[Federal Register Volume 63, Number 24 (Thursday, February 5, 1998)]
[Notices]
[Pages 5973-5974]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-2854]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-352]
Philadelphia Electric Company (Limerick Generating Station, Unit
1); Exemption
I
The Philadelphia Electric Company (the licensee) is the holder of
Facility Operating License No. NPF-39, which authorizes operation of
the Limerick Generating Station (LGS), Unit 1. The license provides,
among other things, that the licensee is subject to all rules,
regulations, and orders of the Commission now or hereafter in effect.
The facility consists of two boiling-water reactors at the
licensee's site located in Montgomery and Chester Counties,
Pennsylvania.
II
Section 70.24 of Title 10 of the Code of Federal Regulations,
``Criticality Accident Requirements,'' requires that each licensee
authorized to possess special nuclear material (SNM) shall maintain a
criticality accident monitoring system in each area where such material
is handled, used, or stored. Subsections (a)(1) and (a)(2) of 10 CFR
70.24 specify 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 SNM is
handled, used, or stored and provides that: (1) The procedures ensure
that all personnel withdraw to an area of safety upon the sounding of a
criticality accident monitor alarm, (2) the procedures must include
drills to familiarize personnel with the evacuation plan, and (3) 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 (b)(1) of
10 CFR 70.24 requires licensees to have a means to identify quickly
personnel who have received a dose of 10 rads or more. Subsection
(b)(2) of 10 CFR 70.24 requires licensees to maintain personnel
decontamination facilities, to maintain arrangements for a physician
and other medical personnel qualified to handle radiation emergencies,
and to maintain arrangements for the transportation of contaminated
individuals to treatment facilities outside the site boundary.
Paragraph (c) of 10 CFR 70.24 exempts Part 50 licensees from the
requirements of paragraph (b) of 10 CFR 70.24 for SNM used or to be
used in the reactor. Paragraph (d) of 10 CFR 70.24 states that any
licensee who believes that there is good cause why he 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
The SNM that could be assembled into a critical mass at LGS, Unit
1, is in the form of nuclear fuel; the quantity of SNM other than fuel
that is stored on site in any given location is small enough to
preclude achieving a critical mass. The Commission's technical staff
has evaluated the possibility of an inadvertent criticality of the
nuclear fuel at LGS, Unit 1, and has determined that it is extremely
unlikely for such an accident to occur if the licensee meets the
following seven criteria:
1. Only three new fuel assemblies are allowed out of a shipping
cask or storage rack at one time.
2. The k-effective does not exceed 0.95, at a 95% probability, 95%
confidence level in the event that the fresh fuel storage racks are
filled with fuel of the maximum permissible U-235 enrichment and
flooded with pure water.
3. If optimum moderation occurs at low moderator density, then the
k-effective does not exceed 0.98, at a 95% probability, 95% confidence
level in the event that the fresh fuel storage racks are filled with
fuel of the maximum permissible U-235 enrichment and flooded with a
moderator at the density corresponding to optimum moderation.
4. The k-effective does not exceed 0.95, at a 95% probability, 95%
confidence level in the event that the spent fuel storage racks are
filled with fuel of the maximum permissible U-235 enrichment and
flooded with pure water.
5. The quantity of forms of special nuclear material, other than
nuclear fuel, that are stored on site in any given area is less than
the quantity necessary for a critical mass.
6. Radiation monitors, as required by General Design Criterion 63,
are provided in fuel storage and handling areas to detect excessive
radiation levels and to initiate appropriate safety actions.
7. The maximum nominal U-235 enrichment is limited to 5.0 weight
percent.
By letter dated December 23, 1997, the licensee requested an
exemption from 10 CFR 70.24. In this request the licensee addressed the
seven criteria given above. The Commission's technical staff has
reviewed the licensee's submittals and has determined that LGS, Unit 1
meets the applicable criteria. Criteria 2 and 3 are not applicable to
LGS, Unit 1 since it has no fresh fuel storage racks, for prevention of
inadvertent criticality; therefore, the staff has determined that it is
extremely unlikely for an inadvertent criticality to occur in SNM
handling or storage areas at LGS, Unit 1.
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
SNM, personnel would be alerted to that fact and would take appropriate
action. The staff has determined that it is extremely unlikely that
such an accident could occur; furthermore, 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, constitutes 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
[[Page 5974]]
in the public interest. Therefore, the Commission hereby grants the
Philadelphia Electric Company, an exemption from the requirements of 10
CFR 70.24(a) for Limerick Generating Station, Unit 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 (63 FR 4497).
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 30th day of January 1998.
For the Nuclear Regulatory Commission.
Samuel J. Collins,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 98-2854 Filed 2-4-98; 8:45 am]
BILLING CODE 7590-01-P