ML20066C179
| ML20066C179 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 09/30/1982 |
| From: | ARMED FORCES RADIOBIOLOGICAL RESEARCH INSTITUTE |
| To: | |
| Shared Package | |
| ML20066C127 | List: |
| References | |
| AFRRI-3020.2G, NUDOCS 8211090373 | |
| Download: ML20066C179 (52) | |
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DEFENSE NUCLEAR AGENCY
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ARMED FORCES RADIO 810 LOGY RESEARCH INSTITUTE SETHESDA, MARYLAND 20814 AFRRI 3020.2G RSD:JAS:hs 30 September 1982 AFRRIINSTRUCTION 3020.2G Subj: AFRRI Emergency Evacuation and Fire Plan Ref: (a) AFRRI-NNMC Interservice Support (Host-Tenant) Agreement (b) AFRRIInstruction 6310.1A (c) NNMC Instruction 11320.1E, Fire Bill (d) AFRRI Reactor Facility Emergency Plan (upon U. S. Nuclear Regulatory Commission (NRC) approval]
Enc 1: (1) Actions and Responsibilities of All AFRRI Personnel for Implementing the AFRRI Emergency Evacuation and Fire Plan (2) Actions and Responsibilities of AFRRI Security Watch Personnel for the AFRRI Emergency Evacuation and Fire Plan (3) Emergency Protection or Destruction of Classified Material; Security of the Armed Forces Radiobiology Research Institute (4) AFRRI Emergency Organization: Assignments and Responsibilities (5) Procedure for AFRRI Evacuation Search Teams (6) Criteria for Notification of Outside Agencies (7) Sources of Additional Help (8) AFRRI Reactor Facility Emergency Plan (upon USNRC Approval)
- 1. Purpose. To establish an effective emergency evacuation and fire plan for AFRRI.
- 2. Cancellation. AFRRI Instruction 3020.2F, AFRRI Emergency Evacuation and Fire Plan, dated 16 January 1978, is hereby cancelled.
- 3. Scope. This Instruction provides guidance for all AFRRI personnel on responding to l
any hazardous condition at the AFRRI that requires emergency actione. The NNMC l
(National Naval Medical Center) Disaster Preparedness Plan will take precedence over I
this Instruction in accordance with Reference (a).
The AFRRI Reactor Facility Emergency Plan (upon its approval by NRC) will likewise take precedence over this l
Instruction in accordance with Reference (d).
- 4. Evacuation Alarm. Full-scale evacuation of the AFRRI is initiated by sounding the fire bell for all emergency conditions.
I S. Primarv Action and Resoonsibilities
- a. All AFRRI personnel.
The required duties are listed in Enclosure 1 of this Instruction. A copy of this Instruction with pertinent enclosures shall be provided to all AFRRI personnel and shall be issued to each new employee by the Head, Occupational Safety and Health Office during the check-in procedure.
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AFRRI 3020.2G 30 September 1982
- b. Security Watch Personnel. Duties are listed in Enclosure 2, which will be posted at the AFRRI Reception Desk. Security Watch personnel will be required to be aware of its content. The AFRRI Administrative Officer is responsible for seeing that all watch-standers receive a briefing of this material at least, semiannually.
- c. AFRRI Emergency Personnel (1) The AFRRI Emergency Organization assignments and responsibilities are outlined in Enclosure 4.
The Radiation Safety Department (SAF) is responsible for the periodic training and for ensuring proper assignment of personnel to the AFRRI Emergency Organization. SAF is also responsible for maintaining a current roster of those assigned to the AFRRI Emergency Organization.
(2) Evacuation Search Teams. Duties are outlined in Enclosure 5.
The AFRRI Administrative Officer is responsible for training and assigning personnel to all AFRRI evacuation search teams and for maintaining a current roster of these teams.
- 6. Sucolementary Actions and Resoonsibilities Reference (b) outlines the procedures for managing injured and/or contaminated a.
personnel; the Medical Team Leader will implement these procedures.
- b. Three separate AFRRI Fire and Emergency Evacuation Information Guides for use at the Emergency Command Post (ECP), at the Emergency Action Station (EAS), and at the AFRRI Reception Desk will be assembled and maintained by SAF. These guides will be kept in the ECP Emergency Box, in the Front Door Emergency Box, and at the AFRRI Reception Desk. Enclosures 4 and 6 outline the instructions governing the material in these guides.
- c. An AFRRI Emergency Notification Roster shall be maintained by SAF and posted in the OOD/ Security Watch instruction book. All department representatives identified in it shall maintain a list of home telephone numbers for their personnel: this shall oonstitute the AFRRI personnel recall roster.
- d. The precautions and procedures of Reference (c) shall be adhered to with 'he following exceptions:
(1) Emergency telephone number stickers and the employee safety booklet shall be used instead of posting Reference (c).
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AFRR13020.2G 30 September 1982 (2) The investigation and reporting requirements of DNA shall be followed,
- e. The Administrative Officer shall (1) Plan and conduct drills at least twice a year to exercise and test the procedures of this Instruction.
(2) Review and, if necessary, update this Instruction annually, not to exceed 14 months.
FOR THE DIRECTOR:
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R. S. CUNNINGHAM CDR, MSC, USN Administrative Officer DISTRIBUTION: C Plus - 1 cy HQ, DNA 2 cys P AO, DN A 1 cy CO, NNMC 1 cy NNMC Rad Saf Officer 1 cy NNMC Security 1 cy NNMC Fire Dept 1 cy NNMC Emerg Room 1 cy RRFSC, AFRRI 1 cy RXSC, AFRRI IcyJNACC i cy NRC 3
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ACTIONS AND RESPONSIBILITIES OF ALL AFRRI PERSONNEL FOR IMPLEMENTING THE AFRRI EMERGENCY EVACUATION AND FIRE PLAN 1.
During Duty Hours
- a. Upon DISCOVERY of fire, smoke, or other hazardous condition, personnel must (1) PULL the nearest fire alarm.
(2) EVACUATE the Institute immediately.
(3) REPORT as soon as posciible the nature and location of the emergency or hazard to the Emergency Action Station (EAS) Commander located outside the front entrance of AFRRI.
- b. Upon HEARING a fire alarm, regardless of its duration, all personnel must (1) EVACUATE the building immediately by the nearest safe exit.
(2) ASSEMBLE in appropriate muster area (see page 2 of this Enclosure).
(3) MUSTER in an orderly manner with respective Department Chairman /IIead or representative, and comply with his/her verbal orders.
(4) DO NOT INTERFERE with emergency activities or act. independently.
2.
During Nonduty Hours
- a. Sign in and out on the Security Area Register maintained at the AFRRI Reception Desk located at the front entrance of AFRRI on nonduty days and after 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on duty days.
- b. Upon DISCOVERY of fire, smoke, or other hazardous condition, personnel must (1) PULL the nearest fire alarm.
(2) EVACUATE the Institute immediately.
(3) REPORT as soon as possible the nature and location of emergency or hazard to the Security Watch or Duty Officer located at the front entrance of AFRRI.
- c. Upon HEARING a fire alarm, regardless of its duration, all personnel must (1) EVACUATE the building immediately by the nearest safe exit.
(2) ASSEMBLE outside the front entrance of AFRRI with the Security 'Natch or Duty Officer.
(3) DO NOT INTERFERE with emergency activities or act independently.
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ACTIONS AND RESPONSIBILITIES CF AFRRI SECURITY WATCH PERSONNEL FOR THE AFRRI EMERGENCY EVACUATION AND FIRE PLAN The following actions apply to nonduty hours:
1.
Maintain the Security Area Register, which lists on-board personnel.
2.
Upon DISCOVERY or notification of a fire or other hazardous condition, the Security Watch or Duty Officer will do the following:
- a. PULL the nearest fire alarm.
- b. EVACUATE the emergency area immediately.
- c. UNLOCK the AFRRI front entrance (if applicable).
- d. CALL the NNMC Fire Department (dial 147 or 50333).
CALL appropriate personnellisted on the AFRRI Emergency Notification Roster.
e.
- f. ' CHECK radiation monitors in Room 3112 for high radiation indications (i.e.,.,100 mR/hr).
- g. TAKE the Security Area Register (which lists on-board personnel) and remain either at the front entrance or go to a safe area nearby,
- h. MEET and brief responding Fire / Rescue personnel.
- i. ESCORT and provide assistance as necessary to the Fire / Rescue personnel upon entry into AFRRI.
[ NOTE:
If a radiological hazard exists or is suspected, contact Radiation Safety Department (SAF) before permitting entry. ]
3.
Upon HEARING a fire alarm initiated by someone else, Security Watch personnel will follow items 2b through 2i above. In addition, they will:
- a. Obtain information about the emergency from the person who pulled the alar'n.
- b. Relay this information to the Duty Officer and the AFilit! Administrative i
Officer.
- c. Make sure that the person who gave the information is available to assist emergency personnel upon arrival.
4.
Resoonsibility and Authoritv. The Duty Officer is authorized to act on behalf of the Director and Deputy Director in their absence. Therefore. Security Watch personnel l
should use sound judgment; their primary concerns should be for personnel safety anr1 protection of the Institute, in that order. In addition, the Duty Officer is responsible for directing and taking appropriate actions in response to an emergency until properly relieved by arrival on-station of the Emergency Command Post (ECP) Commander.
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EMERGENCY PROTECTION OR DESTRUCTION OF CLASSIFIED MATERIAL; SECURITY OF THE ARMED FORCES RADIOBIOLOGY RESEARCH INSTITUTE Emergency procedures for the protection, removal, or destruction of classified material within the Armed Forces Radiobiology Research Institute (AFRRI) due to natural disaster, civil disturbance, enemy action, entry by unauthorized persons, or evidence of forced entry are as follows:
1.
After Normal Duty Hours
- a. In case of any emergency listed above, the Security Watch will notify the AFRRI Duty Officer, the AFRRI Classified Material Control Officer / Custodian, and the National Naval Medical Center (NNMC) Security as soon as possible. Security Watch personnel will contact the proper persons listed on the DA Form 727 that is on the front of the safe in Room 3112.
NNMC Security will provide a security force to help Security Watch personnel maintain security during disaster control operations, threats, or emergencies, by doing the following:
(1) Establish a perimeter security when directed.
(2) Control entering and exiting emergency vehicles and all other traffic.
(3) Ensure the greatest possible security for vital areas.
(4) Prevent riot, panic, hysteria, and other signs of potential mob action.
(5) Man and secure all entry points against illegal entry into the.NNMC and the AFRRI, as appropriate.
(6) Prevent disorderly movements, or other detrimental activities.
(7) Prevent sabotage, espionage, and looting.
l (8) Help to evacuate damaged areas.
(9) Perform other related tasks as directed.
(10) When directed, dispatch any teams and equipment required for emergency recovery operations.
(11) Coordinate the security operations of the emergency recovery unit with those of AFRRI.
I b.
The Classified Material Control Officer / Custodian or alternate will l
determine the extent of the emergency and thereby establish the procedures for safeguarding classified material.
If an unauthorized person is found in AFRRI after duty hours or if any c.
l evidence of forced entry into AFRRI is noted, the Security Watch will enil the NNTir j
Security for assistance.
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2.
During Normal Duty Hours
- a. The Classified Material Control Officer / Custodian (or in his/her absence, the alternate) will be notified, who will take responsibility for the security or destruction of all classified material within the AFRRI.
- b. If the AFRRI is evacuated, anyone having classified material signed out from the Security NCOIC will return the material to the Security NCOIC at the top of the steps directly in front of AFRRI. The Security NCOIC shall safeguard the material until the emergency is over. Then he/she will either return the material to the person who signed for it or return it to the safe.
AFRRI E31ERGENCY ORGANIZATION: ASSIGNMENTS AND RESPONSIBILITIES 1.
Emergency Command Post (ECP).
Physical Location: Initially, the ECP will be located under the bridge at the foot of the parking lot in front of AFRRI. The ECP may subsequently be moved to the AFRRI library or to another nearby building having adequate communicacions if safety, convenience, or the demar.ds of the emergency warrant such a move.
- a. ECP Commander (1) Succession to Command is as follows:
(a) Director, AFRRI (b) Deputy Director, AFRRI (c) Senior military officer present (2) Physicallocation will be at the ECP.
(3) Resoonsibilities:
The ECP Commander has overall responsibility for the Institute and the safety of personnel on-site during an emergency and during recovery operations; for ensuring that outside agencies are notified as necessary; and for requesting any needed NNMC or off-site emergency support. The ECP Commander will utilize the Emergency Organization Staff, as outlined in this Iristruction. to comply with all responsibilities and duties as stated.
(4) Duties:
(a) Ensure that the ECP Emergency Box in the Directorate Area is carried to the ECP during evacuation.
(b) Receive information about the emergency from the sources shown on the AFRRI Emergency Organization Diagram (see page 15 of this Enclosure).
(c) Ensure that the NNMC Fire Department has been notified. (Telephone numbers are listed in the ECP copy of the AFRRI Fire and Emergency Evacuation Information Guide located in the ECP Emergency Box.)
(d) If applicable, ensure that the NNMC Emergency Room is notified of injured personnel and their status. (Telephone numbers are listed in the ECP copy of the AFRRI Fire and Emergency Evacuation Information Guide located in the ECP Emergency l
l Box.)
(e) Ensure notification of the CO, NNMC: the llQ, DN A; the NRC: and the Joint Nuclear Accident Coordination Center (JNACC) in case of an actual emergencv. m; i
necessary.
(Telephone numbers are listed in the ECP copy of the AFRirl Fire and i
Emergency Evacuation Information Guide located in the ECP Emergency Box.)
(f) Ensure that additional support is summoned if evaluation of the emer-gency shows that more help is needed. (Sources of additional support with telephone 1
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numbers are listed in the ECP copy of the AFRRI Fire and Emergency Evacuation Information Guide located in the ECP Emergency Box.)
(g) Approve information before its release to the news media by the DNA Pubil: Affairs /Information Officer. (News release information directive is found in the ECP copy of the AFRRI Fire and Emergency Evacuation Information Guide located in the ECP Emergency Box.)
(h) Ensure personnel are designated to man the telephone (s) and other emergency communication equipment at the ECP.
(i)
Ensure that the billet for Recorder for the ECP is manned, to log all actions and decisions at the ECP. (Log books and writing instruments are in the ECP Emergency Box.)
