[Federal Register Volume 62, Number 64 (Thursday, April 3, 1997)]
[Notices]
[Pages 15943-15944]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-8546]


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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. 
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 of the 
Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, Attention: Docketing and Services Branch, 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: February 14, 1997, revised March 10, 
1997.
    Brief description of amendment: The amendment revises the Technical 
Safety Requirement for the design features for the cranes in the feed 
facilities and reflects the associated changes to the Safety Analysis 
Report.
    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 change to TSR 2.2.5.2 involves a change to the design 
features of the hoist brakes for the feed facility cranes. These 
changes have no impact on plant effluents and will not result in any 
impact to the environment.
    2. The proposed amendment will not result in a significant increase 
in individual or cumulative occupational radiation exposure.

[[Page 15944]]

    The proposed design change for the brakes will not affect 
individual or cumulative occupational radiation exposure.
    3. The proposed amendment will not result in a significant 
construction impact.
    The proposed change will not result in any 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 change involves a change to the description of the 
safety features on the feed facility cranes. The changes are being made 
to reflect the field configuration of the cranes. The brake design in 
question complies with the requirements of ANSI B30.2-1990 and will 
continue to perform its safety function. As such, the potential of 
occurrence of an evaluated event is unaffected. The consequences of 
previously evaluated accidents are not increased.
    5. The proposed amendment will not result in the possibility of a 
new or different kind of accident.
    The proposed changes revise the design feature for the brakes of 
the feed facility cranes to match the field configuration. The brakes 
meet ANSI B30.2-1990 and will continue to meet their safety feature. 
The change does not create the possibility for a new or different type 
of accident.
    6. The proposed amendment will not result in a significant 
reduction in any margin of safety.
    The brake designs for the cranes comply with the requirements of 
ANSI B30.2-1990. The TSR change is necessary to reflect the field 
configuration of the brakes. The accident analysis is not affected by 
this change. The proposed changes cause no reductions in the margins 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.
    The proposed TSR change is being made to reflect the field 
configuration of the brakes for the feed facility cranes. The 
effectiveness of the safety, safeguards, and security programs is not 
decreased.
    Effective date: Upon issuance of amendment.
    Certificate of Compliance No. GDP-1: Amendment will revise a 
Technical Safety Requirement on crane design and incorporate Safety 
Analysis Report changes.
    Local Public Document Room location: Paducah Public Library, 555 
Washington Street, Paducah, Kentucky 42003.

    Dated at Rockville, MD, this 27th day of March 1997.

    For the Nuclear Regulatory Commission.
Carl J. Paperiello, Director,
Office of Nuclear Material Safety and Safeguards.
[FR Doc. 97-8546 Filed 4-2-97; 8:45 am]
BILLING CODE 7590-01-P