IE Circular No. 80-21, Regulation of Refueling Crews
SSINS No.: 6820
Accession No.:
8006190081
IEC 80-21
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555
September 10, 1980
IE Circular No. 80-21: REGULATION OF REFUELING CREWS
Description of Circumstances:
Recent inspections of refueling activities indicate that some licensees have
misinterpreted the regulatory requirements applicable to fuel handling
activities. Therefore, it appears appropriate to identify those specific
regulatory requirements that are applicable to core alterations which
include reactivity manipulations that may result from the handling of fuel
elements, control rods, etc.
A. 10 CFR Requirements
1. 10 CFR 50.2(f) and 10 CFR 55.4:
"Controls" when used with respect to a nuclear reactor means
apparatus and mechanisms, the manipulation of which directly
affect the reactivity or power level of the reactor.
2. 10 CFR 50.54(i):
Except as provided in 55.9 of this chapter, the licensee shall not
permit the manipulation of the controls of any facility by anyone
who is not a licensed operator or senior operator as provided in
Part 55 of this chapter.
3. 10 CFR 55.3:
No person may perform the function of an operator as defined in
this part except as authorized by a license issued by the
Commission;
4. 10 CFR 55.4:
"Operator" is any individual who manipulates a control of a
facility. An individual is deemed to manipulate a control if he
directs another to manipulate a control.
"Senior Operator" is any individual designated by a facility
licensee under Part 50 of this chapter to direct the licensed
activities of licensed operators.
5. 10 CFR 55.9:
Nothing in this part shall be deemed to require a license for:
a. An individual who manipulates the controls of a research or
training reactor as part of his training as a student in a
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IEC 80-21
September 10, 1980
Page 2 of 3
nuclear engineering course under the direction and in the presence
of a licensed operator or senior operator;
b. An individual who manipulates the controls of a facility as a part
of his training to qualify for an operator license under this part
under the direction and in the presence of a licensed operator or
senior operator.
B. Technical Specifications
Standard Technical Specifications require that all core alterations be
directly supervised by either a Licensed Senior Reactor Operator or
Senior Reactor Operator limited to fuel handling, who has no other
concurrent responsibilities during this operation. The NRC interprets
the term "directly supervised" to mean that the SRO is supervising the
core alterations from the refueling deck.
We note that the Licensed Senior Reactor Operator limited to fuel
handling classification was developed for specialized fuel handling
crews. In this case an individual identified as a Refueling Foreman is
responsible for refueling activities subject to the following
provisions:
1. The foreman shall have a Senior Operator's License limited to the
fuel handling duties.
2. The foreman shall directly supervise (from the refueling deck) the
movement of fuel in and out of the reactor.
3. The unlicensed members of the crew shall participate in
appropriate facility administered training programs and be
facility certified to perform their duties.
4. Direct communication will be maintained with a licensed individual
in the control room when fuel movements over the core are being
made.
5. The foreman will exercise indirect supervision over all other fuel
handling operations.
Based on the NRC regulations delineated in Item A above, the individual
manipulating the fuel-handling equipment over the reactor must be an NRC
Licensed Reactor Operator (RO) unless the facility Technical Specifications
include provisions for the operation to be supervised by an SRO or SRO
limited to fuel-handling as described in Item B. During any core alteration,
a licensed individual must also be observing reactivity monitors in the
Control Room with appropriate communications established with personnel on
the fuel handling equipment. In addition, personnel participating directly
in the core alternations must meet the qualification and training
requirements committed to in the FSAR or fuel loading application, i.e.,
ANSI N18.1-1971 or ANSI/ANS 3.1-1978.
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IEC 80-21
September 10, 1980
Page 3 of 3
Recommended Action for Licensee Consideration
Our routine inspection program for refueling activities is based on the
above NRC requirements. Therefore, we recommend that all reactor licensees
review procedures and practices to assure that the individuals responsible
for and participating in refueling activities are in conformance with the
above requirements.
No written response to this Circular is required. If you require additional
information with regard to this subject, please contact this office.
Page Last Reviewed/Updated Thursday, March 25, 2021