(j) If personnel are injured and/or contaminated, direct the Medical Team Leader to provide life-saving actions as needed, and monitor the decontamination of personnel as applicable via the Health Physics personnel. AFRRI Instruction 6310, latest revision, outlines decontamination procedures.
(k) Ensure the billets of Special Advisor on Emergency Conditions, EAS Commander, Search Team Marshal, and Medical Team Leader, are manned as applicable.
(1)
Evaluate and provide final approval authority for all major emergency actions to be implemented at the EAS.
(m) Give orders to secure from the emergency condition and reoccupy the AFRRI when appropriate.
(n) Function as commander fo~r all Emergency Recovery Operations, both immediate and long-term. This includes approval authority for the selection of major recovery alternatives, approval authority for major recovery actions, and authority for sanctioning normalInstitute operational activities to resume.
(o) Final approval authority for any planned personnel exposures in excess of 10 CFR 20 limits. Such decisions should be made only after consultation with the Soecial Advisor on Emergency Conditions.
b.
Recorder for ECP (1) Succession is as follows:
(a) Secretary to Director (b) Secretary to Deputy Director (c) As designated on site by ECP Commander (2) Physical location will be at the ECP.
(3) Resoonsibilities:
The Recorder for the ECP is responsible to the ECP Commander for maintaining a log of all actions and decisions occurring at the ECP and 2
for holding reports for the record and subsequent filing with SAF after appropriate review and action has been taken.
(4) Duties:
(a) Receive and record information and reports from the Search Team Marshal and pass this information on to the ECP Commander.
(b) Maintain a log of all actions and decisions that occur at the ECP.
(c) Maintain a temporary file of reports for the record. These reports will be filed in SAF after they have been reviewed and appropriate action has been taken.
- c. Soecial Advisor on Emergency Conditions (SAOEC)
(1) Succession is as follows:
(a) Head, Radiation Safety Department (b) Acting Head, Radiation Safety Department (c) Most-senior AFRRI Health Physicist on-site (2) Physicallocation will be at the ECP.
(3) Resoonsibilities: The Special Advisor on Emergency Conditions is responsible to the ECP Commander for providing technical advice and interpretation of information on actual or potentially hazardous conditions, either radiological or nonradiological, and overseeing all health physics and radiation safety aspects of the emergency response at the ECP, the AFRRI site, and the Institute boundaries. As Head, SAF will maintain AFRRI files of all alerts and exercises under this Instruction.
(4) Duties:
(a) Establish appropriate radiation-monitoring programs for the AFRRI site boundary, Institute boundary, and unrestricted area as required by the emergency and as directed by the ECP Commander.
(b) Assure that proper notification is made to outside agencies as required, and verify these with the ECP Commander.
(c) Ensure the ECP Commander is provided with a current list of telephone numbers and sources of additional assistance available from outside agencies. (These are listed in the ECP copy of the AFRR1 Fire and Emergency Evacuation Information Guide, in the ECP Emergency Box.)
(d) Assure the NNMC Radiation Safety Officer is notified in case of an actual radiological emergency / hazard.
(e) Decide if the nature of the emergency warrants a beta / gamma survey of the ECP, EAS, and/or Emergency Muster Location (EML), and advise the ECP Commander accordingly.
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4 (f) Provide advice,' assistance, data, and interpretation of data to the ECP Commander, as necessary.
I (g) Provide advise, assistance, and consultation to the ECP Commander for any planned personnel exposures in excess of 10 CFR 20 limits.
- d. MedicalTeam Leader (1) The Director, AFRRI, shall identify two individuals to be assigned as the primary and alternate for this Billet.
(2) Physicallocation will be at the ECP.
(3) Responsibility: The Medical Team Leader is responsible to the ECP Com-mander for managing the treatment of injured and/or contaminated personnel as outlined in AFRRIInstruction 6310.1A.
(4) Duties:
(a) Assign and direct Medical Personnel to perform life-saving actions, as necessary, for injured / contaminated personnel.
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(b) Establish and maintain close coordination with the Team I Health Physics Advisor if any personnel are contaminated or suspected of contamination.
(c) Establish and maintain communications with NNMC Emergency Room, as necessary.
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- e. Medical Personnel (1) The Director, AFRRI, shall ensure at least two personnel, with alternates, have been identified for assignment to this Billet.
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(2) Physicallocation will be at the ECP.
I (3) Responsibilities:. The Medical Personnel are responsible to the Medical Team Leader for performing life-saving actions as necessary for injured / contaminated 4
i personnel.
(4) Duties:
(a) Perform life-saving actions as necessary on injured / contaminated per-
)j sonnel.
(b) Keep Medical Team Leader informed of nature and status of injured /-
contaminated personnel.
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- f. Team I Health Physics Advisor 4
(1) Assignment and succession of a person to fill this billet shall be accomplished by the Head, Radiation Safety Department (SAF).
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(2) Physicallocation will be at the ECP.
(3) Responsibilities: The Team I Health Physics Advisor is responsible to the Special Advisor on Emergency Conditions for assuring that all radiation surveys at and outside the boundaries of AFRRI are performed as required and as directed; assuring that all actions concerning radioactively contaminated personnel are performed as required and directed; and assessing radiation levels and environmental releases of radioactive material at and outside the boundaries of the Institute. The Team I Health Physics Advisor is also responsible for directing and assisting the Team I Health Physics Monitors in the decontamination of contaminated personnel (4) Duties:
(a) Assure that appropriate emergency radiation equipment is readily avail-able (or accessible) and operable.
(b) Assign Team I Health Physics monitoring personnel to perform surveys of radioactively contaminated personnel and of areas outside the boundaries of AFRRI, as directed.
(c) Direct and assist the Team I Health Physics Monitor in the decontami-nation of contaminated personnel.
(d) Assign Team I Health Physics monitoring personnel to accompany injured / contaminated persons to the NNMC emergency room, if requested by the Medical Team Leader.
(e) Assure that radiation surveys outside the confines of AFRR1 are per-formed as required by the emergency conditions when directed by the Special Advisor on Emergency Conditions; provide this data to the Special Advisor on Emergency Conditions.
- g. Team I Health Physics Monitors (1) The assignment of two personnel and alternates for this billet shall be accomplished by Head, SAF.
(2) Physicallocation will be at the ECP.
(3) Resoonsibilities: The Team i Health Physics Monitors are resoonsible to the Team I Health Physics Advisor for performing their assigned health physics monitoring tasks.
(4) Duties:
(a) Perform surveys and conducting the decontamination of radioactively contaminated personnel as required and as directed by the Team i Health Physics Advisor.
(b) Accompany injured / contaminated persons to the NNMC emergency room when directed.
(c) Perform radiation surveys outside the confines of AFRRI as directed by the Team I Health Physics Advisor; provide this data to the Team I flealth Physics Advisor.
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- h. Search Team Marshal (1) Succession is as follows:
(a) Administrative Officer (b) Chief, Administrative Services Division (2) Physicallocation will be at the ECP.
(3) Responsibilities:
The Search Team Marshal is responsible to the ECP Commander for personnel accountability and for information on the general status of the AFRRI facility immediately after an emergency evacuation.
(4) Duties:
(a) Receive sweep reports from the Evacuation Search Teams.
(b) Receive muster reports from the Department Chairmen / Heads.
(c) Determine (from compiling and evaluating data received) if anyone is missing and who might still be in AFRRI.
(d) Report information on personnel accountability and facility status to the ECP Commander and to the Emergency Action Station Commander, as applicable.
(e) Provide Evacuation Search Team Sweep Reports, Department Muster 4
Reports and any additional personnel or Facility Reports to the ECP Recorder for disposition and filing with SAF.
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- i. Evacuation Search Teams (1) Assignment of personnel and alternates to fill these billets shall be the responsibility of the AFRR1 Administrative Officer.
(2) Location.
After each Evacuation Search Team Member has searched its assigned area (s), they will report to the Search Team Marshal at the ECP. Each Team Member will then muster with their department at the Emergency Muster Location (EML).
(3) Resoonsibilities: Each Evacuation Search Team Member is responsible to the Search Team Marshal for searching a specific assigned area (s) for personnel and hazards.
and reporting the search results to the Search Team Marshal and. if required, to the EAS Commander.
(4) Duties: Each Team Member is to perform the following duties in assigned zone (s), subject to their own discretion and good judgment in case of difficulty:
(a) CHECK all spaces (including rest rooms and equipment roo ms) for personnel and immediate hazards.
(b) CLOSE doors to offices and laboratories.
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(c) CLOSE corridor doors.
(d) TURN OFF or extinguish (if possible without undue risk) all sources of heat, fire, and/or sparks.
(e) CLOSE gas jets (if possible without undue risk).
(f) SECURE classified material and lock any safe observed open.
(g) REMOVE (or secure) all flammable liquids from the immediate vicinity of a fire or hazard (if possible without undue risk).
(h) REPORT any unsecured radioactive source to the Search Team Marshal at the ECP and the EAS Commander at the EAS.
(i)
DO NOT TURN OFF interior lights, unless they are the source of a hazard.
(j)
DO NOT MOVE an injured person unless in imminent danger and likely to sustain further injury if not moved or removed.
(k) PUT OUT any fire in assigned zone, without endangering life; or leave zone and report its status to the Search Team Marshal at the ECP and the EAS Commander at the EAS.
NOTE: Repert always to the Search Team Marshal at the ECP. whether or not able to search assigned zone (s). Make sure that the Search Team Marshal correctly records the Team's report, including any hazards noted and any areas not searched. If an immediate hazard is observed in an assigned area, report directly to the EAS Commander at the EAS. Then report to the Search Team Marshal at the ECP, and muster at the EML.
2.
Emergency Action Station (EAS). Physical Locatiom Initially, the area immediately outside the front door of the AFRRI will be the EAS (see page 2 of Enclosure 1 of this Instruction). After establishing this station, the EAS Commander may move the EAS to another area having adequate communications, for reasons of safety or efficiency; before doing so, the EAS Commander will notify the ECP Commander for approval to move.
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- a. EAS Commander (1) Succession to Command is as follows:
(a) Chief, Radiation Sources Division (b) Physicist-In-Charge (PIC), Reactor l
(c) Acting PIC, Reactor 1
l (2) Physical location will be at the EAS.
(3) Resoonsibilities: The EAS Commander is directly responsible to the ECP Commander for the immediate and continuing assessment of emergency conditions and for all actions taken within the boundary of the Institute during the emergency (including entry) and during any recovery or restoration operation (s).
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(4) Duties:
(a) Act for the Director of AFRRI in performing staff and technical supervision of and compliance with emergency evacuation procedures and actions.
(b) Establish the Emergency Action Station (EAS) and notify ECP when operational.
(c) Assign personnel to fill vacant emergency billets at the EAS, if necessary.
(d) Direct and advise all EAS personnel.
(e) Establish and maintain close communications with the ECP Commander, and to provide him/her with status and emergency information. (This can be most easily accomplished by designating a runner to transport one of the three Emergency Walkie-Talkies available at the EAS to the ECP Commander, when evacuating the building.)
(f) Receive reports directly from the person who initiated the evacuation or when applicable from an Evacuation Search Team (s) within whose search zone (s) an emergency or hazard is noted.
(g) Receive personnel accountability reports /information from the Search Team Marshal.
(h) Receive notification and information on the location, extent, and type of hazard or' emergency throughout its duration.
(i)
Meet and brief responding Fire / Rescue personnel upon their arrival at AF RRI.
(j)
Direct the establishment of Institute controlled-access points as neces-sary, for personnel traffic control and Institute physical boundary security.
(k) Establish, direct, and coordinate all Entry Team activities.
(1)
Recommend actions to the ECP Commander and implement them, if approved.
i (m) Implement and carry out all directives from the ECP Com mander pertaining to activities within the Institute boundaries during an emergency or recovery /-
restoration operation.
- b. Recorder for EAS (1) Succession is as follows:
(a) Secretary of Radiation Safety Department.
(b) Secretary of Radiation Sciences Department.
(c) Alternate as assigned on-site by the EAS Commander.
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(2) Physicallocation will be at the EAS.
(3) Responsibilities:
The Recorder for the EAS is responsible to the EAS Commander for maintaining a log of all actions and decisions that occur at the EAS, and for forwarding received reports and information to the EAS Commander.
(4) Duties:
(a) Receive and record information from the Area Controller.
(b) Receive and record information from the EAS Commander.
(c) Maintain a log of all actions and decisions made at the EAS.
(d) Upon termination of alert turn in all records and reports to SAF for filing.
- c. Team II Health Physics Advisor (1) Succession is as follows:
(a) Head of the Safety Operational Health Physics Division (b) Alternate assigned by Head. SAF (2) Physical location will be at the EAS.
(3) Responsibilities: The Team II Health Physics Advisor is responsible to the EAS Commander for the assessment of radiological conditions within the Institute, and for the direction and coordination of activities of the Team II Health Physics Monitors.
(4) Duties:
(a) Ensure that the EAS Emergency Box, located in the AFRRI main lobby, is moved to the EAS.
(b) Ensure that the front door emergency constant air monitor (CAM) is properly positioned and functioning.
(c) Assure that a Team II Health Physics Monitor (s) begins to dress out in appropriate protective equipment for entry with the Entry Team (firemen and others) upon direction and establishment by the EAS Commander.
(d) Inform and advise the EAS Commander of radiological conditions within the Institute. including the result of the emergency CAM sampling.
(e) In coordination with the Area Controller, aid in the setup of a controlled-access point to prevent or reduce the spread of contamination, if necessary, upon establishment and direction by the EAS Commander.
(f) Assist in coordinating Entry Team efforts as directed by the EAS Com mander.
I 9
(g) Assign a Team II Health Physics Monitor (s) to accompany the Entry Team (s) to perform radiation surveys, upon establishment of an Entry Team (s) by the EAS Commander.
(h) Assess and advise the EAS Commander of the on-site health physics aspects of the emergency or hazardous condition, during the course of the emergency, as necessary.
- d. Team II Health Physics Monitors (1) This billet will be filled by at least two Health Physics personnel assigned by SAF.
(2) Physicallocation will be at the EAS.
(3) Responsibilities: The Team II Health Physics Monitors are responsible to the Team II Health Physics Advisor for performing their assigned health physics monitoring tasks.
(4) Duties:
(a) When evacuating the building, move the EAS Emergency Box to the EAS and set up the front door emergency constant air monitor (CAM).
