[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
