ML20112E626
| ML20112E626 | |
| Person / Time | |
|---|---|
| Site: | 05000124 |
| Issue date: | 01/10/1985 |
| From: | VIRGINIA POLYTECHNIC INSTITUTE & STATE UNIV., BLACKSB |
| To: | |
| Shared Package | |
| ML20112E620 | List: |
| References | |
| NUDOCS 8501150209 | |
| Download: ML20112E626 (11) | |
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I-m j 16.1 Definitions 16.1.1 Ahngtmal Qqqutgagg An: abnormal occurence is any one of the following:
A. An , observed inadequacy in the implementation of admidistrative or procedural controls, such that the inadequacy causes or could cause an unsafe condition with regard to reactor radiological practices.
B. A malfunction of the instrumentation such that a release of radioactive material could occur or a release could occur without being detected.
C. A release of fission fragments from one or more of the reactor fuel elements of a magnitude to indicate a failure of the fuel element cladding.
D. An accidental or unanticipated release of radioactivity to the environment in excess of the limits specified in 10-CFR, Part.20.
16.1.2 ChaQOgl The combination of. sensor, lines, amplifiers, and output devices which are connected for the purpose of measuring the value of a' parameter.
16.1.3 Gbagogi Galib tgti 90 The adjustment of the channel such that it's output responds within acceptable range and accuracy to known values of the parameter which the. reactor measures.
16.1.4 Gbagagl gegrgbility Gbggk ,
Qualitative verification of acceptable performance by observation of channel behavior.
16.1.5 GbEDDgl Tggt The introduction of a signal into the channel to verify that it is operable.
-16.1.6 Qcaf.i ogmRD1 A closure of the reactor room cell (room 10) which controls the movement of air into and out of the cell through a controlled path.
r-8501150209 850110 DR ADOCK 05000 2 1
16.1.7 dggsytgd Valug
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- The value of a parameter as it appears on the output nf the channel.
16.1.8 gggtablg A system or component which is capable of performing it's inten'ded function in it's normal manner.
16.1.9 gestating A system or component which is performing it's intended function in it's normal manner.
16.1.10 Bgagtgt Qigabled The reactor is considered disabled whenever:
A. The means of placing and maintaining moderator in the core area is removed and, B. The control rod drive mechanisms are physically disconnected from the control rods in the core and, C. All control rods are fully inserted and, D. The fuel is not in the reactor core.
16.1.11 Ggattg1 Bgd A device fabricated from a neutron absorbing material which is used to control the rate at which fissionable material in reactor fuel reacts. In the present case, the control rods will remain fully inserted in order to assure that the reactor fuel would remain subtritical, even if the fuel were loaded into the core.
16.1.12 Ebg11 2 Ebgylda gt day The word "shall" is used to denote a mandatory or required action or condition; the word "should" a recommended or
-desirable option: and the word "may" a permissible or discretionary course, without bias.
16.2 LimillD9 C90diti903 f9C tbR E955RSalGQ 90iY bier 0se 16.2.1 Rgagtgt Eggi At no time will the fuel be placed in the reactor core assembly.
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The control rods will be fully inserted and uncoupled from the control rod drive mechanisms except at such times when tests are being performed on the control systems.
16.2.3 Ques Malyg The ~ dump valve shall be disabled in the full open condition except at such times when tests are being performed on the control systems.
16.2.4 Ggafingsgat A. Ngtmal Cggfingegnt Operations that require normal confinement are:
- 1. Irradiated fuel is being handled.
- 2. Other operations in which irradiated or contaminated equipment or materials are being handled.
B. G9Bdit190s 19 ochinxe Netmal Geofinement The existing conditions necessary to achieve normal confinement are:-
- 1. All reactor room accesses are maintained closed and locked except as necessary for controlled personnel movements.
- 2. The reactor room ventilation is operating and maintaining a negative pressure within room 10 with respect to the surrounding areas. The need for an operating ventilation system will be evaluated, after the fuel has been removed according to provisions of Section 16.7.2.B.
- c. Emeteensx Geofinement Emergency confinement shall require as a minimum:
-1. The reactor room shall be evacuated and all means of access closed and locked.
- 2. Robeson Hall in which the reactor is located shall be evacuated and reentry prohibited, except for emergency response personnel, until such t i n.e as the emergency condition is cleared.
