safety Limit Violation Report shall be prepared. This report shall be reviewed by the RRFSC, and shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation on facility components, structures, or systems, and (3) corrective action taken to prevent or reduce the probability of recurrence. ~!
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- d. The Safety Limit Violation Report shall be submitted to the NRC; the Director, AFRRl; and the RRFSC within 14 days of the violation. .
6.5.2 REPORTABLE OCCURRENCES Reportable occurrences as defined in 1.21 (including causes, actual or probable consequences, corrective actions, and measures to prevent recurrence) shall be reported to the NRC. Supplemental reports may be required to fully describe the final resolution of the occurrence.
- a. promet Notification With Written Followup. The types of esents listed below shall be reported as soon as possible by telephone and confirmed l by telegraph, mailgram, or similar transmission to the Regional !
Administrator of the appropriate NRC Regional Office (or designate) !
no later than the first workday following the event, with a written followup report as per 10 CFR. The report shall include (as a minimum) the circumstances preceding the event, current effects'on the facility, and status of corrective action. The report shall contain as much supplemental material as possible to clarify the situation. ,
(1) Unscheduled conditions arising from natural or man made events that, as a direct result of the event, require operation of safety systems or other protective raeasures required by Technical Specifications.
(2) Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the Safety Analysis Report, or in the bases for the Technical Specifications that have or could have permitted reactor operation with a smaller margin of safety than in the erroneous analysis.-
(3) Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a F manner less conservative than assumed in the accident analyses ,
, in the Safety Analysis Report or Technical Specifications bases, or discovery during plant life of conditions not specifically l- considered in the Safety Analysis Report or Technical l Specifications that require remedial action or corrective i measures to prevent the existence or development of an unsafe condition.
6.6 REPORTS ,
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_In addition to the applicable reporting requirements of Title 10 of the Code of:
l Federal Regulations, the following reports shall be submitted to the Regional Administrator of the appropriate -NRC Regional Office unless otherwise noted.
l 6.6.1 OPER ATING l REPORTS l
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- a. Sintlyp Repo.m A summary report of planned startup and power r escalation testing shall be submitted following (1) receipt of an operating l l license; (2) amendment of the license involving a planned increase in
[ power level; (3) installation of fuel that has a different design; and (4) modifications that may have significantly altered the nuclear, thermal, or i hydraulic performance of the reactor. The report shall address each of the tests identified in the Safety Analysis Report and shall, in general, ,
include a description of the measured values of the operating conditions or characteristics obtained during the test progra'n and a comparison of -
these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be '
described. Any additional specific details required in license conditions based on other commitments shall be included in this report. Startup Reports shall be submitted within (1) 90 days following completion of i the startup test program, (2) 90 days following resumption or _
commencement of power operation, or (3) 9 mor.ths following initial >
criticality, whichever is earliest.-If the Startup Report does not cover all-three events (i.e., initial criticality, completion of startup test program, and resumption or . commencement of power operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.
- b. Annual Operating Report: Routine operating reports covering the !
operation of the unit during previous calendar year si'all be submitted prior to March 31 of each year, covering the previous calendar year's ,
operation. The Annual Operating Report shall provide _a comprehensive summary of the operating experience having safety significance during the year, even though some repetition of previously reported information may be involved. References in the annual operating report -
to previously submitted reports shall be clear.
Each annual operating report shallinclude (1) A brief narrative summary of (a) Changes in facility design, performance characteristics, and operating. procedures related to reactor safety, that.
occurred during the reporting period
-(b) Results of surveillance test and inspections ;
(2) A tabulation showing th energy generated by the reactor on a _- :
monthly basis, the cumulative total energy since initial criticality, !
and the number of pulser greater than $2.00 (3) List of the unscheduled shutdowns, including the reasons and the corrective action taken, if applicable 38.
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