(b) Dress out as directed by the Team II Health Physics Advisor.
(c) If designated a member of an Entry Team by the EAS Commander or the Team II Health Physics Advisor, perform radiation surveys continuously during the entry, and inform and advise the Entry Team Leader of the radiation environment and any radiation hazards. Keep a close watch on radiation dose to the Entry Team Members, and recommend to Entry Team Leader necessary actions to prevent overexposure.
(d) Report results of radiation surveys to the Team II Health Physics Advisor or the Entry Team Leader, as appropriate.
- e. Nonradiological Hazards Advisor (1) Succession is as follows:
(a) Head, OccupationalSafety and Health Office (OSH)
(b) Alternate assigned on-site by EAS Commander.
(2) Physicallocation will be at the.EAS.
(3) Responsibilities: The Nonradiological Hazards Advisor is responsible to the EAS Commander for providing information, advice, and assistance concerning nonradio-logical hazards.
(4) Duties:
(a) Assure that appropriate and operable emergency equioment :s re idity available, or accessible, and operational.
to
(b) Provide information, advice, and assistance as necessary to the EAS Commander concerning nonradiological chemical and toxic material hazards within the Institute.
- f. Area Controller (1) Succession is as follows:
(a) Security NCOIC (b) Acting Security NCOIC (c) Alternate assigned on-site by EAS Commander.
(2) Physical location will be at the EAS.
(3) Responsibilities: The Area Controller is responsible to the EAS Commander for facility boundary security, for vehicular traffic control at the site, and for personnel traffic control at the facility boundary.
(4) puties:
(a) 3ssign personnel to direct and control traffic on the roads surrounding AFRRI to ensure quick access for emergency vehicles and equipment.
(b) Control personnel access to the AFRRI to ensure that only authorized personnel enter the building during an emergency.
(c) Assign personnel to establish and maintain facility boundary security and personnel traffic control at the facility controlled-access point (s) upon establishment and direction by the EAS Commander.
- g. Facility Advisor (1) Succession is as follows:
(a) Facility Manager, LOG (b) Assistant Facility Manager. LOG (2) Physical location will be at the EAS.
(3) Resoonsibilities: The Facility Advisor is responsible to the EAS Commander for providing information, advice, and assistance concerning the AFRRI facility.
(4) Duties:
(a) Duties of the Facility Advisor are to perform tasks as assigned and provide information as requested by the EAS Commander pertaining to the AFRRI facilities and equipment.
(b) Serve as a member of the Entry Team at the direction of the EAS Commander.
11 1
- h. Fire Marshal (1) Succession is as follows:
(a) NNMC Fire Marshal (b) Representative of NNMC Fire Marshal at the site (2) Physicallocation will be at the EAS.
(3) Responsibilities: The Fire Marshal is responsible to the EAS Commander for providing and coordinating fire-fighting and rescue operations during an emergency.
(4) Duties:
(a) Receive briefing upon arrival at the scene, by the EAS Commander.
(b) Assign fire and rescue personnel to the Entry Team (s) upon direction by the EAS Commander.
(c) Establish and maintain communications with entering fire and rescue personnel.
(d) Coordinate activities of entering fire and rescue personnel.
(e) Inform and advise the EAS Commander of the activities of entering fire and rescue personnel, and of the status of the fire hazard or other nonradiological hazard, as appropriate.
(f) Ensure that fires, other nonradiological hazards, and injured personnel are given fire and rescue attention and treatment, as appropriate, by entering fire and '
rescue personnel.
- i. Radiation Source Advisors (1) Succession is as follows:
(a) Primary Source Manager from each of the three major AFRRI radiation sources (i.e. Reactor, Cobalt, and LIN AC)
(b) Alternates assigned by Chief, Radiation Sources Division (2) Physicallocation will be at the EAS.
(3) Resoonsibilities: The Radiation Source Advisors are responsible to the EAS Commander for providing information, advice, and assistance concerning their respective major radiation source facilities at AFRRI.
(4) Duties: Duties of the Radiation Source Advisors are to provide information, advice, and assistance upon request by the EAS Commander concerning their respective major radiation source facilities at AFRRI.
12
O a
- j. Entry Team. Personnel appointed to an Entry Team are selected by the EAS Commander at the time of or during an emergency from competent personnel available at the EAS. An Entry Team usually consists of one or more firemen, a Team II Health Physics 31onitor, and a member from LOG. Other personnel may be assigned by the EAS Commander, depending on the nature of the emergency.
The EAS Commander will assign the duties of the Entry Team before entry into the Institute. An Entry Team Leader will be appointed by the EAS Commander. Upon entry, the Entry Team members are responsible to the Entry Team Leader who, in turn, is responsible to the EAS Commander. Communications will be established and maintained between the EAS Commander and the Entry Team Leader upon entry into the Institute.
- k. Person Turning In Alarm Upon DISCOVERY of a fire or other hazardous condition, l
(1) PULL the nearest fire alarm.
(2) EVACUATE the Institute immediately.
(3) REPORT the nature, extent, and location of the emergency or hazardous condition to the EAS Commander or the Security Watch, as appropriate, at the EAS.
NOTE: The person turning in or initiating an evacuation alarm shall report to the EAS Commander or to Security Watch Personnel, as appropriate, at the EAS immediately af ter evacuating the Institute, regardless of whether the alarm was intentional or inadvertent.
3.
Emergency Muster Location (EML).
Physical Location:
The Emergency Muster Location (EML) will be under the bridge adjacent to the front entrance of AFRR1 for all AFRRI departments except VMD. VMD will muster in the rear parking lot behind Building 47 (New Animal Facility).
- a. Department Chairmen / Heads l
{
'(1) Succession is as follows:
(a) Department Chairman / Head for each department (b) Acting Department Chairman / Head for each department (2) Physical location will be at the EML.
(3) Responsibilities: Each Department Chairman / Head is responsible at the EML for personnel accountability and control within his/her department at the EML and for reporting this personnel accountability information to the Search Team Marshal at the ECP.
i (4) Duties:
(a) Muster and account for all Department personnel at the EML.
13
(b) Give Department muster report to the Search Team Starshal at the ECP, to include the names of any Department personnel not accounted for, who might be inside the AFRRI.
(c) Provide to the Search Team Marshal the names of all Deptrtment personnel who have pocket ion chamber dosimeter readings greater than 100 mR.
- b. Staff (1) All persons not assigned a specific emergency duty or responsibility and who are in the AFRRI complex at the time of an emergency are classed as staff.
(2) Staff Resoonsibilities.
Upon hearing the fire bell, all staff members will immediately evacuate the AFRR1 complex via the nearest safe exit, and assemble at the EML.
(3) Duties:
(a) Immediately evacuate the building via the nearest safe exit upon hearing a fire alarm.
(b) Muster in an orderly fashion with the appropriate Department Chairman / Head or representative at the EML (see Enclosure 1).
(c) Follow the directions of the appropriate Department Chairman / Head or representative and the ECP Commander. (Under no circumstances is any member of the staff to interfere with any emergency activities or to act independently after reporting to the EML.)
NOTE: During nonduty days and after 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on duty days, in addition to the above, each staff member is responsible for signing in and out on the Security Area Register maintained at the AFRRI Reception Desk.
s, AFRRI EMERGENCY ORGANIZATION:
1 LINES OF RESPONSIBILITY AND FLOW OF INFORMATION EMERGENCY MUSTER
- a~
OEPT CHAIRMEN /
5 "
LOCATION (EML)
HEAoS (3bi (3al (para. 3) 5,
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's, EMERGENCY COMMANO RECoRoER POST (ECP) htpl
'g (para.1)
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- DNES OF COMMUNICATtON, REPCRTING l3
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'J E S O F 4 E SPC'.S 9' u '
u PROCEDURE FOR AFRRI EVACUATION SEARCH TEAMS 1
3 r
1.
Search Areas. The specific search zones within AFRRI are illustrated on page 2 of this Enclosure.
2.
Duties.
Each Evact$ttion Search Team shall perform the following duties in its assigned zone (s), subject to discretion and good judgment in case of difficulty:
4
- a. CHECK all spaces (including rest rooms and equipment rooms) for personnel and immediate hazards.
- b. CLOSE doors to offices and laboratories.
- c. CLOSE corridor doors.
- d. TURN OFF or extinguish (if possible without undue risk) all sources of heat, fire, and/or sparks.
- e. CLOSE gas jets fih possible without undue risk).
- f. SECURE classified material and iock any safe observed open.
- g. REMOVE or secure all flammable liquids from the immediate vicinity of a fire or hazard (if possible without undue risk).
- h. REPORT any unsecured radioactive source to the EAS Commander at the EAS and the Search Team Marshal at the ECP.
. l.
DO NOT TURFoff interior lights, unless they are the source of a hazard.
J. DO NOT MOVE an injured person unless he/she is in imminent danger and likely to i
sustain further injury if not moved or removed.
l 1
- k. PUT.OUT any fire in assigned zone, without endangering life; or leave zone and report its st_atus immediately to the EAS Commander at the EAS and the Search Team Wrshal at the ECP.
NOTE: Report always to the Search Team Marshal at the ECP, whether or not able to search assigned zone (s).3 Make sure that the Search Team Marshal correctly records the report, including any hazards noted and any areas not searched. If an immediate Team's,is observed in an assigned area, report directly to the EAS Commander at the EAS.
hazard l
Then report to the Search Team Marshal at the ECP and remain available at the ECP to provide additional assistance, if needed. If not needed, muster at the EML.
l l
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1 N'
l Enci 5 :: ;i??
' n : ~~ 03.7 l
I AFRRI ZONE ASSIGNMENTS FOR EVACUATION SEARCH TEAMS FIRST LEVEL ZONE 11 h tfdd7' "Ei2 m
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CRITERIA FOR NOTIFICATION OF OUTSIDE AGENCIES REQUIRED NOTIFICATION Personnel Notified Requiring Instruction or Regulation Conditions NEMC Fire NNMC/AFRRI Host-Tenant Agreemt Fire and/or hazardous Dzpartment N00168-81274-007; term. date Sep 86 conditions HQ,DNA DNA Instruction 7730.2B Nuclear accident or signi-ficant incident involving nuclear material AFRRI Instruction 5200.14 Felony, crimes, incidents AFRRI Instruction 5200.14 Natural phenomenon or disaster; racial or labor dis--
turbances involving DNA personnel or facilities DNA Instruction 5230.1; Nuclear accident or AFRR1 Instruction 5230.1 significant incident NRC (after con-AFRRI Reactor License R-84 Reactor or nuclear sultation with and accident or incident concurrence of EAS Commander & Reactor Physicist-in-Charge)
PAO,DNA DNA Instruction 5230.1; Nuclear accident or AFRRI Instruction 5230.1 significant incident JNACC DNA Instruction 7730.28 Nuclear accident or sign'ificant incident CO, NNMC NNMC/AFRRI Host-Tenant Agreemt Formally declared emer-N 00168-81274-007; term. date Sep 86 gencies 't drills or praetm.
activities in preparation for operations under emergency conditions NRC Title 10 CFR, Part 20, Standards Any incident involving by-(immediate) for Protection Against Radiation product, source, or special nuclear material that has caused or threatened to cause violations of 10 CF R 20.402 or 20.403 News Media DNA Instruction 5230.1; Promotion of public safat:.
Representatives AFRRI instruction 5230.1 or prevention of wideson
,,4 public alarm inn 6
- 3 =.=.
- -n:
e a,
SOURCES OF ADDITIONAL SUPPORT Pcrsonnel/
Committing Instruction, Organization Regulation, or Letter Tvpe Support Offered Disaster Prepared-NNMC/AFRRI Host-Tenant Agreemt Complete emergency ness Officer / Plan N00168-81274-007; term. date Sep 86 support NNMC Emergency Room NNMC/AFRRI Host-Tenant Agreemt Emergency medical N00168-81274-007, term. date Sep 86 treatment NNMC Ambulance NNMC Instruction 11240.20 Emergency medical treatment NNMC Radiation NHBETH Instruction 6470.40 Film badge development Safety Office safety and interpretation; radioactive material counting and monitoring NNMC Decontami-NHBETH Instruction 6470.40 Decontamination of nttion Facility personnel NNMC Security NNMC Instruction 11320.1C Perimeter control NBS (Dr. Schwebel)
Radioactive material counting and analysis NRC Emergency NRC Radiological Assistance Team Program Environmental Protection Environmental evaluation Agency Environmental Maryland Department of Health evaluation Ewe d%
. e a.
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IMD[ATIO[80tKES DIVISIW 4 January 1982
~
IMrIRUCTI N IG EER 5-1 Ft2CTIQ6 AIO GGWIZATIN
& 'IfE REACIm IRAICI 1.
Purpose. To set forth the functions and organization of the Reactor Branch IAW AFRRI instruction 5100.1, "AFERI Organization," and to define the duties of the personnel.
2.
Applicability.
'Ihe provisions of this instruction are applicable to the Reactor Branch staff.
3.
Cancellatlon. RSD Instruction 5-1, " Functions and Organization of the Reactor Branch," dated 27 March 1981, is hereby cancelled.
4.
Functions, a.
Operates, calibrates and niaintains the AFRRI 'IRIGA Reactor and associated systens in empliance with appropriate regulations.
b.
Provides radiation exposures in the various experimental facilities in direct support of the AFRRI research mission.
c.
Supplies instruction and technical assistance to the AFRRI staff, relat-ing to reactor operations, utilization, perfonnance, limitations, instrinnenta-tion, design, and nodification.
(m
/
d.
Conducts research to analyze reactor characteristics and perfonnance, dtvelop and advance its capabilities, increase its reliability and safety, and svolve new applications.
5.
Organization.
'Ihe block diagran presented in Enclosure 1 defines the crganizational relationships among the positions. The dutles and qualifications for each position are defined in the following paragraphs:
a.
Physicist-In-O arge (PIC) of the Reactor Branch.
(1) The PIC will possess an NIC Senior Reactor Operator License for the AFRRI 'IRIGA Reactor under the provisions of 10 GR-50 and 10 GR-55.
(2) The PIC is responsible to the Head, Radiation Sources Division, for dtsign, operational, technical, adninistrative, and safety matters pertaining to the utilization of the reactor in support of APRRI approved research prograns.