- 3. The ventilation system for the reactor cell will be turned'off.
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1 16.3- Emgtggncy Power !
i A backup emergency power supply shall be available to provide uninterrupted power to such instruments as will be maintained in an operating condition during the possession only status.
16.3.1 Cgmegggots The emergency power supply consists of a converter unit, a battery bank, an inverter, and connections to the instrumentation.
16.3.2 Saggifigatigog The battery bank shall be capable of delivering a nominal 48 VDC to the inverter unit for at least 15 minutes under a full load and the inverter shall be cabable of delivering a single phase, nominal 220 VAC output.
16.4 Badial190 d90119C10Q While the reactor fuel remains at the facility, the fixed radiation monitoring system shall remain functional and sufficient portable radiation survey instruments shall be maintained at the facility to permit monitoring of personnel and the facility to assure safety of reactor personnel and the public. After the fuel is removed, sufficient components of the fixed system will remain functional for a period of six months to permit demonstration that no radioactive materials or effluents are escaping from the
-facility, or that radiation conditions within the facility do not cause the requirements of10 CFR Part 20 to be exceeded. After_six months if the data. support the premise that no radioactive material has escaped the facility during the period nor is likely to do so in the future, a formal request will be made to turn off the fixed system.
Continued demonstration of the absence of escaping radioactive material will be made by quarterly swipe and area surveys at the points of egress from the reactor room.
16.4.1 Eixgd Badiatigo dggitgt i ng Systgm The fixed system shall consist of the following:
A. A G-M type detector with proportional compensation on the West wall of the reactor room. This detector -has a range of 0.1 to 10,000 mrem per hour. The normal setpoint will be 15 mrem per hour or less, except during transfer of irradiated fuel when it may be increased to avoid initiation of a building alarm due to momentary (less than one minute) excursions at that time. An individual will be at the console observing the meter to insure that the levels do not exceed safe levels. When tripped, the monitor initiates the 4
n building evacuation alarm and deenergizes the reactor room ventilation.
B. A G-M type detector with proportional compensation on the East wall of the reactor room. This detector has a range of .1 to 10,000 mrem per hour. The normal setpoint will be 5 mrem or less. When tripped, the monitor initiates an oVer tolerance area alarm.
C. A G-M type detector with proportional compensation is located within the reactor room vent exhaust stack as the stack passes through the library on the 3rd floor of Robeson Hall. The detector has a range of 0.1 to 10,000 mrem per hour. The normal alarm setpoint is 15 mrem or less. When tripped, the monitor initiates the building evacuation alarm and deenergizes the reactor room ventilation.
16.4.2 Pgttable Radiatige Mggitgts Portable radiation monitoring equipment shall be maintained at the reactor facility during the period of preparation for
" Possession Only Status" and thereafter at the Radiation Safety Office, a division of Safety and Health Programs.
This instrumentation shall consist of:
A. -A beta-gamma instrument capable of measuring dose rates of 0.1 to 20,000 mrem per hour.
B. A neutron instrument capable of monitoring dose rates of 0.1 to 10,000 mrem per hour.
C. A portable air sampler for collecting airborne activity.
Dy A G-M type "frisker" or equivalent for personnel and equipment surveys and for determining air-borne particulate activity levels.
E. An Eberline Model PAC-4G low level alpha counter.
16.5 Byilding Eyagygtign System-A building evacuation system for Robeson Hall shall be maintained in an operable condition while the reactor fuel remains at the facility and for a period of at least six months thereafter. At the end of the interval a formal request will be made to deactivate the system based on submission of supporting data that no accidental release of radiation due to the presence of the defuelled facility is likely to occur. The building shall be evacuated whenever any one of the following three conditions exist:
p A. The building monitor on the West wall of the reactor room exceeds it's set point (normally 15 mrem per hour
! except as noted in section 16.4.1.A).
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B. .The ventilation stack monitor exceeds it's setpoint of 15 mrem per hour.
C. A condition exists which, in the opinion of a responsible person, e.g. a member of the reactor staff, a radi ati on safety person, or a member of the Reactor Safety Committee, would pose a danger to personnel within the reactor facility or members of the general public, would result in a manual initiation of the evacuation alarm.
