[Federal Register Volume 62, Number 133 (Friday, July 11, 1997)]
[Notices]
[Pages 37317-37318]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-18210]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-289]
In the Matter of GPU Nuclear Corporation (Three Mile Island
Nuclear Generating Station, Unit 1); Exemption
I
The GPU Nuclear Corporation (the licensee) is the holder of
Facility Operating License No. DPR-50, which authorizes operation of
the Three Mile Island Nuclear Generating Station, Unit 1 (TMI-1). The
license provides that the licensee is subject to all rules,
regulations, and orders of the Nuclear Regulatory Commission (the
Commission) now or hereafter in effect.
The facility consists of a pressurized-water reactor at the
licensee's site located in Dauphin County, Pennsylvania.
II
The Code of Federal Regulations at 10 CFR 70.24, ``Criticality
Accident Requirements,'' requires that each licensee authorized to
possess special nuclear material shall maintain a criticality accident
monitoring system in each area where such material is handled, used, or
stored. Subsection (a)(2) of 10 CFR 70.24 specifies detection and
sensitivity requirements that these monitors must meet. Subsection
(a)(1) also specifies that all areas subject to criticality accident
monitoring must be covered by two detectors. Subsection (a)(3) of 10
CFR 70.24 requires licensees to maintain emergency procedures for each
area in which this licensed special nuclear material is handled, used,
or stored and provides (1) that the procedures ensure that all
personnel withdraw to an area of safety upon the sounding of a
criticality accident monitor alarm, (2) that the procedures must
include drills to familiarize personnel with the evacuation plan, and
(3) that the procedures designate responsible individuals for
determining the cause of the alarm and placement of radiation survey
instruments in accessible locations for use in such an emergency.
Subsection (d) of 10 CFR 70.24 states that any licensee who believes
that there is good cause why it should be granted an exemption from all
or part of 10 CFR 70.24 may apply to the Commission for such an
exemption and shall specify the reasons for the relief requested.
III
By letter dated February 7, 1997, as supplemented March 26 and June
5, 1997, GPU Nuclear Corporation
[[Page 37318]]
requested an exemption from 10 CFR 70.24(a). The Commission technical
staff has reviewed the licensee's submittal and has determined that
inadvertent criticality is not likely to occur in special nuclear
materials handling or storage areas at TMI-1. The quantity of special
nuclear material other than fuel that is stored on site is small enough
to preclude achieving a critical mass.
The purpose of the criticality monitors required by 10 CFR 70.24 is
to ensure that if a criticality were to occur during the handling of
special nuclear material, personnel would be alerted to that fact and
would take appropriate action. Although the staff has determined that
such an accident is not likely to occur, the licensee has radiation
monitors, as required by General Design Criterion 63, in fuel storage
and handling areas. These monitors will alert personnel to excessive
radiation levels and allow them to initiate appropriate safety actions.
The low probability of an inadvertent criticality together with the
licensee's adherence to General Design Criterion 63 constitute good
cause for granting an exemption to the requirements of 10 CFR 70.24(a).
IV
The Commission has determined that, pursuant to 10 CFR 70.14, this
exemption is authorized by law, will not endanger life or property or
the common defense and security, and is otherwise in the public
interest; therefore, the Commission hereby grants the following
exemption:
The GPU Nuclear Corporation is exempt from the requirements of 10
CFR 70.24(a) for TMI-1.
Pursuant to 10 CFR 51.32, the Commission has determined that the
granting of this exemption will have no significant impact on the
quality of the human environment (62 FR 36084).
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 3rd day of July 1997.
For the Nuclear Regulatory Commission.
Frank J. Miraglia,
Acting Director, Office of Nuclear Reactor Regulation.
[FR Doc. 97-18210 Filed 7-10-97; 8:45 am]
BILLING CODE 7590-01-P