(3) 'lhe PIC is directly responsible to the Head, Radiation Sources Division, for insuring empliance,dth the 140 Facility License (R-84) including all snendnents, other NIC regulations, and APRRI instructions.
(4) The PIC will resolve conflicts between the various AFFRI user requirenents concerning scheduling of the reactor in the event that the Olef Supervisory Operator (GO) who schedules the routine use of the reactor, is unable O to resolve the conflict.
The PIC will contact the Olef, Radiation Sources V Division, in the event of a conflict involving a question of research priorities.
/}TT/KHMENT 2 1
s RAblATIdiSOURCESDIVISIW 4 January 1982
'O INS'IRUCTIW NihBER 5-1 (5) The PIC will sign all Reactor Use Requests (RURs) thereby giving his official approval for operation of the reactor as indicated.
(6) 'Ihe PIC, as the Olef of the Reactor Branch, will participate in special development projects as authorized or directed by the Olef, Radiation Sources Division.
(7) De PIC is responsible for the training of Reactor Operater trainees in preparation for NEC certification as 10s or SiOs.
(8) The PIC is also the principal administrative officer of the Branch and as such will maintain the files and periodically review and update operating procedures.
(9) he PIC is responsible for the empletion and sutrnittal of all required reports.
(10) During the absence of the PIC for nere than one day, the Director will designate, orally or in writing, a qualified individual to act as the PIC. In all other absences, the C90 is authorized to act on behalf, and instead of the PIC.
(11) 'Ihe PIC may deviate fran the provisions of the RSD instructions if such a deviation does not violate the AFERI-TRIM Reactor License, NIC regula-tions, applicable AFRRI safety directives, and he has received prior approval fran the O lef, Radiation Sources Division for each and every such deviation.
(12) The PIC's staff includes the CSO, all assigned reactor operators, cnd all assigned reactor operator trainees.
b.
Olef Supervisorn Operator (b90).
a (1) he C90 will possess an MC Senior Reactor Operator License for the l
AFRRI 'IRIM Reactor under the provisions of 10 GR-50 and 10 GR-55.
(2) 'Ihe 00 is responsible to the PIC for the efficient, safe operation of the reactor on a daily routine, and for its maintenance.
(3) Af ter tentatively scheduling reactor time the OO will forward to the PIC RLRs sutznitted by investigators.
(4) 'Ihe 00 will schedule reactor time as requested by approved users for cpproved research.
In the event of an unresolved scheduling conflict he will g
refec,the matter to the PIC.
l (5) 'Ihe OO will schedule the operations and maintenance activities of the assigned licensed operators and trainees.
\\
l (6) The 0 0 wil Ding on the operations / maintenance of the resetor systen, andH!!,@__.._g $e re3urring training of licensed operators IAW NRC regulations and the AFRRI Reactor Operator Requalification Program.
1 i
1 1
(2)
L
RADIA'flCN SOUR S DIVISICH 4 January 1982 A,
INS'IRUCTICN NibEER 5-1 L
(7) The GO will direct the supply activities of the Reactor Branch. The supply activities include requisitioning equipnent and expendable supplies, main-taining supply records, and equipnent inventories.
(8) 'Ihe GO is primarily responsible for execution of the Reactor Maintenance Prograrn as prescribed in NSD Instruction 5-4.
c.
Reactor Operator (IO).
(1) All assigned H0s will possess either an NRC Senior Reactor Operator (SIO) or an NIC Reactor Operator License for the AFRRI 'IRICA Reactor, under the provisions of 10 G R-50 and 10
-55.
(2) The 10 will be trectly responsible for the safe and legal operation of the reactor in empliance with the Reactor License (R-84), 10 GR, AFRRI Instructions and the RSD Instructions.
(3) 'Ihe 10 will perfonn operation and maintenance duties as assigned by the C90, and other duties as assigned by the PIC.
d.
Reactor Operator Trainee.
(1) High School or equivalent.
O (2) se in training for NIC operator examination.
(3) At no time will a reactor operator trainee manipulate the controls of the reactor alone (i.e., while not under the direct supervision of a licensed HD l
or SID).
l l
6.
Performance Ratings, t
a.
The military performance ratings will be acecriplished IAW AFRRI Instruc-tion 1600.1, " Performance Ratings and Schenes."
b.
'Ihe civilian performance ratings will be accmplished IAWINA Instruction 1434.1, " Performance Evaluation."
7.
Radiation Sources Division Instructions.
a.
'Ihe Reactor Branch will function and operate the AFERI 'IRIGA Reactor and support systems IAW the Reactor License, 10 GR, AFRRI Ins etions and all i
applicable RSD instructions; i.e., RSD 5-series.
/
pW
^
J EPH A.'
TI Car, uSAe Reactor Branch Ofef and Physicist-In-Oarge l
Y-l HCNAID R. ShMER EN, USA MAJ,f. Radiation Sources Division l
Chie l
(3)
4 January 1982 A
U REACTOR BRANCH ORGANIZATION ADMINISTRATION Head (Physicist-In-Charge)
PIC Q
OPERATIONS h
Chief Supervisory Operator CSO I
Operator / Reactor Staff
('.
l l
.i O
t Ibclosure 1 to RSD instruction 5-1.
j
RADIATIO 4 SOLICES DIVISIW 4 January 1982 IMrIRLLTIW IOBER 5-2 A
NMINISTRATIVE LIMITS A10 L
CINIIELS RR REACIm TERATIO6 1.
Purpose.
To establish the adninistrative limits and controls for reactor operations that will insure carpliance with the Reactor License (R-84) and the Technical Specifications.
2.
Applicability.
De provisions of this instruction are applicable to the AFERI-1RI M Reactor and all operations conducted using the reactor, the reactor support equipnent, and the irradiation facilities.
3.
Cancellation. RSD Instruction 5-2, "Adninistrative Limits and Controls for Reactor Operations," dated 27 March 1981 is hereby cancelled.
4.
Operating Limits.
The operation of the AFERI-TRIG Reactor and associated facilities will be performed IAW the AFERI-TRIG Reactor License (R-84), Technical Specifications, and with the following adninistrative operating limits and con-trols.
a., Adninistrative Controls b.
Mode Operation Limits (See Table 1) c.
Miscellaneous Operation Limits (See Table 2)
Q 5.
Adninistrative Controls.
De mininun operable instrinnentation for reactor power operation shall a.
consist of the following:
(1) Two independent reactor power level monitoring channels which indi-cate the power level of the reactor during the steady state mode of operation.
(2) An E f channel for pulse operation which indicates the integrated power produced during a pulse.
(3) Scrams as indicated in Table 3.
(4) A miniman of two radiation area monitors and a continuous air monitor in the reactor roan. The radiation area monitor directly over the reactor e
pool surface and the continuous air monitor shall produce audible and visible alarm signals in the control roan. D e second area monitor in the reactor roan shall have a visible alarm in the control roan. The continuous air monitor in the reactor roan must be capable of autanatically isolating the reactor roan air voltane upon receipt of a high level alann.
(5) 'Iwo radiation area monitors in the preparation area on the wall directly opposite both Exposure Roan #1 and Exposure Roan #2 plug doors to serve as radiation stresning detectors.
(6) A radiation detector systen continuously sanpling the effluent fran
~.Q the reactor building ventilating systen exhaust stack and capable of producing a visible alann at the control console.
i RADIATIN SOW G S DIVISIW 4 January 1982 INS'IRLTIN NUEER 5-2 V
b.
A "Startup Oecklist" will be acceplished each day (or other extended operational period) that reactor power operations are planned, prior to performing r.ny operations (other than those required for the startup).
A Senior Reactor Operator (SRD) will approve and sign the ecnpleted "Startup Gecklist."
he licensed SRO that approves the checklist cannot be the same licensed operator that Eecarplished the checklist.
f,oA eTwt emwnee efence esmoQ Ttwr c.
Excess reactivity will be measured on each dayAany power operat is planned. 'Inis measurement will be the first reactor power operation of that day af ter conpletion and approval of the startup checklist.
The same SRO that signed / approved the startup checklist will initial this k-excess measurenent in the logbook.
~
d.
The reactor will be operated in Modes II and III IAW the " Mode II O ecklist" and " Mode III O ecklist," respectively.
i e.
A " Nuclear Instrtunentation Oecklist" will be accamplished each week that a reactor operation is planned.
De coupleted checklist will be reviewed and l
signed by the Olef Supervisory Operator (C90) or the Physicist-In-Oarge (PIC).
f.
An " Annual Shutdown Maintenance Oecklist" will be acconplished by the C90 during each annual shutdown maintenance period.
D e checklist will be reviewed and signed by the PIC.
g.
Before any Mode II or More III operation, the reactor will be at a steady O
state power level for at least 30 seconds, since the last control rod movenent, and with the power level at cold critical.
h.
When the reactor is operating, all doors and hatches into the Reactor Room will be closed with the exception that Door 3161 may be opened to pennit personnel passage frcrn the hallway into the Reactor Roan or return.
- i. During reactor power operations, no person will be allowed inside the chain surrounding the Reactor Pool except as authorized by the PIC or CSD.
- j. We Reactor Operator at the console or the Senior Reactor Operator on duty, as appropriate, will be notified before opening, closing or use of any exposure facility.
k.
When an unprogrsuned scran occurs, the reactor operator will notify the senior operator on duty and the CEO and PIC and nake appropriate logbook entries.
Reactor operations will cease until the scran condition or cause has been investigated and corrected.
1.
D e Q OSE switch for the lead shield doors will not be depressed during nonnal operations while the core dolly is in Position 2.
De QOSE switch may be depressed, with the core dolly in POSITIN 2, to check the operability of the reactor core position safety interlock.
His will be acccuplished under the direct supervision of the CBO.
~
m.
During nonnal operations, no attenpt will be made to drive the core dolly into Region 2 when the lead shield doors are not fully open. Only the C30 may perfonn this action but only to check the operability of the reactor facility core position safety interlock.
W
RADIATIOi80WQ3DIVISICN 4 January 1982 INS'IRUCTICN ISBER 5-2 AV n.
A " Shutdown Cnecklist" will be acceplished each day (pr other extended operational period) for which a "Startup O ecklist" was performed.
o.
D e reactor operator will maintain in the " Reactor Operations Logbook" a clean and concise account of all operations.
The entries will be made IAW the
" Reactor Operations Logbook Entry Oecklist" such that all operations being performed could be reproduced at any future date. 'Ihe future reproduction of any reactor operations would include using the " Malfunction Logbook," the Maintenance Log," the Reactor Use Request," etc.
p.
For any reactor operation, excluding routine reactor maintenance, a mininun of two NIC licensed operators will be present in the AFERI carplex. One operator will be an NEC licensed senior reactor operator. The second operator nay be an SHO or 90. When the key is in the reactor console, a licensed operator will be present in the control roan.
If the operator at the reactor console anticipates the need for assistance, a second staff msnber or operator will be available such that voice conmunication can be established between the two.
q.
" Reactor Operating Instruction Books" will be in the Reactor Control Roan and be accessible to the operator at the reactor console. These notebooks will contain the following information pertinent to reactor operations:
(1) AFRRI 'IRIGA Reactor License R-84 (2) AFRRI 'IRIGA Technical Specifications O
(3) RSD Instructions (4) Pertinent AFERI Instructions (5) RAD-SAF SCPs (HPPs) & RSIs (6) Carpleted checklists for the current year (7) Current core data (8) Other data as desired r.
Reactor Experiments.
O (1)
Before any experiment can be conducted using the reactor and/or ext.erimental facilities, the experiment will be reviewed by the " Reactor and Rad 2ation Facility Safety Cannittee."
If approved, the " Reactor and Radiation Fecility Safety Carmittee" will issue either a "Special Reactor Authorization" or a " Routine Reactor Authorization."
(2) The scheduling of reactor experiments will be accarplished IAW AFRRI Instruction 3000.4 " Reactor Operations," and RSD Instruction 5-1.
(3) Before an experiment can be perfonned, the reactor operator will insure that the following conditions are met:
c-
%.)
(a) Except as noted in paragraph 4 below, a Reactor Use Request (RUR), AFRRI Fonn 2, has been carpleted, approved, and signed by the PIC.
ou
1801ATI'm SOLB S DIVISIN 4 January 1982 INSTRUCTIN NUEER 5-2 O
L (b) No unsafe conditions exist with either the reactor system or the experimental facilities.
(4) 'Ihe following operations do not require an RUR:
(a) Reactor operator training (b)
Instrtmentation checks and calibrations (c) K-excess measurenents (d) Reactor and reactor facility paraneter measurenents (e) Maintenance (f) Tours (5)
If it is anticipated that an experiment will cause a reactivity change in excess of 1.0.S k/k, (t $'71) k-excess measurenents will be made, at the core position where the experiment will be perfonned, both with and without the experiment inserted.
In addition, k-excess measurenents will be made on all new experiments regardless of their anticipated worth.
O TABLE 1 MIE OPERATIN LIMITS AIO ASSOCIATED SGAM SEITIKE MIE MAXIMAf PWER LIMI'IS AUIOfATIC SOAM SEITIME I & IA 1 W Steady State 11096 of hhxinun Power (1.1 W)
Fuel temerature of 500*C (2 E channels).
II 1 W Steady State 11096 of Maxinun Power (1.1 m)
Fuel temerature of 500*C (2 'IC channels)
III 2.396ek/k Pulse Peak Power not to exceed 2750
($3.28)
W.
Fuel temerature of 500*C (2 E channels).
(4)
ItADIA'rIW SOUECES DIVISIW 4 Jr.nuary 1982 IN!hRUCTIW NthBER 5-2 TABLE 2 n
MISOLIANERE OPERATIW LIMI'IE 2
PAIUAETER
%_,1
'ISL Maxinun Excess Reactivity 3.3% Ak/k 3.R Ak/k With Infinite Water Reflector
($4.72)
($5.00) cnd With or Without all Experiments Installed Maxinun Absolute Reactivity 2.E Ak/k 2.1 k/k Giange for Experiments
($2.86)
($3.00)
Bulk Water Tarperature 50*C 60*C Maxinun Fuel Tarperature 500*C 600*C 3
4 Primary Coolant Conductivity 2.0 ;soho 2.0 Ao an an 1 - Operating Limit 2 - Technical Specification Limit 3 - Maxinun Measured O
4 - Averaged Over One Month TABLE 3 l
MINIMM REACKR SAFEIY SYSTEM SGAMi Mode in which Effective Originating Channel Set Point SS Pulse 1.