If maintenance is required on either of the two devices which would initiate an automatic building evacuation alarm, the facility would be secured and all operations other than those involved in the maintenance would cease.
During normal working hours, surveys using portable instrumentation would be performed at the begining and end of the work day.
16.5.1 Octigns When .a building alarm occurs, the following actions will take place:
A. Facility operations will immediately cease; all personnel within the reactor laboratory area will immediately evacuate, and assist in the evacuation of personnel from the remainder of Robeson Hall. The doors to the facility shall be locked, and the ventilation system will automatically shut down. The VPILSU Police will be notified and will respond bringing an emergency kit and will prevent anyone from rentering the building. If the alarm occurs when no one is present within the reactor facility, the Police will notify reactor staff (until the fuel is removed from the facility and the Director, Safety and Health Programs thereafter) and radiation safety personnel from .an emergency call list maintained by the police.
. Rentry of the facility will be only by a joint decision of the senior reactor staff member and the radiation safety person pr esent. Due care will be taken to insure the protection of all individuals. Only after it is proven that it is safe to do so will occupancy of any portion of Robeson Hall be permitted.
16.6 Euel Handling It is not intended that the fuel be moved from the fuel storage pits, where it is currently located, until such time that removal of the fuel from the facility shall take
' place. However, if it is necessary to move one or more elements for inspections, auditing or safety reasons, the fuel shall be handled under the f ollowing conditions:
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!' _A. All movement of fuel will be made by a team of at least fthree persons; a react'or staff member, a health physicist, Land an assistant. When the fuel is being transferred to a Ri commercial firm for removal from the site, the commercial
$7 firm shall have the responsibility for handling the fuel.
' , fB. Radiation monitoring will be done using the portable e and ' fixed radiation monitoring equipment described in
'Section 16.4.
C. All fuel element movhments will be logged.
D. A fuel transfer cask will be used for movement of all
" hot " fuel. Acceptably " cold" fuel as determined by
. -radiation surveys and specifically permitted by the 7'"
Radiation Safety Officer may be moved without using the fuel transfer cask.
- x E. A maximum of one " hot" element shall be allowed in
- y. transition at'any-one time.
9 16.7 EWtvtillADEk BR991CRERDt1 Under . the possessi on only status, only a limited amount of checking of the. instrumentation will be required. The intervals will range from annual, not to exceed 15 months, semiannual, not'to exc'eed 7 months, and quarterly, not to exceed 4' months. Six months after the fuel has been y removed, . tests of specific systems will be discontinued (after approval has been obtained from .the Radioisotope Committee).
The following systems will be inspected and/or functionally checked as noted at the prescribed intervals.
16.7.1 BRagtgt Bggs The general conditions' within the reactor room will be
.g. inspected quarterly with a walkthrough type inspection for f_fFf9' obvious- damage to maintain the integrity of the reactor
~ * - systems.
A 16.712 'BRestet B99m YRotilat190 Untilasuch time as the fuel is disposed of, the ventilation-
. g.) isystem will be checked for the following items:
bg A. The ventilation -system.shall be checked quarterly to
.l 7,p assure that a negative pressure is being maintained in the reactor cell.
JB, The capability of the systems to automatically turn off
' the - ventilation system will be performed semi-annually.
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a After the fuel has been removed from the facility, the ducts 1eading to the ventilation stack and the upper end of the stack shall be covered and the ventilation fans and motors protected from the environment. If found to be necessary to prevent radioactive material leaving the facility, according to the swipe and area surveys specified in Section 16.4, the ventilation system will be temporarily reactivated until the dispersion problem is resolved.
16.7.3 Esgtggacy Egwat A functional transfer and load test shall be done quarterly or following any repairs or modification. A commercial power outage during normal working hours, with proper operation for 15 minutes or longer, will count as a successful test.
16.7.4 Building Eygguatige Systgm Building evacuation drills shall be performed semi-annually until such time as the fuel has been removed, at which time the-frequency will be changed to annually.
16.7.5 Badiati90 090it9CiD9 SYEARES The reactor Area, Building and Stack monitors shall be calibrated semi-annually until such time that permission is secured to turn these systems off.
16.8 Dgsign fggtutgg The following features are described in order that changes shall not be made while under the " Possession Only Status".
