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What is the hierarchy of authority per TS?
The following specific organizational levels and responsibilities shall exist.
a. President (Level 1): The President of Reed College is responsible for the facility license
and represents Reed College.
b. Director (Level 2): The Director reports to the President of Reed College via the Dean
of the Faculty, and is accountable for ensuring that all regulatory requirements, including
implementation, are in accordance with all requirements of the U.S. NRC and the Code of
Federal Regulations.
c. Reactor Operations Manager and Supervisor(s) (Level 3): The Reactor Operations
Manager reports to the Director and is responsible for directing the activities of the reactor
staff and for the day-to-day operation and maintenance of the reactor. The Supervisor(s)
report to the Reactor Operations Manager.
d. Operating Staff - Reactor Operators and Senior Reactor Operators (Level 4): The Reactor
Operators (RO) and Senior Reactor Operators (SRO) report to the Supervisor(s), Reactor
Operations Manager, and the Director, and are primarily involved in the manipulation of
reactor controls, monitoring of instrumentation, and operation and maintenance of reactor-
related equipment.
e. Radiation Safety Officer: The Radiation Safety Officer reports to the President of Reed
College via the Vice President and Treasurer and is responsible for directing health physics
activities including implementation of the radiation safety program. The Radiation Safety
Officer shall communicate with the Reactor Director regarding health physics issues.
How do Tech Specs differ from the Admin Proc?
What are the main differences between the two?
Describe the role and responsibilities of the: President
Describe the role and responsibilities of the: Dean of Faculty
Describe the role and responsibilities of the: VP and Treasurer
Describe the role and responsibilities of the: RSO
Describe the role and responsibilities of the: Director
Describe the role and responsibilities of the: ROM
Describe the role and responsibilities of the: Soupervisors
Describe the role and responsibilities of the: ROs and Technicians
Discuss Staffing when reactor is not secured
○ Give a definition of “Reactor Secured”
The minimum staffing when the reactor is not secured shall be:
1. A licensed reactor operator in the control room;
2. A second person present in the reactor facility able to scram the reactor and summon
help;
3. If neither of these two individuals is an SRO, a designated SRO shall be readily
available on call. “Readily available on call” means an individual who:
a) has been specifically designated and the designation known to the operator on
duty,
b) can be contacted quickly by the operator on duty, and
c) is capable of getting to the reactor facility within 15 minutes.
b. A list of reactor facility personnel by name and telephone number shall be readily available
in the control room for use by the operator. The list shall include:
1. Reactor Director;
2. Reactor Operations Manager;
3. Supervisor;
4. Radiation Safety Officer; and
5. At least one other person who is a licensed SRO.
Events which require the presence of the SRO
Initial start-up and approach to power of the day or following significant changes
(>$0.25) to the core;
2. All fuel or control rod relocations in the reactor core;
3. Maintenance on any reactor safety system;
4. Recovery from unscheduled reactor scram or significant power reduction; and
5. Relocation of any in-core experiment or irradiation facility with a reactivity worth greater than one dollar.
Discuss the purpose of the ROC
The operation of the ROC shall be in accordance with written procedures including provisions for:
a. Meeting frequency: not less than once per calendar year.
b. Quorums: a group consisting of at least half of the voting members, of which the operating staff (i.e. the director and anyone who reports to that person) does not constitute a majority.
c. Use of subcommittees.
d. Review, approval, and dissemination of minutes.
Define “review” and “audit”
Review: An examination of records, procedures, or other documents prior to implementation
from which appropriate recommendations are made.
Audit: A qualitative examination of records, procedures, or other documents after
implementation from which appropriate recommendations are made.
Discuss the composition and qualifications of the ROC
The ROC shall have at minimum 3 members, at least two of whom are knowledgeable in fields
that relate to physics and nuclear safety. The Dean of the Faculty, the Reactor Director, and the
campus Radiation Safety Officer shall be voting members. Additional voting members shall be
added at the President’s discretion.
Discuss the basic review and audit procedures that the ROC performs
The Reactor Operations Committee (ROC) shall have primary responsibility for review and audit of the safety aspects of reactor facility operations, and to assure that the facility is operated in a manner consistent with public safety and within the conditions specified in the facility license. Minutes, findings, or reports of the ROC shall be presented to the President (Level 1) and the Director (Level 2) within ninety days of completion.
The ROC, or a subcommittee thereof, shall audit reactor operations at least annually. The annual
audit shall include at least the following:
a. Facility operations for conformance to these TS and applicable license conditions;
b. The requalification program for the operating staff;
c. The results of action taken to correct deficiencies that may occur in the reactor facility
equipment, systems, structures, or methods of operation that affect reactor safety; and
d. The Emergency Plan and implementing procedures.
The responsibilities of the ROC, or designated subcommittee thereof, include, but are not limited
to, the following:
a. Review determinations that proposed changes in equipment, systems, tests, experiments or
procedures are allowed without prior authorization by the U.S. NRC;
b. Review new procedures and substantive changes to existing procedures;
c. Review proposed changes to the TS or license;
d. Review violations of TS, license, or violations of internal procedures or instructions having
safety significance;
e. Review operating abnormalities having safety significance;
f. Review events from reports required in Section 6.6.1 and 6.7.2 of these TS;
g. Review and approve new experiments under Section 6.5 of these TS; and
h. Review audit reports.
What procedures are we required to have?