Percent Power
_/-1.1 M yt X
2.
Scran Button on Console X
X 3.
Preset Pulse Timer Less than or equal X*
to 15 seconds 4.
Pool Water Level
> 14 feet above X
X top of core 5.
Scran Button in Exposure X
X Roan 6.
Fuel Tarperature (2
{600*C X
X independent channels) 7.
Loss of Ion Chanber High X
X Voltage i
8.
Loss of Facility Electrical X
X l
Power
- Required, as a mininun, to scran the transient rod following a pulse.
V
(
(5) 1
RADIATI N SOLB ]S DIVISI W 4 January 1982 INS'IRLUTIW NUEER 5-2
/
s/h A.
, JR.
C W P, USAP Reactor Branch Chief and Physicist-In-Charge M
IDWD R' SOER fMJ, I!N, USA Chief, Radiation Sources Division O
i t\\'
i (6) l
RADIATIW SOLRIS DIVISIN 4 January 1982 INS'IRLLTIm DBER 5-3 N
N 1.
Purpose. To set forth the energency procedures to be followed in the event of a radiation alann or hazard, a fire, or other threatening events to the Reactor Facility should occur.
2.
Applicability.
'Ihe provisions of this Instruction are applicable to the AFRRI 'IRIM Reactor, the Reactor Branch staff, and the Safety Department staff.
3.
Cancellation. RSD Instruction 5-3 " Reactor Branch Bnergency Procedures," 27 March 1981, is hereby cancelled.
4.
Radiation Hazard. 'Ihe auxiliary detection systens for the AFRRI 'IRIM Reactor are presented in Table I (See Enclosure 1). The sensor, range, alarm settings, and alann notification are included in Table I for each individual systen. Any deviation fran these established setpoints requires the authority by the PIC, subsequent to coordination through the Head, Radiation Sources Division, and the Head, Radiation Safety Department, in writing.
a.
Inmediate action.
'Ihe licensed reactor operator at the console will respond to activated alarms as follows:
(1)
If any alarm listed in Table I occurs, the reactor will be scranmed within 15 seconds unless the operator is certain of the cause of the alann, and that no hazard exists.
If the alarm occurred as a result of a malfunction on any O
instrunent required by the Technical Specifications for the AFRRI Reactor (indi-cated by # in Table I) the reactor will be scranned inmediately. The PIC or his designee will be inmediately notified, and the alann will be recorded in the Reactor Operations Log.
(2)
In the event of an alann fran the Stack Particulate Monitor, the operator will ascertain if the LINAC is operating.
'Ihis infonnation will be considered before determining which action to take in (3) below.
(3)
If any alarm listed in Table I occurs, the PIC or his designee will decide which one of the following actions to take:*
- (In the absense of the PIC or his designee, the licensed reactor operator at the e
reactor console will make the decision himself or herself).
(a) Action #1 - Sound the fire alarm to evacuate the AFRRI emplex.
(b) Action #2 - Give oral orders to evacuate the imnediate area in the vicinity of the radiation hazard.
(c) Action #3 - No radiation hazard exists and evacuation is not required.
(4) At no time will any reactor operator take actions in response to instrtsnentation which would be in violation of the Technical Specifications of the
{
AFRRI Facility License R-84.
'RADIATIN SOURCES DIVISIW 4 January 1982 INirIIEXII W NLIEER S-3 p
b.
Action #1.
The Reactor Branch staff will respond to this action as follows:
v (1) AFRRI Instruction 3020.2, "AFERI Bnergency Evacuation and Fire Plan" will be inplanented, and the Reactor Branch staff will respond in accordance with that Instruction.
(2)
If the reactor is operating, the operator will scran the reactor, insure that all rods are seated, and lock the reactor console. The operator will pickup all the keys in the Reactor Console Roan, the Reactor Operations Log and the Bnergency Checklist, close the doors to the Reactor Control Roan, and then report to the PIC. The operator will give the keys, energency checklist, and the Reactor Operations Log to the PIC.
(3) The reactor operator will insure that the experimental facilities are secured.
(4) A detailed investigation of the radiation hazard will be conducted, and a written report, stzunarizing the results of the investigation, will be empleted by either the PIC or his designee, and suttnitted through the Head, Radiation Sources Division to appropriate managenent levels within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
c.
Action #2.
The Reactor Branch staff will respond to this action as follows:
(1) Same as subparagraph 4b(2).
O (2) 'Ihe Health Physics Division personnel will be inmediately notified of the hazardous condition by either the PIC, CSO, or the reactor operator.
(3) 'Ihe reactor operator will insure that the experimental facilities are secured.
(4) A Ccunnand Post will be established at the nearest safe point to the evacuated area having adequate emnonications.
The PIC, his designee,
- Chief, Radiation Sources Division, or the 0 0, as available, in that order, will act as the Ccrumnd Post Cannander under such situations.
(5)
If time allows, a two man re-entry tesn will consist of one nmber of the Reactor Branch staff, and one mmber of the Health Physics Division staff.
The teen will suit up accordingly and will enter the evacuated area to determine the type, size, and extent of the radiation hazard. The teen will renove injured personnel if required.
'Ihe corrective action taken will be detennined by the information acetamlated by the re-entry tesn. The snount and type of protective equigrnent carried or worn by the re-entry teen will be determined based on considerations of the type of hazard existing.
(6)
Injured and/or contaninated personnel will be handled in accordance with AFRRI Instruction 6310.1, "Managenent of Injured and/or Contaminated Person-nel."
c (2) l
'RAPIATIOi SOURCES DIVISI m 4 January 1982 INS'IRUCTIW NLABER S-3
{
(7) Same as subparagraph 4b(4).
d.
Action #3.
The Reactor Branch staff will respond to this action as follows:
(1) A thorough investigation will be conducted by the PIC or CBD to determine the cause of the alarm; the findings of this investigation will be reported to the Gief, Radiation Sources Division and Head, Radiation Safety Department, orally or in writing within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
(2) Corrective actions will be taken by the PIC, his designee, CSO, or Oief, Radiation Sources Division together with Head SAF to insure that the alann will not sound unnecessarily in the future.
5.
Fire Hazard. He Reactor Branch staff will respond to a fire hazard energency as follows:
a.
When the fire alann is sounded (continuous tone bell), this indicates that AFERI Instruction 3020.2, "AFRRI Bnergency Evacuation and Fire Plan," has been inplemented. De Reactor Branch will respond in accordance with that Instruction.
b.
Same as subpapagraph 4b(2).
c.
The reactor operator will insure that the experimental facilities are secured.
,O d.
if the reactor operator en the eensole discovers the fire he will foilow the procedures in subparagraph 4b(2). In addition, he will pull the nearest fire alarm when exiting the AFERI ccrrplex.
i e.
Personnel with contaminated clothing will not attenpt to change clothes prior to evacuation, but will segregate themselves when outside the building.
f.
No attengt will be made to rarove fuel elements from the reactor pool / core during a fire.
g.
If the fire occurred in the Reactor facility then an investigation will be l
initiated IAW subparagraph 4b(4).
6.
Natural Disaster. He Reactor Branch staff will respond to a natural disaster such as flood, tornado, hurricane, earthquake, etc., as follows:
i E
a.
If either a forecast is received that a natural disaster is inminent or a natural disaster strikes the AFRRI emplex, the reactor operator will inmediately scram the reactor, if operating, and then place the reactor in a secured l
condition, and notify the PIC, CSO, and O lef, Radiation Sources Division.
b.
He reactor operator will insure that the experimental facilities are secured.
t'
- V l
(3) i
t RADI' TIW SOLB ]S DIVISIW 4 January 1982 A
INS'IRLLTIN lOBER 5-3 O'
7.
Bmb 'Ihreat.
The Reactor Branch staff will respond to a bm1b threat as follows:
Upon receipt of a beb threat, Adninistrative Services Division and the a.
PIC will be notified inmediately.
b.
'Ihe Reactor Branch ataff wi11 take appropelate action in accordance with APRRI Instruction 5200.4, " Physical Security Plan for AFRRI," and AFRRI Instruc-tion 5220.4, " Physical Security P1an for APRRI 'IRICA Reactor Faci 1ity."
8.
Civil Disorder, Unauthorized Entry Into Reactor Controlled Access Area, Attested or Actual Thef t/ Diversion of SNW, or Threats of Sabotage Against AnetI cr the AFRRI Reactor. The Reactor Branch staff will respond to these threats in atecordance with Anatl Instruction 5220.4, " Physical Secu ity Plan for AFRRI 'IRICA Reactor Facility."
f A.
IS CAPT,IBAF Reactor Physicist-In-Oarge Mr IENAID R. SW3GR O
ma, m, US&
O lef, Radiation Sources Division 4
O r
(4)
m-m h
TABLE I l
TEGI SPIC SYSTB1 Ri%g3 IRED RAN3E AIMM SEITOINTS AIAlh1 MJrIFICATIN 6
i 1.
R-la 1 to 10 mr/hr a) 500 nr/hr when reactor a)I Local audible buzzer staff are on duty and red light.
j b) 20 nr/hr during non-duty b)5 Instrinnent nodule - audible hours buzzer and red light.
\\
c)3 Annunciator Panel -
audible horn and red light.
5 2.
R-2a 1 to 10 mr/hr 10 nr/hr*
5 Instrtment nodule - red light.
5 3.
R-3a 1 to 10 mr/hr 10mr/hr*
5 Instrtsnent nudule - red light.
5 4.
E-3a and E-6a 1 to 10 mr/hr 10 nr/hr*
a)4 Local red light.
b)5 Instrtsnent nodule - red light.
5 5.
Stack RAMa 1 to 10 mr/hr 100 pr/hr*
5 Instrument nodule - red light.
6.
Stack Gasb 10 to 106 cpn 105 egge 5
Instrtsnent module - red light.
7.
Reactor Roan Canf 50 to 5x104 cpn 104 cp#**
a)1 Local audible bell and red light.
1 b)5 Annunciator panel - red light.
c)
Air dsTper closed lights on instrument nodule.
d)5 Instrinnent nodule - red light.
e)3 Annunciator panel - audible horn and red light.
8.
N\\C Critical-3 ity Monitora 1 to 10 nR/hr a) 50 nr/hr - when reactor 6
Audible bell and red light.
personnel are on duty ****
b) 20 nr/hr - during non-duty hours 9.
Water Box Ganma Monitore 0 to 1.0 ma 0.5 ma 5
Red light on instrtsnent nodule
- 10. Main Stack n/a Motor Failure 5 Bell and red light on wall.
Exhaust Fan Abnitor
- 11. gig n/a 0 Cat (Phase I Stack Flow) 5 Bell and red light on wall.
~
(
O O
' to RSD 5-3 4 January 1982 a - Scintillation detector 1 - Reactor R..m b - Proportional detector 2 - Roan 3152 c - G1 detector 3 - Itallway 3101 d - Float activated switch 4 - Prep Area 5 - Control Roan S
- - Loss of signal alann:
Instrunent wodule - blue light
- - Loss of signal a)5 Local audible hom,and red light; Loss of air purp alann: Audible horn PdEe 2/6#T b) White light on instrunent nodule L
5 I ocal yellow light; Los er cipal alann:
White light on instrment nodule
- - Lou te m t alarm:
SYSTIM RA!CE AIAN SEIIOINIS AIAIN ICTIFICATKN 5
3 S
- 12. Stack Particulatec 10 to 10 cpn 2 x 10 cpy Instrunent nodule-red light 5
Pool H 0 Level N/A Loss ofi,6" H O Console-Red light scran indicator 13.
2 2
nonitor d,1 fran pool 3 nnunciator Panel-audible horn A
and red light i
j
RAdIATIC SOUICES DIVISIN 4 January 1982 ItBIRUCTIN lEEER 5-4 OL REACIm MINIMICE PHWRW IM 'IIE AFRRI 'IRIGA REACIm 1.
Purpose. To set forth an organized and systenatic reactor maintenance progran for the AFERI 'IRIGA Reactor and to establish maintenance records that w*ll provide a permanent maintenance history of the reactor systens and auxilit.cy support equipnent.
'2.
Applicability.
'Ihe provisions of this Instruction are applicable to the AFRRI 'IRIGA Reactor and the Reactor Branch Staff.
3.
Cancellation.
RSD Instruction 5-4 " Reactor Maintenance Progran for the AFERI 'IRIGA Reactor," dated 27 March 1981 is hereby cancelled.
4.
Definitions.
a.
Malfunction.
'Ihe failure of a canponent of a reactor systen that will prevent the systen fran either operating in its nornal manner or fran performing its intended function.
b.
Modification.
Any physical change, other than direct replacanent or equivalent substitution, in either the corponents or the design of the reactor systen or its associated equipnent.
c.
Major Modification. Any physical change, in either the corponents or the O
.aesira or the re etor =v=t a, or it
=oci ted e9 ia at ta t itt re9uire
snendnent to the existing Technical Specifications of the Reactor License (R-84) atnd therefore approval by the Nuclear Regulatory Cannission (NEC).
i d.
Minor Modi fication. Any physical change, other than direct replacanent or equivalent substitution, in either the carponents or the design of the reactor systen or its associated equipnent, that will not require an snendnent to the existing technical specifications of the Reactor License (R-84). Minor modifica-tions require notification and concurrence of the RRFSC and are authorized by the PIC.
Minor modifications will be docunented by the Reactor PIC in a Minor Modification Log and reported to the USNIC per 10 GR 50.59 and in the Annual Report.
l e.
Equivalent Substitution. Direct replacanent or substitution of a canpo-nent, subsysten, or systen which does not alter the intended function and does not l
constitute either a major or minor modification. Equivalent substitutions do not l
specifically require notification or concurrence of the HRFSC and are authorized by the Reactor PIC or CSO. Equivalent substitutions nust not involve changes with unreviewed safety questions. Equivalent substitutions will be docunented within the as-built drawings, as appropriate, and in the Maintenance Log, and will be reviewed and initialled by either the Reactor PIC or C90.
5.
Responsibilities. Responsibilities for the reactor maintenance progran are delineated as follows:
g l
RADIETIN SOLKES DIVISIN 4 Jenuary 1982 INSTRUCTIN NGER 5-4 a.
