[Federal Register Volume 63, Number 198 (Wednesday, October 14, 1998)]
[Notices]
[Pages 55151-55152]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-27507]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-313 and 50-368]


Entergy Operations, Inc. (Arkansas Nuclear One, Units 1 and 2); 
Exemption

I

    Entergy Operations, Inc., (the licensee) is the holder of Facility 
Operating License Nos. DPR-51 and NPF-6, which authorize operation of 
Arkansas Nuclear One, Units 1 and 2. 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 at the 
licensee's site located in Pope County, Arkansas.

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 ANO-1 and 
ANO-2 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 ANO-1 and ANO-2, and has determined that it is 
extremely unlikely for such an accident to occur if the licensee meets 
the following seven criteria:
    1. Only one new 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 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 October 31, 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 the 
applicable criteria are satisfied for ANO-1 and ANO-2. Therefore, the 
staff has determined that it is extremely unlikely for an inadvertent 
criticality to occur in SNM handling or storage areas at ANO-1 and ANO-
2.
    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

[[Page 55152]]

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, 
constitute good cause for granting an exemption from 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 Entergy Operations, 
Inc., an exemption from the requirements of 10 CFR 70.24 for ANO-1 and 
ANO-2.
    Pursuant to 10 CFR 51.32, the Commission has determined that the 
granting of this exemption will have no significant impact on the 
environment (63 FR 51380).
    This exemption is effective upon issuance.

    Dated at Rockville, Maryland, this 6th day of October 1998.
    For the Nuclear Regulatory Commission.
Roy P. Zimmerman,
Acting Director, Office of Nuclear Reactor Regulation.
[FR Doc. 98-27507 Filed 10-13-98; 8:45 am]
BILLING CODE 7590-01-P