16.8.1 Sitg The Virginia Tech Argonaut Reactor is located in Robeson Hall of VPI&SU. Robeson Hall is located in the northwest corner of the main campus. Buildings located within a 500 foot radius include Davidson, Williams, Derring, Cowgill, Burruss and Pamplin. Additions are planned to Robeson and Pamplin within the next year.
16.8.2 Bgagigt Eggility The area to be maintained secure under the " Possession Only Status" will be room 10, and portions of room 106. Other areas currently within the restricted area may be made available for other use by constructing walls or by providing alternate access after the fuel has been removed.
Until that-time, rooms 106, 6, 8 and 10 will be included within~ the. area defined as the reactor facility. The building roof has been part of the restricted area. Since the reactor will not be operating during the " Possession 8
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Only Status" the roof area will no longer be part of the restricted area.
16.8.3 Begctet Ggglagt The water in the dump tank will be removed and the water supply to the reactor coolant system shall be disconnected so t' hat it will be impossible to fill the reactor coolant system.
16.8.4 ghigld Tang The shield tank shall be emptied and the tank will remain empty.
16.8.5 Eugl Stgtagg Pits While under " Possession Only Status", the only places where the fuel may be stored, pending it's removal from the facility, are the East and West Fuel storage pits. Only a single element or the equivalent number of plates may be stored in each storage hole in these pits.
16.9 8dminisitatiyg Cgattgis The overall responsibility for the reactor while in
" Possession Only Status" has been assigned to the Vice President for Administration and Operations. He has assigned the rsponsibility for administering the facility to the Director of Safety and Health Programs. The Reactor Safety Committee has the responsibility for monitoring reactor activities to assure compliance with NRC regulations, provisions of the terms of the reactor license, and these Technical Specifications. Operations of the facility while fuel is still present is under a Reactor Supervisor. A half-time senior operator assists the Reactor Supervisor. A Radiation Safety specialist is assigned to
, the reactor . When the fuel is removed from the facility, the reactor supervisor and senior operator positions will be transferred to other areas within the- University. The organizational chart in section 16.9.4 reflects the organization which will exist as long as the fuel is present. When the fuel is removed, the Reactor Safety Committee will be replaced by the Radioisotope Committee on this chart and-the Reactor Supervisor and Reactor staff will be ~ deleted.
16.9.1 Bggctgt Safgty Ggmmittgg During the peri od while the f uel remains at the University, the Reactor Safety Committee. will remain a separate subcommittee of the University Radiation Safety Committee.
The Reactor Safety Committee will be chaired by an administrator familiar with radiation and appointed by the 9
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, Vice President for Administration and Operations. There will be at least 5 other members of whom one will be the Reactor Supervisor, another the Director of Safety and Health Programs, and a third the Reactor Safety Officer.
The others will be chosen according to their backgrouna in radiation applications, engineering or other relevant disciplines.
Once- the fuel has been removed from the facility, the Reactor Safety Committee will cease to exist as a separate committee and the oversight function will be assumed by the Radioisotope Committee, the other subcommittee of the Radiation Safety Committee. The membership of this committee is defined under the terms of the University's Broad License for Use of Radioisotopes.
In each- case, a quorum is defined as half the total membership plus one. Decisions of the committees require a majority of the members present and voting.
16.9.1.1 MggtiD99 The- Reactor Safety Committee or it's successor shall meet quarterly or as needed, or by request of any Committee member.
16.9.2 Bgggtts The reactor staff, when one exists, and the Reactor Safety Officer shall make a report to the Reactor Safety Committee or it's successor, at each quarterly meeting, of reactor activities, radiation exposures, and transfers and discharges of radioactive materials during the preceeding quarter..
16.9.3 Bgegtds l Records shal1~be maintained of all information pertinent to lthe facility under " Possession Only' Status" to allow others
-at a later time to determine the function and condition of all_ the reactor systems at such time as the facility is finally decommissioned or a decision is made to seek
. operational status.
16.9.4 Ot gggigatigggi Ghatt (On next page) 10
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7 08Get!IIGIlRN8L Gt!8BI I I I President I I - I L
IVice President i I for !
IAdministration i I & Operations !
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! Reactor Safety i I Director, Safety I i Committee i ._ _I & Health Programst
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