Head, Reactor Branch (Physicist-In-O arge, PIC):
O b
(1) Has authority to approve any change in either the emponents or the d:: sign of the reactor systen or its associated equipnent that does not constitute a major nodification.
(2) Performs periodic inspections to insure that the naintenance sched-ules and procedures are followed, and that all naintenance records are being properly naintained.
(3) Reviews the Malfunction Log quarterly to insure that proper corree-tive measures have been taken.
(4) Prepares doctmentation for proposed major and minor nodifications, and maintains the major and minor modification records / logs, b.
Olef Supervisory Operator (C90):
(1) Has prinary responsibility for inplanentation of the reactor nainte-n2nce program in accordance with the Reactor License (R-84).
(2) Supervises the reactor operators in the performance of all reactor maintenance.
(3) Accmplishes the training of reactor operator trainees in the reac-tor maintenance progran.
O (4) Sup-vises, when necessary, maintenance personnei fran outside the Reactor Branch when working on reactor systens and auxiliary support equipnent.
(5) Maintains current and accurate reactor naintenance record except for minor and major modifications.
(6)
Insures that all changes in the reactor systens are reflected in the es-built drawings.
(7) Schedules preventive maintenance to include the annual shutdown maintenance period.
(8) Reconnends to PIC changes that will enhance the reactor maintenance progran and procedures.
(9) Has authority to approve an equivalent substitution.
c.
Reactor Operator (IO):
(1)
Performs reactor naintenance as directed by the Chief Supervisory Operator.
nV (2)
RADIATIW SOUROS DIVISIW 4 Janu2ry 1982 INS'IELLTIW NUEER 5-4 O
(2)
Inmediately notifies the Gief Supervisory Operator and PIC whenever a malfunction occurs.
(3) Informs the Olef Supervisory Operator and/or PIC whenever mainte-nance on any eaponent of either the reactor or auxiliary systens is required.
(4) Recannends to Olef Supervisory Operator and/or PIC changes that will enhance the reactor maintenance progran and procedures.
Maintenance Progran. He AFRRI 'IRICA Reactor Maintenance Progran is conducted 6.in eagllance with the Technical Specifications of the NEC Reactor License (R-84),
and to insure the safe and reliable operation of the reactor in support of the AFERI research progran.
In order to facilitate the adninistration of the maintenance progran, the reactor systen is divided into cagonent systens.
Likewise, the maintenance progran is divided into three general categories:
- a. Preventive Maintenance.
Consists of maintenance that is scheduled in advance and is accaglished in accordance with the schedule indicated on the Maintenance G art.
b.
Corrective Maintenance.
Consists of maintenance that is non-scheduled and that requires either repairs or calibrations as a result of a malfunction or detection of a marginally operating cagonent, subsysten, or systen.
c.
Modifications.
Consist of major and minor modifications as defined in subparagraphs 4.c. and 4.d., respectively. Modifications are made to the existing O
reactor systens and associated equipment to increase the safety and/or reliability of reactor operations.
7.
Maintenance Records. He AFERI 'IRIGA Reactor maintenance records are nain-tained in eagliance with the Technical Specifications of the NEC Reactor License (R-84), and to provide a permanent history of all maintenance performed on each reactor systen and auxiliary equipnent.
a.
Maintenance Log.
(1) De Maintenance Log will consist of a file systen delineating each major cagonent or systen of the reactor. H e first section will be a list of current camponents in the systen.
Each section will refer to the frequency of inspection, or preventive maintenance, or calibration of the cagonent specified.
Each section will describe the action required or refer to nanuals or files giving such description.
Direct replacanents, modifications, or equivalent substitu-tions to any camonent, subsystan, or systan, and any change in procedura covering calibration or inspection or the frequency of inspection will be appropriately referenced in each systens section.
(2) here will be a space provided in each systen section for a written statenent of actions taken on any cagonent, subsysten,or systen along with the date, signature of the operator ca@leting the action, and a block for the G O's or PIC's initials upon review of the action taken.
(3)
RADIATICW SClB S DIVISIm 4 January 1982 Il&lRUCTIm NthEER 5-4 b.
Malfunction Log.
Consists of a bound notebook with all infonnation pertinent to the reactor systens malfunctions in it.
De entries in the Malfunction Log will be made by the individual discovering the malfunction and will consist of the date the malfunction occurred, the cmponent that malfune-tioned with a description of the malfunction, the corrective action taken, and the initials of the individual.
He C90 or PIC wil review the malfunction statenents and initial the Malfunction Log.
c.
Maintenance Gart. A chart may be used to cover a calendar year depicting the date on which prc~,cntive maintenance is scheduled to be performed for emponents in the systen. D e dates for preventive maintenance are depicted on the chart with an (X). The Maintenance Gart is to be used for infonnal reference only, actual records will be contained within the Maintenance Log. The Mainte-nance Chart may be color coded to highlight the required timing frequency for maintenance.
d.
Modification Records. Consists of all proposed major and minor Modifica-tion Manorandte pertinent to reactor modifications.
These records will be maintained in a current status by the PIC.
e.
As-Built Drawing Records. Consists of all as-built prints of the cmpo-nents of the reactor systens as originally designed and includes any modifications made to these reactor systens.
These records will be maintained in a current status by the C90.
f.
Calibration Data Records. Consists of final data taken during calibra-O tions of the various reactor parameters specified in the Technical Specifications of the Reactor License (R-84).
Rese records will be maintained in a current status by the CSO.
8.
Manuals. The maintenance progran will be accmplished in accordance with the procedures set forth in the Reactor Maintenance Manual and as reemmended in the manufacturers' manuals except where updated or modified based on operational crperience.
9.
Modification Procedures.
A modification wi11 be doctmented, approved and reviewed prior to being accmplished.
The proposed modification will be docu-mented in a " Modification Manorandtm." De Memorandtm will contain the following information:
a.
The purpose of the modification.
b.
A detailed description of the modification to include figures and as-built drawings as desned necessary.
c.
An analysis of the nudification with eipahsis placed on the reactor Technical Specifications, the safety of operation of the reactor, and the safety of personnel.
d.
A Minor Modification Memorandtm will be prepared by the CSO, approved by the PIC and reviewed by the Gief, Radiation Sources Division. A Major Modifica-Q tion Memorandtm will be prepared by the PIC, reviewed by the Gief, Radiation Sources Division, reviewed by the Reactor and Radiation Facility Safety Cmmittee, approved by the Director and approved by the NIC.
(4)
RADIATIW SOlHIS DIVISIW 4 January 1982 INS'IRLUTIN NLM3ER 5-4 O
11.
Reactor Core Maintenance.
He maintenance on the reactor core will be cecmplished in accordance with the following conditions:
a.
Maintenance on the control rods will be performed only when the reactor is in a shutdown condition.
b.
De PIC will insure that the nmber of non-essential personnel in the Reactor Roan will be kept to a mininun when core maintenance is perfomled.
c.
D e core maintenance will be recorded in either the Reactor Operations Log, Maintenance Log, or Malfunction Log,or a cmbination of these, as required.
d.
A control rod will only be manually renoved frcm the reactor core under the following conditions (1) D e reactor will be in a shutdown condition.
(2) A mininun of three ' individuals will be present, and at least two of these individuals will possess an NIC license. One individual will be either the PIC or C90 and possess an NEC Senior Reactor Operator license.
The second individual will possess either an NIC Senior Reactor Operator license or an NEC Reactor Operator license.
(3) One licensed operator will observe the core nuclear instrumentation.
(4) The mininun shutdown margin provided by the renaining control rods l O with the most reactive controi red foily renoved shali be $1.oo (o.2* x/a).
e.
The loading and unloading of the fuel elenents in the reactor core will be teemplished in accordance with RSD Instructi 5-8 " Reactor Core Loading and Unloading Procedures."
P
/
EEH A.
JR.
CAPT, USAF Reactor Branch O ief and Physicist-In-O arge 1
IENAID R.
l MAJ, EN, USA l
Chief, Radiation Sources Division iV l
l (5)
l RADIATI(W SOLBCES DIVISIW 15 March 1982 IISIRUCTIW MbEER 5-5 h
REACICR IEX)! IWER IOISP TERATIGE P!0CHXEES 1.
Purpose.
To set forth the procedures to be followed by the Reactor Branch staff in the operation of the Reator Roan Power Holst.
2.
Applicability.
'Ihe provisions of this Instruction are applicable to the Reactor Branch staff.
3.
Cancellation. He BSD Instruction 5-5, " Reactor Roan Power Holst Operations Procedures," dated 31 March 1981 is hereby cancelled.
p 4.
General.
a.
ne power hoist will not be operated without the pennission of the Physicist-In-O arge (PIC) of the Reactor Branch or his designee.
b.
A mininun of two people will be present during the operation of the power hoist. One of the two people nust be fran the Reactor Branch.
c.
'lhe key to the power hoist circuit breaker lock will rannin secured in the Reactor Branch key box when the power hoist is not in use.
5.
Operation.
a.
'lhe reactor will be in a shutdown condition before electrical power is O
applied to the hoist.
b.
Restraining lines will be attached to all loads, prior to being lifted by the power hoist, to control swinging of the load, and to assist in guiding the load during horizontal novament.
c.
Any equipnent to be used with the hoist for actual operations such as hooks, slings, cables, chains, ete; nust be visually inspected for wear and danage, if acting as load bearing devices, and nust be load tested or certified prior to their being used with the hoist for any operation. The results of the visual inspection and the load testing will be doeurnented in the Reactor Opera-tions Logbook or Maintenance Log as appropriate. 'Ihis paragraph does not apply to the annual hoist load testing by the inspectors if their certified equignent is used.
A d.
While electrical power is applied to the hoist and overhead rails, the following additional adninistrative controls will apply:
(1) 'Ihe personnel in the Reactor Roan will ranain clear of the hoist, load, and overhead power rails. Personnel will not, stand directly under the load for any reason. All personnel should renain as far fran the load as the length of the longest load-bearing cable, if possible.
(2) Tools and poles, longer than 10 feet, will not be raised vertically in the Reactor Roan to include the storage area over the Control Roan.
V l
RADIdTI N SOURCES DIVISIW 15 March 1982 INSTRUCTIW NUWER 5-5 q
(3) The control box will be continuously in the possession of the v
operator when power is applied to the hoist and overhead rails, f.
Before any load is lif ted in the vicinity of the reactor pool, sinulated operations will be conducted in another location by the operator and the proce-dures approved by the PIC or his designee.
g.
Before any load is lifted in the vicinity of the aluninum floor hatch in the Reactor Roan, the areas on the first and second levels beneath the hatch will be secured to ensure all personnel are kept out of areas directly below the load, h.
The power hoist will be load tested and certified periodically by licensed inspectors. Results of the load test will be filed in the maintenance files and 3
the maxinun load rating will be stenciled or marked on the hoist.
- i. The operator shall test the brakes each time a load approaching 10,000 lbs. is handled.
The brakes shall be tested by raising the load a few inches, applying the brakes and checking for slippage,
- j. A load shall not be lowered below the poin where two full wraps of cable renain on the drun.
<4g EPH A.,
T, JR.
/
N,USAF Q
Reactor Branch O lef and Physicist-In-O arge RENAID R. SW3ER MAJ, EN, USA Chief, Radiation Sources Division l
9 D
(2)
o hAIIAT m SOUIGS DIVISIm 27 March 1981 Il6IBUCTIm MMER 5-6 O
REACIGt TERNIm 'IRAINIIG AtO RB@ALIFICATIN PIURAM s
1.
Purpose.
To set forth a reactor operator training progran to insure that candidates for UNC Senior Reactor Operator and Reactor Operator license are properly trained in facility design, operation, maintenance', nuclear theory, and energency procedures applicable to the AFERI 'IRICAMark-F Reactor. To set forth a reactor operator requalification progran, in accordance with 10 GR-55, Appendix A and IAW the "AFRRI Reactor Facility Operator Requalification Progran."
s 2.
Applicability.
De provisions of this instruction are applicable _to the f
Reactor Branch staff and to all operators licensed by USNIC on the AFRRI 'IRIGA Reactor.
l' 3.
Cancellation. RSD Instruction 5-6, " Reactor Operator Training and Requalifi-cation Progran," dated 27 June 1979 is hereby cancelled.
4.
Responsibilities.
He authority to inplanent both the reactor operator training progran and the reactor operator requalification progran is delegated to the Head, Reactor Branch through the Head, Radiation Sources Division.
5.
Training Prograns.
He reactor operator training progran is designed to provide the training for both Senior Operator and Reactor Operator candidates for USN10 operator licenses.
Personnel assigned to the Reactor Branch wilIJ be prestrned to possess a general faniliarity with reactor operations by virtue of O
previous training and experience.
All such personnel will enter the training progran to achieve the desired level of carpetency as a nuclear. reactor operator.
Certain individuals assigned to the Reactor Branch will be ' subsequently provided additional training to enable than to becane a candidate for a USNIC Senior Operator's License.
He reactor operator trainees will follow an organized progran.
He extent of the training progran will be developed in view of the trainees' previous training and experience.
The progran nay include classroan lectures and exaninations, on-the-job training and denonstration, console opert '
tion, and operation of the experimental facilities.
Principally, the " actor t
nuclear theory and radiological safety portions of the progran will con:"t of i
classroan lectures while the renaining portions will be conducted by on-the-job techniques and supplanented by lectures as necessary.
a.
Reactor Operator Training. He reactor operator training will be conduct-
'r ed in accordance with the " Reactor Operato-M;ualification Progran."
his training progran is designed to. provide perrsc~/ previously trained in the basic principles of nuclear reactor operatio% wir i En acceptable faniliarity and operational empetency with the AFRRI-W@. M* st-F Reactor. Carpletion of this course denonstrates ability to operatt t.h..'.ctor and accarplish all operator assigned tasks, without supervision, dding all nomal reactor startups, opera-tions, and shutdowns. In addition, each operator nust be capable of establishing and insuring a safe configuration during any abnomial condition; must deuonstrate faniliarity with the design and control of the reactor necessary for knowledgea~ le o
and empetent operation; nust possess a thorough knowledge of nuclear safety, the possible hazards associated with this facility, and response to the separate f'
levels of alann; nust denonstrate a thorough knowledge of the diTpetives appli-U cable to and the reports required of all operations, t
___._._.,..._.___..._m
~
RADIATIm SOLBCES DIVISI N 27 March 1981 INSTRLCI'Im NUEER 5-6 h
b.
