[Federal Register Volume 62, Number 198 (Tuesday, October 14, 1997)]
[Notices]
[Pages 53352-53353]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-27085]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-266 and 50-301]
Wisconsin Electric Power Company; (Point Beach Nuclear Plant,
Unit Nos. 1 and 2); Exemption
I
Wisconsin Electric Power Company (the licensee) is the holder of
Facility Operating License Nos. DPR-24 and DPR-27, which authorize
operation of the Point Beach Nuclear Plant, Units 1 and 2,
respectively. The licenses provide, 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 pressurized-water reactors located at
the licensee's site in Manitowoc County, Wisconsin.
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
[[Page 53353]]
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(2) also specifies that all areas subject to criticality
accident monitoring must be covered by monitoring devices.
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 (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. Subsection (c) of 10 CFR 70.24 exempts Part
50 licensees from the requirements of subsection (b) of 10 CFR 70.24
for special nuclear material used or to be used in the reactor.
Subsection (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 special nuclear material that could be assembled into a
critical mass at Point Beach Nuclear Plant is in the form of nuclear
fuel; the quantity of special nuclear material other than fuel that is
stored on site is small enough to preclude achieving a critical mass.
The Commission technical staff has evaluated the possibility of an
inadvertent criticality of the nuclear fuel at Point Beach Nuclear
Plant and has determined that such an accident cannot occur if the
licensee meets the following seven criteria:
1. Only one new fuel assembly is 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
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 Point Beach Nuclear Plant
General Design Criterion 18 which is analogous to 10 CFR part 50,
Appendix A, 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 weight
percent.
By letter dated June 7, 1997, Wisconsin Electric Power Company
requested an exemption from 10 CFR 70.24. In this exemption request the
licensee addressed the seven criteria given above. The Commission
technical staff has reviewed the licensee's submittal and has
determined that Point Beach Nuclear Plant, Units 1 and 2, meets the
criteria for prevention of inadvertent criticality; therefore, the
staff has determined that it is extremely unlikely for an inadvertent
criticality to occur in special nuclear materials handling or storage
areas at Point Beach Nuclear Plant.
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. The staff has determined that it is
extremely unlikely that such an accident could occur; furthermore, the
licensee has radiation monitors, as required by Point Beach Nuclear
Plant's General Design Criterion 18, in fuel storage and handling
areas. Specifically, Point Beach Nuclear Plant's General Design
Criterion 18 requires ``Monitoring and alarm instrumentation shall be
provided for fuel and waste storage and associated handling areas for
conditions that might result in loss of capability to remove decay heat
and to detect excessive radiation levels.'' 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 Point Beach
Nuclear Plant's General Design Criterion 18 constitute good cause for
granting an exemption to the requirements of 10 CFR 70.24.
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 Wisconsin
Electric Power Company an exemption from the requirements of 10 CFR
70.24 for the Point Beach Nuclear Plant.
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 45883).
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 6th day of October 1997.
For the Nuclear Regulatory Commission.
Samuel J. Collins,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 97-27085 Filed 10-10-97; 8:45 am]
BILLING CODE 7590-01-P