[Federal Register Volume 63, Number 169 (Tuesday, September 1, 1998)]
[Notices]
[Pages 46487-46489]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-23456]
-----------------------------------------------------------------------
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,
KY
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
[[Page 46488]]
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, 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: May 13, 1998, revised August 12, 1998.
Brief description of amendment: The amendment proposes to revise
two technical Safety Requirements (TSRs). USEC proposes to revise the
quarterly surveillance for the calibration of the Criticality Accident
Alarm System (CAAS) equipment in the product withdrawal facility to an
annual calibration. This would require a revision to TSR 2.3.4.7. USEC
also proposes to correct a cross reference contained in a Feed Facility
TSR, TSR 2.2.4.4. The current TSR cross references a TSR for the Toll
Transfer and Sampling Facility instead of the one for the Feed
Facilities. The two TSRs contain identical requirements.
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 a calibration frequency and correct
a cross reference 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 changes will not significantly increase any exposure
to radiation. Therefore, the changes will not result in a significant
increase in individual or cumulative radiation exposure.
3. The proposed amendment will not result in a significant
construction impact.
The proposed changes 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 to TSR 2.3.4.7 revises the calibration
frequency for the CAAS equipment. This change is consistent with the
calibration requirements for the other facility CAASs. This change has
no impact on the potential for or occurrence of an accident. TSR
2.2.4.4 is being revised to reflect the appropriate cross reference for
the required action associated with this TSR and has no impact upon
either the potential for an accident or the resulting consequences.
Therefore these changes will not increase the probability of occurrence
or consequence 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 revise a surveillance frequency and
correct an editorial error. 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 changes to the TSRs revise a calibration frequency for
the product withdrawal CAAS and correct a cross reference in a TSR for
the feed facilities and have no impact on the margin of safety.
Therefore, these changes do not decrease 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.
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
[[Page 46489]]
signed by the Director, Office of Nuclear Material Safety and
Safeguards.
Certificate of Compliance No. GDP-1: Amendment will revise TSR
2.3.4.7 to change the calibration frequency from quarterly to annual
and revise TSR 2.2.4.4 to correct a cross reference to another TSR.
Local Public Document Room location: Paducah Public Library, 555
Washington Street, Paducah, Kentucky 42003.
Dated at Rockville, Maryland, this 24th day of August 1998.
For the Nuclear Regulatory Commission.
Carl J. Paperiello,
Director, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 98-23456 Filed 8-31-98; 8:45 am]
BILLING CODE 7590-01-P