Se for Reactor Operator Training.
The senior reactor operator training will be accmpli::hed in accordance with the " Reactor Operator Requalification Progran." Dis training progran is designed to provide personnel with that depth of knowledge required for supervisory direction, analysis of routine reactor data and solution of problens associated with reactor operation or experinunt handling.
Cmpletion of this course denonstrates empetence to direct the activities of licensed reactor operators in all routine, non-routine, or energency reactor operations to include accmplishnent of required data forms, observance and interpretation of reactor parsneters, and timely response to and solution of abnormal parsretric conditi ns; nust be capable of directing and training other 7
operators and effecting an u: curate and timely analysis of energency indications.
D 6.
Requalification Progran.
De requalfication progran wi11 be conducted in cecordance with the NEC approved AFERI " Reactor Operator Requalification Pr All NIC licensed reactor operators and senior reactor operators are requir
'to participate in the requalification progran.
7.
Reconnendation for Licensing. Upon caTpletion of the required training, the Olef, Reactor branch will determine the level of empetency of the license candidates and forward to the Olef, Radiation Sources Division, a reconnendation for sutmission of the candidate to the USNIC for licensing. De Olef, Radiation S?arces Division will review the reconnendation sutmitted and nake a determination whether or not the candidate will be subnitted to the USNIC for licensing.
If cpproved the candidate will prepare an application either for licensing in cecordance with 10 0R-55.10 or for renewal.. reactor license in accordance with 10 G R-55.33. De application will be coordinated with the Olof, Reactor Branch; O Olef, Radiation Sources Division; and Director, prior to being forwarded to the USNIO.
f
/rh f
EEH TI CAPI', IEAF Reactor Branch O lef and Physicist-In-O arge (effective 13 Oct 1981)
M IKNAID R. SWEER MAI, IN, IEA Olef, Radiation Sources Division C
m
RADIATI N SOURCES DIVISIW 18 March 1981 INS'IMLTIN MAEER 5-7 h
PNEUMTIC 'IRANSFER SYSTENE AND REE EXPERIhENT 'IUBE OPERATIN PIOGIXEES 1.
Purpose.
To set forth the procedures to be followed by the Reactor Branch staff in the operation of the Pneunatic Transfer Systens (PTS), and the Core Experiment Tube (GP).
2.
Applicability.
The provisions of this Instruction are applicable to the Reactor Branch staff and the Radiation Safety Departnent staff.
3.
Cancellation. RSD Instruction 5-7 dated 8 April 1980 is hereby cancelled.
4.
General. All use of the PTS and GP will be under the supervision of a Senior F
Reactor Operator.
hhen not in use, the control key for the PTS will renain secured in the Reactor Branch key box.
5.
Irradiation. No irradiation will be carried out without an approved RUR and, when required, an SWP.
6.
Operator and Monitors.
A licensed operator of the Reactor Branch will operate or directly a.
supervise a trainee in the operation of the PTS and the Gr.
His responsi-bilities include:
(1)
O control panel or GP, as appropriate. Physical operation or direct supervision of the oper (2) Cmnunication with the reactor operator at the console in the reactor control roan.
(3)
Inspection of rabbits to be used to preclude use of cracked or otherwise danaged rabbits.
b.
A nonitor fran the Radiation Safety Department (SAHP) will be present when a retrieval is in progress, and will insure carpliance with applicable Health Physics Standard Operating Procedures of the SAHP.
c.
In all cases the reactor operator at the console in the reactor control roan is responsible for making the appropriate operations log book entries and for coordinating the insertion and retrieval of experiments.
l NOTE:
Itans 7 and 8 apply only to the Pneunatic Transfer Systens.
l
- 7. Aluninun rabbits will be diverted to the hot cell, and therefore can only be i
irradiated in the "A" systen.
l 8.
If the anticipated radiation level of any returned rabbit is greater than 1.0 R/hr at 1 meter fran the receiving station, the following precautions will be taken:
'V l
l
- RADIATIm SOLBQS DIVISICN 18 March 1981 11EI'RLIfrIm NilEER 5-7 Unless experiment requirenecta dictate otherwise, the FTS operator will a.
(
use the renote or auxiliary control unit, b.
All non-essential personnel will exit fran the Radiochenistry Laboratory prior to returining the rabbit.
c.
A radiation survey meter will be set up near the receiving station so that it will be visible fran the renote or auxiliary control unit.
d.
The rabbit will b3 irradiated in the "A" systen and then diverted to the Hot Cell or returned to 11e tenninus.
MJPE:
Itens 9 through 12 apply only to the GP.
9.
Only GP type rabbits will be used with the Gr. GP rabbits will be raised or lowered into the GP through the use of a fishing pole asseTbly which allows the operator to maintain up to approxinately six feet between himself and the retrieved experiment. At the direction of an SRO a plastic rabbit may be sinply dropped into the GP without using the fishing pole asseibly.
10.
Irradiated GP rabbits will be raised near the pool surface, within the GP, for dose rate measurenents by the SAHP monitor. Experiments too active for safe transfer will be returned to a lower portion of the GP and allowed to decay.
- 11. To protect the fishing pole asssibly and the extractor fran undue activa-tion, insertions and retrievals are best performed when the reactor is shut down.
p Normally the extractor will not be lowered into the active core region when the v
power level is greater than 100 watts.
- 12. Open air transfer of a sufficiently " cool" rabbit will be accaTplished only af ter nonessential personnel have cleared the inmediate area.
1
/
- 13. Radiological safety considerations will be coordinate hrough SAHP.
a,a EPH A.
TI CAPP, USAP Reactor Branch Chief and Physicist-In-01arge (effective 13 Oct 1981)
M HCNAID R. !MEER MAJ, EN, USA Qilef, Radiation Sources Division
!V (2)
RAblNTIdi SOLK:ES DIVISICN 27 March 1981 INS'IBUCTI(N NLDBER 5-8 O
L..
REACKR CIEE INDIKi AIO INIMDIN:i Pf00DLEES 1.
Purpose.
To set forth the procedures to be followed by the Reactor Branch staff in the c<nplete loading and unloading of the AFRRI 'IRICA reactor core.
2.
Applicability.
'!he provisions of this instruction are applicable to the Reactor Branch staff, and the Health Physics Division staff.
- 3. Cancellation. RSD Instruction 5-8 dated 14 December 1976 is hereby cancelled.
4.
General.
The reactor core loading and unloading procedures contained herein apply a.
to the preparation phase as well as the actual loading and unloading phases.
These procedures are based on two (2) separate core loadings and one core unloading of the APRRI 'IRICA reactor.
Bqhasis is placed on following the procedures specified herein to insure continuity of operation and retention of experience within the Reactor-Branch.
b.
All activities associated with either the loading or unloading of the reactor core will be recorded in the Reactor Operations Logbook.
c.
The mininun nmber of personnel that will be required is (1)
Physicist-in-01arge (PIC) or his designee, (2) Chief Supervisory Operator (CBO),
O (3) One NRC licensed reactor operator, and (4) Health Physics Division representa-tive.
d.
A daily Startup Checklist will be eagleted prior to the novanent of any l
fuel elenents.
e.
An approved Special Work Pettnit wil be initiated prior to the novenent of cny fuel elenents, if a.nd a.s req,we A. -
f.
If any new fuel elenents are t be used, each elsnent must be inspected when received at AFRRI. Each elanent will be renoved from its shipping container, cleaned, and inspected for visual defects. Length and bow measursnents nust also be nude and recorded. Smears of the elenent cladding for alpha contanination nust be performed by the Health Physics Division representative prior to being handled by Reactor Branch personnel.
g.
If any new themocouple elenents are to be used, a thermocouple calibra-tion will be perfortned. 'I3:e fuel elenent will be placed in a water bath, and Bnf readings will be recorded over the range 20-100 degrees Centrigade.
h.
At no time will more than six (6) new fuel elenents be out of their l
shipping containers and on the reactor roan floor level.
- i. The Physicis t-In-01arge or his designee nust directly supervise all sequences of loading and unloading the reactor core.
V
_ = _ -. -
e RADIATICN SOLRIS DIVISICN 27 March 1981 i
L INTIRUCTICN MMER 5-8
- j. An NIC licensed reactor operator will continuously observe the nuclear instrtunentation att the control console during all movenents of control rods and fuel elenents.
k.
No fuel elenent which has experienced burnup in the core shall be renoved fran the reactor pool unless at least two (2) weeks have transpired since its use in the core.
5.
Nuclear Instrtunentation.
l a.
The following nuclear instrtunentation is the mininun required for a reactor core loading:
(1) Two ionization chambers will be located outside the core shroud, along the core centerline, and adjacent to core positions F-4 and F-12, respec-tively. De readouts for these chasers will be picomuneters, or equivalent.
l (2) One BF3 or fission chenber will be located outside the core shroud, along the core centerline, and adjacent to core position F-8.
'Ihe readout for this chster will be a scaler unit.
b.
The mininun nuclear instrumentation required for the unloading of the reactor core is:
(1) One BF3 or fission chanber will be located outside the core shroud, along the core centerline, and adjacent to core position F-8.
'Ihe readout for this chaser will be a scaler unit.
c.
An operational check of the channels will be Inade as follows prior to the movanent of any fuel elenent.
(1) A neutron source (3-5 curies) will be placed in the neutron source holder, and an increase in the readings will be observed on all channels.
(2) The neutron source will be renoved frcrn the neutron source holder and the readings will be taken and recorded.
(3) Replace the neutron source in the neutron source holder, and then generate a bias curve for the startup channel identified in 5.a.(2) or 5.b. above as appropriate. Record all channel readings with the source. These measurenents will be performed several times in order to obtain reasonable reproducibility.
These readings will be the basis for future calculations of source multiplication only in the loading of a reactor core. The neutron source reading will be the difference between the readings with and without the neutron source in place in the reactor core.
V,.,
Page 2 of 7
RADIATION SOURCES DIVISION 27 March 1981 INSTRUCTION NUMBER 5-8 g
d.
The nuclear instrumentation will be turned on and allowed to stabilize prior to the movement of any fuel elements, or making measurements of source effect.
6.
Core Loading.
A 1/M curve is obtained by plotting the inverse multiplication vs the amount of a.
fuel added (total amount in the core). The inverse multiplication is the ratio of the source reading to the reading with the fuel added. The loeding curve will seldom be a straight line but may be either concave or convex dependent upon the geometry (source-detector distance).
Hence, a number of different channels will yield different predictions of criticality. Since not all channels will agree, a conservative approach will be taken and the smallest number of estimated fuel elements required for criticality will be used to dictate future steps.
b.
The fuel elements will be loaded in accordance with Table 1.
TABLE 1 FUEL LOADING SCHEDULE STEP #
- ELEMENTS REMARKS ADDED TOTAL l
1 4
4 Load four thermocouple elements,2 in the B ring and 2 in the C ring.
2 14 18 Complete loading of B and C rings.
' Load D ring.
3 15 33 4
15 48 Load E ring positions 1,2,4,6,8,9,10,12, 14,16,17,18,20,22 and 24. This loading is designed to complete a compact array around the control rods as well as to fill water gaps.
l 5
9 57 Complete loading of E ring.
6 9
66 Load F ring in positions 1,5,9,13,17,21, 22,23, and 27.
c.
After each step of the fuelloading, perform the following:
l (1) Record readings.
(2) Withdraw control rods 50%
(3) Record readings.
V Page 3 of 7
RADIATION SOURCES DIVISION 27 March 1981 n
INSTRUCTION NUMBER 5-8 L
(4) Withdraw control rods 100E (5) Record readings.
(6) Calculate M,1/M for the step.
(7) Plot 1/M vs # fuel elements.
(8) Plot 1/M vs weight of uranium-235.
(9) Plot 1/M vs control rod position (50% and 100%).
(10) Predict criticalloadings.
(11) Estimate worth of the control rods.
(12) INSERT CONTROL RODS TO FULL "IN" POSITION.
d.
AFRRI-TRIGA Core I(aluminum clad elements) attained criticality with 72 fuel elements, 2811.33 grams uranium-235.
AFRRI-TRIGA Core II (stainless steel clad elements) attained criticality with 69 fuel elements,2630 grams uranium-235.
Continue the loading sequence as detailed below until criticality is obtained, and e.
until the excess reactivity is 40-50 cents:
TABLE I (Continued)
FUEL LOADING SCHEDULE STEP #
- ELEMENTS REMARKS ADDED TOTAL 7
2 68 Load F ring positions 15 s 'd 25.
8 2
70 Load F ring positions 3 and 11.
f.
Prior to loading the core to an operational configuration, the following measure-ments willbe made:
(1) Control rod calibrations using the rod drop techniques.
(2) The worth of fuel elements in the remaining vacancies (E and F ring) vs water, taken one at a time.
(3) Estimate the core configuration for an excess reactivity of approximately
$3.20.
g.
The loading sequence will continue in order to attain a critical configuration with the transient rod in the DOWN position. This is the basis for the excess reactivity r-estimate of approximately $3.20.
V Page 4 of 7
_ ~ - _ - ---
RADIATIN SOUICES DIVISIm 27 March 1981 INSTRUCTIN NLABER 5-8 O
U TABLE I (Continued)
FUEL IIMDI!O SWEDULE STEP #
- EIRENTS IEMARES pun
'IUPAL 9
2 72 Load F ring positions 7 and 15.
10 4
76 Load F ring positions 2, 14, 18, and 29.
Record critical rod Bank position; Calibrate the lower portion of the transient rod (0-25%) via the e
positive-period technique.
11 4
80 Load F ring positions 8, 10, 24, and 30.
Calibrate the middle portion of the transient rod (25-7S%) via the positive-period method.
12 2
82 Load F ring positions 16 and 20, and this should carplete the operational configuration as stated above.
h.
Calibrate the four control rods via the positive-period method, and then O
careute the excess reactivity in the reactor core (K-excess n st not exceed
$5.00).
- i. Carplete the core loading, insuring that the K-excess does not exceed
$5.00.
TABLE I (Continued) f FUEL INDIM3 SWEDULE i
STEP #
- EIBINTS REMARKS AmFn
'IUPAL 13 5
87 Load F ring positions 4, 6, 12, 26, and 28.
j.
Recalibrate the four control rods via the positive-period method, and then caTpute the K-excess reactivity in the reactor core.
j 7.
