[Federal Register Volume 63, Number 229 (Monday, November 30, 1998)]
[Notices]
[Pages 65815-65816]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-31812]


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NUCLEAR REGULATORY COMMISSION

[Docket 70-7001]


Notice of Amendment to Certificate of Compliance GDP-1 for the 
U.S. Enrichment Corporation Paducah Gaseous Diffusion Plant Paducah, 
Kentucky

    The Director, Office of Nuclear Material Safety and Safeguards, has 
made a determination that the following amendment request is not 
significant in accordance with 10 CFR 76.45. In making that 
determination, the staff concluded that: (1) There is no change in the 
types or significant increase in the amounts of any effluents that may 
be released offsite; (2) there is no significant increase in individual 
or cumulative occupational radiation exposure; (3) there is no 
significant construction impact; (4) there is no significant increase 
in the potential for, or radiological or chemical consequences from, 
previously analyzed accidents; (5) the proposed changes do not result 
in the possibility of a new or different kind of accident; (6) there is 
no significant reduction in any margin of safety; and (7) the proposed 
changes will not result in an overall decrease in the effectiveness of 
the plant's safety, safeguards or security programs. The basis for this 
determination for the amendment request is shown below.
    The NRC staff has reviewed the certificate amendment application 
and concluded that it provides reasonable assurance of adequate safety, 
safeguards, and security, and compliance with NRC requirements. 
Therefore, the Director, Office of Nuclear Material Safety and 
Safeguards, is prepared to issue an amendment to the Certificate of 
Compliance for the Paducah Gaseous Diffusion Plant. The staff has 
prepared a Compliance Evaluation Report which provides details of the 
staff's evaluation.
    The NRC staff has determined that this amendment satisfies the 
criteria for a categorical exclusion in accordance with 10 CFR 
51.22(c)(19). Therefore, pursuant to 10 CFR 51.22(b), no environmental 
impact statement or environmental assessment need be prepared for this 
amendment.
    USEC or any person whose interest may be affected may file a 
petition, not exceeding 30 pages, requesting review of the Director's 
Decision. The petition must be filed with the Commission not later than 
15 days after publication of this Federal Register Notice. A petition 
for review of the Director's Decision shall set forth with 
particularity the interest of the petitioner and how that interest may 
be affected by the results of the decision. The petition should 
specifically explain the reasons why review of the Decision should be 
permitted with particular reference to the following factors: (1) The 
interest of the petitioner; (2) how that interest may be affected by 
the Decision, including the reasons why the petitioner should be 
permitted a review of the Decision; and (3) the petitioner's areas of 
concern about the activity that is the subject matter of the Decision. 
Any person described in this paragraph (USEC or any person who filed a 
petition) may file a response to any petition for review, not to exceed 
30 pages, within 10 days after filing of the petition. If no petition 
is received within the designated 15-day period, the Director will 
issue the final amendment to the Certificate of Compliance without 
further delay. If a petition for review is received, the decision on 
the amendment application will become final in 60 days, unless the 
Commission grants the petition for review or otherwise acts within 60 
days after publication of this Federal Register Notice.
    A petition for review must be filed with the Secretary, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemakings and Adjudications Staff, or may be delivered to the 
Commission's Public Document Room, the Gelman Building, 2120 L Street, 
NW, Washington, DC, by the above date.
    For further details with respect to the action see (1) the 
application for amendment and (2) the Commission's Compliance 
Evaluation Report. These items are available for public inspection at 
the Commission's Public Document Room, the Gelman Building, 2120 L 
Street, NW, Washington, DC, and at the Local Public Document Room.
    Date of amendment request: April 24, 1998.
    Brief description of amendment: The amendment proposes to revise 
the Technical Safety Requirements (TSRs) which specify the C-310, C-
315, and C-360 facilities crane design features credited for safety. 
The proposed change will specify the design requirement for the crane 
brakes as opposed to listing the specific type of brake for each

[[Page 65816]]

facility crane. USEC is committing to ANSI B30.2-1990, ``Overhead and 
Gantry Cranes'' for the hoist brakes on the cranes.
    Basis for finding of no significance:
    1. The proposed amendment will not result in a change in the types 
or significant increase in the amounts of any effluents that may be 
released offsite.
    The proposed changes to revise the design requirements for the 
cranes in C-310, C-315, and C-360 have no effect on the generation or 
disposition of effluents. Therefore, the proposed TSR modifications 
will not result in a change to the types or amount of effluents that 
may be released offsite.
    2. The proposed amendment will not result in a significant increase 
in individual or cumulative occupational radiation exposure.
    The proposed TSR revisions will not change or increase maintenance, 
testing or operational requirements for the affected equipment; 
implementation of the revised TSRs will not increase exposure. The 
changes do not relate to controls used to minimize occupational 
radiation exposures. Therefore, the changes will not result in a 
significant increase in individual or cumulative occupational radiation 
exposure.
    3. The proposed amendment will not result in a significant 
construction impact.
    The proposed changes will not result in any building construction, 
therefore, there will be no construction impacts.
    4. The proposed amendment will not result in a significant increase 
in the potential for, or radiological or chemical consequences from, 
previously analyzed accidents.
    The proposed TSR changes involve a change to the description of the 
safety features on the cranes in the withdrawal and toll transfer and 
sampling facilities. The current TSRs specify the type of brakes on the 
cranes. The proposed TSR would require that the brake designs comply 
with the requirements of the standard on cranes (ANSI B30.2-1990). The 
brakes will continue to perform their safety function. The change to 
the design requirements does not increase the probability of occurrence 
or consequences of any postulated accident currently identified in the 
safety analysis report.
    5. The proposed amendment will not result in the possibility of a 
new or different kind of accident.
    The proposed TSR modifications will require the brakes to comply 
with ANSI B30.2-1990. The brakes will continue to perform their safety 
function. The specific type of brake required will no longer be 
specified in the TSR. The proposed changes will not create the 
possibility of a new or different type of equipment malfunction or a 
new or different type of accident.
    6. The proposed amendment will not result in a significant 
reduction in any margin of safety.
    The proposed TSR changes involve a change to the description of the 
brake safety feature. Instead of specifying the type of brake, the TSR 
will commit to a brake design that complies with the requirements of 
the industry standard for cranes (ANSI B30.2-1990). Although the 
previous brake designs complied with the standard, it was not required 
by the TSR. The safety function of the brakes remains unchanged and the 
brakes will continue to perform their safety function. As such, the 
changes do not decrease the margin of safety.
    7. The proposed amendment will not result in an overall decrease in 
the effectiveness of the plant's safety, safeguards or security 
programs.
    Implementation of the proposed changes do not change the safety, 
safeguards, or security programs. Therefore, the effectiveness of the 
safety, safeguards, and security programs is not decreased.
    Effective date: The amendment to Certificate of Compliance GDP-1 
becomes effective 30 days after being signed by the Director, Office of 
Nuclear Material Safety and Safeguards.
    Certificate of Compliance No. GDP-1: Amendment will revise TSRs 
2.1.5.2 and 2.3.5.2 to change the design requirement for the crane 
brakes in the C-310, C-315, and C-360 facilities.
    Local Public Document Room location: Paducah Public Library, 555 
Washington Street, Paducah, Kentucky 42003.

    Dated at Rockville, Maryland, this 18th day of November 1998.

    For the Nuclear Regulatory Commission.
Elizabeth Q. Ten Eyck,
Acting Director, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 98-31812 Filed 11-27-98; 8:45 am]
BILLING CODE 7590-01-P