Written operating procedures shall be adequate to ensure the safe operation of the reactor, but
shall not preclude the use of independent judgement and action if the situation requires. Operating
procedures shall be in effect and used for the following:
a. Startup, operation, and shutdown of the reactor;
b. Fuel loading, unloading, and movement within the reactor;
c. Maintenance of major components of systems that could have an effect on reactor safety;
d. Surveillance checks, calibrations, and inspections required by TS or those that have an
effect on reactor safety;
e. Radiation protection;
f. Administrative controls for operations and maintenance and for the conduct of irradiations
and experiments that could affect reactor safety or core reactivity;
g. Implementation of required plans, such as the Emergency and Security plans; and
h. Use, receipt, and transfer of byproduct material held under the reactor license.
Substantive changes to the above procedures shall be made only after review and approval by the
ROC. Non-substantive changes shall be reviewed and approved prior to implementation by the
Director or Reactor Operations Manager.
Temporary deviations from the procedures may be made by the responsible SRO when the
procedure contains errors or in order to deal with special or unusual circumstances or
conditions. Such deviations shall be documented and reported by the next working day to the
Director or Reactor Operations Manager.
Who approves experiments, operations, facility changes, etc.? How?
a. Approved experiments shall be carried out in accordance with established and approved procedures.
b. All new experiments or classes of experiments shall be reviewed and approved by the ROC.
c. Substantive changes to previously approved experiments will be made only after review by
the ROC and approval in writing by the Director or Reactor Operations Manager.
d. Minor changes that do not significantly alter the experiment may be approved by a
Supervisor, Reactor Operations Manager, or Director.
What records are we required to retain: for at least 5 years
Normal reactor operation
Principal maintenance activities
Reportable occurrences
Surveillance activities required by TS
reactor facility radiation and contamination surveys
experiments performed with the reactor
fuel inventories, receipts, and shipments
aproved changes to the operating procedures
ROC meetings and audit reports
What records are we required to retain: for the duration of the requal cycle
Records of retraining and requaliication of licensed reactor operators and senior reactor operators shall be retained for at least one complete requalification cycle and maintained at all times the individual is employed or until the certification is renewed. For the purpose of the tech spec, the certification is an NRC issued operator license.
What records are we required to retain: lifetime of the facility
Gaseous and liquid radioactive effluents released to the environs
Offsite environmental monitoring surveys
Radiation exposures for all personell monitored
Drawings of the reactor facility
reviews and reports pertaining to a violation of the safety limit, limiting safety system setting, or LCO
What actions must be taken in the case of Safety Limit or other Tech Spec violations?
6.6.1 Actions to Be Taken in Case of Safety Limit Violation
In the event the safety limit is exceeded:
a. The reactor shall be shut down and reactor operation shall not be resumed until authorized by the NRC.
b. An immediate notification of the occurrence shall be made to the Director, the Chair of theROC, and the President of Reed College.
c. A report shall be prepared and reviewed by the ROC. The report shall describe the following:
1. Applicable circumstances leading to the violation including, when known, the cause and contributing factors;
2. Effects of the violation upon reactor facility components, systems, or structures and on the health and safety of personnel and the public; and
3. Corrective action to be taken to prevent recurrence.
6.6.2 Actions to Be Taken in the Event of an Occurrence of the Type Identified in Section 6.7.2 Other than a Safety Limit Violation
For all events that are required by regulation or TS to be reported to the U.S. NRC within 24 hours under Section 6.7.2, except a safety limit violation, the following actions shall be taken:
a. The reactor shall be shut down and the Director or Reactor Operations Manager and ROC chair notified;
b. Operations shall not resume unless authorized by the Director or Reactor Operations Manager;
c. The ROC shall review the occurrence at or before their next scheduled meeting; and
d. A report shall be submitted to the US NRC in accordance with TS 6.7.2.
How quickly must those actions be taken? (safety limit violation)
By SOP 85:
Notify NRC, Director/ROM, President of Reed, and ROC chair within 1 hour (required by regulatory bodies)
Notify ROC and public affairs within 24 hours
Report to NRC within 14 days (Required by regulatory bodies)
for safety limit violation Are facility procedures different from Tech Specs?
Demonstrate filling out an NRC Notification form
Bonus to be redistributed
In addition to the requirements of applicable regulations, and in no way substituting therefor, the Director shall report to the U.S. NRC as follows:
a. A report not later than the following working day by telephone and confirmed in writing by facsimile to the U.S. NRC Headquarters Operations Center, to be followed by a written report that describes the circumstances of the event within 14 days to the Document Control Desk, U.S. NRC, Washington DC, of any of the following:
1. Violation of the safety limit;
2. Release of radioactivity from the site above allowed limits;
3. Operation with actual safety system settings from required systems less conservative than the limiting safety system setting;
4. Operation in violation of limiting conditions for operation unless prompt remedial action is taken as permitted in Sec. 3;
5. A reactor safety system component malfunction that renders or could render the reactor safety system incapable of performing its intended safety function. If the malfunction or condition is caused by maintenance, then no report is required;
6. An unanticipated or uncontrolled change in reactivity greater than one dollar. Reactor trips resulting from a known cause are excluded;
7. Abnormal and significant degradation in reactor fuel or cladding, or both, coolant boundary, or confinement boundary open (excluding minor leaks) where applicable; or
8. An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or could have caused the existence or development of an unsafe condition with regard to reactor operations.
b. A report within 30 days in writing to the Document Control Desk, U.S. NRC, Washington DC, of:
1. Permanent changes in the facility organization involving Level 1-2 personnel; or
2. Significant changes in the transient or accident analyses as described in the Safety Analysis Report.