Core Unloading a.
The reactor core will be unloaded starting with the F ring and ending with the B ring.
b.
The fuel elenents will be individually renoved fran the reactor core, l
identified by serial nuit>er, and placed either in the fuel storage racks or a shipping cask.
l c.
If the fuel elenents are to be loaded into a shipping cask, the follow-l ing actions will be taken in preparing the shipping easks for loading:
rewra LWL1
RADIATION SOURCES DIVISION 27 March 1981 INSTRUCTION NUMBER 5-8 (1) A radiological survey will be made of the shipping cask upon arrival and before it willbe removed from the truck.
(2) The cask will be moved from the truck to the Prep Area.
(3) The hatches, which provide access from the Prep Area to the Reactor Room, willbe opened and the lifting hook to the power hoist lowered to the Prep Area.
(4) The power hoist will be operated in accordance with RSD Instruction 5-5.
(5) The lifting yoke will be attached to the cask and the cask lifted to the Reactor Room.
(6) The lid to the cask will be removed. The cask will be monitored by the Health Physics Division representative while the lid is being removed, to insure that no radioactive materialis inside the cask.
(7) The inside of the cask will be smeared for gross alpha and beta i
contamination.
(8) The inside of the cask will be vacuumed. The inside and outside of the cask willbe washed down. The water drain line on the cask will be checked to insure that it is not blocked. Also verify the operability of the pressure relief valve and the temperature sensing thermocouple.
I (9) If more than seven elements are to be loaded into the cask, it will bc l
necessary to verify that a thermal neutron poison is present in the cask to prevent the loading of a critical mass.
(10) Move the cask by erane from the reactor deck and position the cask in the reactor pool.
d.
Load the cask with up to as many fuel elements as allowed by the license for the cask. If grid index markings are present in the cask, record which fuel element is placed in which grid position.
e.
Lower the lid to the cask into the pool, place the lid on the cask, and secure the lid.
f.
Raise the cask from the pool, drain the water from the cask into the pool, and then dry the cask off. The cask will be monitored while being removed from the pool to l
insure that no radiation hazard exists as a result of a weakness in the shielding in the cask. The cask will be smeared for gross alpha and beta contamination.
i g.
An air sample will be taken from the cask to measure the activity of the air.
The data from all radiological surveys will be recorded.
h.
After the air sample has been taken, observe the temperature and pressure inside 4
the cask until the temperature and pressure reach an equilibrium.
p Page 6 of 7 v
IW>IATIW SW ras DIVISIW 27 March 1981 INSIRLTim NEWBER 5-8
{
1.
Label the cask accordingly and caiplete the appropriate paperwork either for tenporary storage or for transporting..
- j. Move the cask to either a tenporary storage area or to the truck for transporting.
If the cask is to be placed in t rary storage, a criticality monitor nust be available in accordance with 10 70.
.,f[f
- GPT, Reactor Branch Chief and Physicist-In-O arge o
(effective 13 Oct 1981)
IENAID R.
MM, EN, IEA O lef, Radiation Sources Division O
l l
l r
(7)
RADIATIm SOG CES DIVISIN 4 January 1982 Il6IRUCTIN MM3ER 5-9 g
GBCELIS'IS: REACKR STARIUP, REACKR SEUIIDN, WEEHLY NU1 EAR Il6IIDENTATIN SURVEIIIAKE 1.
Purpose.
To set forth and doctsnent the current procedures for reactor startup, reactor shutdown, and instrtsnentation surveillance via the use of checklists.
2.
Applicability.
The provisions of this Instruction pertain to the Reactor Branch staff.
3.
Cancellation. 'Ihis is the initial version of this Instruction, therefore, cancellation of a previous version does not apply.
4.
General. O ecklists/ procedures for reactor startup, reactor shutdown, and nuclear tristrianentation surveillance have been utilized over the operational lifetime of the AFRRI Reactor. 'lhis Instruction provides a means of doctanenting current checklist items and procedures for reactor startup, reactor shutdown, and weekly nuclear instrtsnentation surveillance.
5.
O ecklists.
Oecklists illustrating the current items and procedures for reactor startup, reactor shutdown, and weekly nuclear instrtsnentation surveil-lance are attached as Enclosures 1, 2, and 3, respectively.
Modified or new checklists, upon approval by the PIC and 0 0, will be appropriately attached to O
this Instruction and the superseded checklist will renoved and filed for reference.
n
^
i MEPHA.
TI car, usAP Reactor Branch O lef and Physicist-In-O arge i
ID; AID R. SGER MAJ, EN, USA O lef, Radiation Sources Division nV
- -. -., -.., -...., =... _.
Date Approved:_ M I/
. d %. I.7 M.,
[
PIC/CSO Initials:
O L.
DAILY START-UP CHECKLIST FOR AFRRI-TRIGA REACTOR (RSD INSTRUCTION NO. 5-2)
CHECKLISTNo.
DA TE SUPERVISOR.IN-CHARGE PERFORMED BY OPERA TORS APPROVED BY TIME COMPLETED
- 1. EQUIPMENT ROOM (Rm-3152)
- 1. Stack gas monitor pump and cooling air blower "ON"
- 2. Air compressor pressure (psi)......................................................
- 3. Air compressor water traps D R AI N E D...............................................
- 4. Doors 231, 231 A. 3152 and roof hatch S ECU R ED.......................................
fl. LOBBY AREA Lobby audio alarm tu rned "O F F"...................................................
fil. EQUIPMENT ROOM (Rm.2158)
C 1
- 1. Profilter Differential Pressure..................................................
- 2. Primary discharge pressure (psi)................................................
- 3. Domineraliar flow rates set to 6 gpm............................................
- 4. Stack roughing filter D.P. (inches of water)........................................
- 5. Stack absolute filter D.P. (inches of water).........................................
- 6. Door 2158 S ECU R E D......................................................
- 7. Visual inspection o f a rea.....................................................
- 8. Air compressor water traps drained..............................................
IV. PREPARATION AREA Vis u al inspectio n o f a rea..........................................................
V. REACTOR ROOM (Rm-3161)
- 1. Transient rod air pressu re (p:i)......................................................
- 2. Shielding doors bearing air pressure (psi)..............................................
- 3. Tank water level below full n ark (inches).............................................
- 4. Shield ing doors open or closed.....................................................
- 5. Visual inspection of co re and tank...................................................
- 6. Number of fuel elements and control rods in tank storage
- 7. D oo r 3162 S E C U R E D...........................................................
- 8. Continuous air monitor
( a) O pe rating and tracing......................................................
( b) A l a rm test co m pleted......................................................
(c) High Rad air indication on annunciator pja el.................d...................
- 9. Temp. chart recorder dated........ [4f. F. N.
4. I?
.dM)(..
.s
,/
..h.
- 10. Turn temp. chart recorder "ON". N'.
.5 MO cm)........
(d) DM1 conductivity. List resistivity in M O. cm (must be >.5 MO. cm)..................
(e) DM2 conductivity. List resistivity in MO. cm (must be >.5 MO. cm)...................
- 6. S tac k gas flow rate ( K cfm ).........................................................
- 7. Stack gas monitor
( a ) Backgrou nd ( cpm )..........................................................
( b ) A l a r m ch ec k..............................................................
(c) High alarm set to 105,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
- 8. Stack particulate monitor
( a) Background (cpm )..........................................................
( b ) A lar m chec k..............................................................
3 (c) High alarm set to 2 x 10,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
- 9. Radiation Monitors ALARM POINTS READING ALARM SETTING MONITOR FUNCTIONAL (mR/hr)
(mR/hr)
(a) R.1 500 (b) R-2 10 (c) R 3 10 (d) E.3 10 (e) E-6 10 (f) S 100 (g) NMC 50
- 10. Timer"ON"....................................................................
1 1. TV moni to rs "O N "..............................................................
- 12. Source level on log channel >.5 cos.................................................
l
- 13. Core dolly position (units).........................................................
- 14. Time delay O PE R ATIV E.........................................................
- 15. OPERATIONAL CHANNELS Cal Log Switch Pos No.
Range Switch
% Linear
% Log 1
0.3 watt 2
30 watt 3
300 watt 4
1 kw 5
10 kw 6
3 meg watt
- 16. R od raising in terlock f or Mode i....................................................
- 17. Rod raising interlock for Mode ill...................................................
- 18. Zero power pu l se...............................................................
(a) Carriage movement O (f) Fuel temp 2 O
(b) Fuel temp 1 (g) Safety flux 2 (c) Safety flux 1 (h) Timer (d) Manual (i) Emergency stop (e) Pool H O level (j) Reactor key 2
- 20. Wate r tem pe ratu re ( bu l k )...................................................
- 21. Comments:
V PAGE 2 of 2
Date Approved:_ @ h 4,., $. A PIC/CSO Initials: w/
/ g,g/'
DAILY SHUT DOWN CHECKLIST FOR AFRRI-TRIGA REpFl" g'
(RSD INSTRUCTION No. 5-2)
CHECKLIST No.
L OPERA TORS PERFORMED BY TIME COMPLETED
- 1. REACTOR ROOM (RM-3161)
- 1. A ll rod d r i v es D OW N............................................................
- 2. Carriage lights OFF....
- 3. Temp. chart recorder
... /g.
88.
- 4. Doo r 3162 S E C U R E D...........................................................
- 5. Doo r 3161 lock ed w ith k ey......................................................
fl. EQUIPMENT ROOM (RM-3152)
- 1. Distillation unit discharge valves CLOSE D............................................
- 2. M ill i po re cou pl i ng O P E N.........................................................
- 3. Air d ryer O N or O F F.............................
y
- 4. Doors 231, 231 A, 3152 and Roof Hatch S E CU R ED.....................................
Ill. EQUIPMENT ROOM (RM-2158) l l
- 1. Primary discharge pressure (PSI)...
- 2. Domineralizer flow rates set to 6 gpm
- 3. Visual inspection f or leaks.......................................................
- 4. D oo r 2158 S E C U R E D...........................................................
?
IV. PREPARATION AREA
- 1. ER 2 plug door CONTROL LOCKED: door CLOSED and handwheel PADLOCKED.............
- 2. E R 2 iigh ts O N,and rhoostat at 10%.................... 6...........................
- 3. ER 1 plug door CONTROL LOCKED: door CLOSED and handwheel PADLOCKED.............
l
- 4. E R 1 lights O N, and rhoostat at 10%.................................................
- 5. Visual inspection o f a rea.........................................................
V LOBBY AREA Q
LobbV a la r m aud io M..........................................................
AFRRI FORM 62 (PREVIOUS EDITIONS OF THIS FORM ARE OBEOLETE.)
PAGE 1 of 2 3 SEP 81 Jnclosure 2. to. RSD 5-9
-~
...m
.. ~
o.. >
V/ REACTOR CONTROL ROOM (RM-3160)
- 1. Reactor tank lights and reactor room lights OFF 2.TimerM...................................................................
- 3. TV monitor s M..............................................................-
- 4. Console L OC K E D..............................................................
- 5. Diffuser and secondary pumps O F F.................................................
- 6. Purification and primary pumps O N................................................
- 7. Radiation monitors:
MONITOR READING HIGH-LEVEL ALARM SETTING tmR/hr)
(mR/hr)
(a) R.1 20 (b) R 2 N/A (c) R-3 N/A (d) E-3 N/A s
(e) E 6 N/A (f) S N/A l
I (g) NMC 20 l
l
- 8. COMMENT:
PAGE 2 of 2
Date Approved: J[eyo M fd g 'a
, e e.
ed g
PIC/CSO Initials:
M
[
WEEKLY NUCLEAR INSTRUMENT CHECKLI CHECKLIST No.
DATE PERFORMED BY REVIEWED BY SATISFY OPERATING CONDITIONS
- 1. SAFETY CHANNEL ONE A.
Raise rod -2%. depress and release switch marked HV.;$2 in left hand drawer. observe and reset scram.
B.
Rotate operate switch to zero, check meter for zero. reset scram.
C.
Rotate operate switch to calibrate, check meter for 100 %. reset scram.
- 11. OPERATIONAL CHANNEL HIGH VOLTAGE Depress and hold in switch HV# 1 in left hand drawer. Attempt to raise control rod 111. SAFETY CHANNEL TWO A.
Raise rod ~2%. depress and release switch HV trip test in right hand drawer.
Observe and reset scram...
B.
Rotate operate switch to zero, check meter for zero, reset scram C.
Rotate operate switch to calibrate, check meter for 100 %. reset scram.
MM g
IV. NV.NVT Set pulse ti r on440&sec., satisfy conditions to fire pulse. Insure all rods are down. Using the safety channel two trip tast, achieve indicated percent power to check linear (blue) chart recorder as follows :
- 1. In manual made set 20% on safety channel #2 high flux meter, switch to pulse HI reed 20% on recorder.
Repaint for 40 %. 60 %. 80 % and 100 %. Check scram at 110 % NV reading, reset scram......
2 Check NVTby connecting digital mit meter to board #9 at TP3 (POS) and TP2 (GD)
/Jbt t m\\fbc, and obtaining reading of 490L*4~e99 VDC in manual mode. Switch to pulse mode, insure all rods are down, fire zero powerpulse. Read.964+&& MW-sec on NVTmeter. Reset timer to 0.500 sec g
4 and return to manual mode. Return trip test to zero.............................
V. FUEL TEMPERATURE No.1 Rotate switch to calibrate position observe 100 %. reset scram.
VI. FUEL TEMPERATURE NO.2 Rotate switch to calibrate position observe 100 % on meter, reset scram Vll. WATER LEVEL INDICATOR l
Raise any rod 2%.
1.
In pool, aest side, depress float on water levelindicator......
2.
Obserw scram on console. (scram indication should reset automatically).
Vill. WATER MONITOR BOX Check conductivity at the following points.
- 1. Cell Number 1 (Water Box) List resistivity in MG. cm l
l Conductivity should not be more than 2.0 pmhcsicm,i.e. resistivity should not read < 0.5 MO cm IX. RADIATION MONITOR A.
Test alarm functiens for high level and failure HIGH. Level Monitor Failure Alarm Functional Alarm Functional R.1 R.2 E.3 E.6 NMC B.
Reset Alarms I
l AFRR1 FORM 66 (PREVIOUS EDITIONS OF THIS FORM ARE OBSOLETE.)
3 SEP 81
.