[Federal Register Volume 60, Number 169 (Thursday, August 31, 1995)]
[Notices]
[Pages 45499-45500]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 95-21619]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-295 and 50-304]
Commonwealth Edison Company; Zion Nuclear Power Station, Unit 1
and Unit 2 Environmental Assessment and Finding of No Significant
Impact
The U.S. Nuclear Regulatory Commission (the Commission) is
considering issuance of exemptions from certain requirements of 10 CFR
Part 50, Appendix J, Paragraph III, Leakage Testing Requirements, to
Commonwealth Edison Company (the licensee), for operation of Zion
Nuclear Power Station, Unit Nos. 1 and 2, located in Lake County,
Illinois, in accordance with Facility Operating License Nos. DPR-39 and
DPR-48.
Environmental Assessment
Identification of the Proposed Action
This Environmental Assessment has been prepared to address
potential environmental issues related to the licensee's application
dated August 16, 1995. The proposed action would exempt the licensee
from the requirements of 10 CFR Part 50, Appendix J, which were
discussed in the licensee's request for enforcement discretion dated
August 15, 1995. These exemptions are: (1) Paragraph III.B and
III.D.2.(a), to the extent that a one-time schedular exemption would
permit deferral of certain Type B and C tests for Zion Nuclear Power
Station, Unit 2, until September 15, 1995; (2) Paragraph III.B and
III.D.2.(a), to the extent that a one-time schedular extension would
permit deferral of certain Type B and C tests that can only be
performed with the unit shutdown for Zion Nuclear Power Station, Units
1 and 2, until the next cold shutdown of sufficient duration to perform
the tests, but in any case, prior to the end of the next refueling
outage on each unit, currently planned for the fall of 1995 (Unit 1)
and the fall of 1996 (Unit 2); and (3) Paragraph III.C and III.D, to
the extent that permanent exemptions would be granted due to system and
penetration design.
The Need for the Proposed Action
The current Type B containment leak rate test requirements for Zion
Nuclear Power Station, pursuant to 10 CFR Part 50, Appendix J, Section
III.B and III.D.2.(a) are that local leak rate periodic tests shall be
performed during reactor shutdown for refueling, or other convenient
intervals, but in no case at intervals greater than 2 years. The
current Type C containment leak rate test requirements for Zion Nuclear
Power Station, pursuant to 10 CFR Part 50, Appendix J, Section III.C
and III.D.3 are that local leak rate periodic tests shall be performed
during reactor shutdown for refueling, or other convenient intervals,
but in no case at intervals greater than 2 years. These requirements
are reflected in the Zion Technical Specifications (TS), Paragraph
4.10.1.A.2, as requirements to perform Type B and C containment leak
rate testing in accordance with 10 CFR Part 50, Appendix J and approved
exemptions. The required tests have not been performed on the
penetrations and valves that form the basis for this exemption request.
If a separate forced outage were imposed to perform the Type B and C
testing and operation then resumed until the scheduled refueling
outages, ComEd would be subject to undue hardship or other costs that
result from increased radiological exposure and unit thermal cycling.
If the exemptions the licensee requested in its letter dated August 16,
1995, are granted, the tests would be performed during the upcoming
fall 1995 Unit 1 refueling outage, or during power operation on Unit 2
prior to September 15, 1995, or during the Unit 2 refueling outage in
the fall of 1996, or during any outage of sufficient duration.
Permanent exemptions from the requirement to perform the tests would be
granted for others. The exemptions are needed to allow the licensee to
schedule and perform certain tests and to be permanently exempt from
performing others, which will result in a considerable cost savings,
less radiological exposure and fewer unit thermal cycles with no
adverse impact on public health and safety.
Environmental Impacts of the Proposed Action
The proposed exemptions would not increase the probability or
consequences of accidents previously analyzed and would not affect
facility radiation levels or facility radiological effluents. The
licensee has analyzed the possible leak paths, availability of
isolation valve seal water and penetration pressurization systems,
prior Type A leak test results as they are impacted by leaks from the
types of penetrations and valves in question and the probability of the
sequences of events necessary for significant leakage to occur through
the identified pathways. The licensee discussed these as its basis for
concluding that in spite of the proposed one time and permanent
exemptions the containment leak rates would still be maintained within
acceptable limits. The staff has evaluated the licensee's
justification, and agrees that the combination of the small leak paths
and the presence of the isolation valve seal water system and
penetration pressurization system minimize the probability of a large
leak from the types of penetrations and valves in question and this is
shown by the fact that prior Type A leak tests have not been impacted
by leaks from these types of valves and penetrations. In addition, the
staff finds that the likelihood of occurrence of the sequence of events
necessary to cause leaks from the penetrations and valves is very low.
Accordingly, the Commission has concluded that the exemptions do not
result in a significant increase in the amounts of any effluents that
may be released nor do they result in a significant increase in
individual or cumulative occupational radiation exposure. Therefore,
there are no significant radiological environmental impacts associated
with the proposed exemption.
[[Page 45500]]
With regard to potential nonradiological impacts, the proposed
exemption only involves Type B and C testing of the containment. It
does not affect nonradiological plant effluents and has no other
environmental impact. Accordingly, the Commission concludes that there
are no significant nonradiological environmental impacts associated
with the proposed exemption.
Alternatives to the Proposed Action
Since the Commission has concluded there is no measurable
environmental impact associated with the proposed exemption, any
alternatives with equal or greater environmental impact need not be
evaluated. The principal alternative to this action would be to deny
the request for exemption. Such action would not reduce the
environmental impacts of plant operations.
Alternative Use of Resources
This action does not involve the use of resources not previously
considered in connection with the Nuclear Regulatory Commission's Final
Environmental Statement dated December 1972, related to the operation
of the Zion Nuclear Power Station, Units 1 and 2.
Agencies and Persons Consulted
In accordance with its stated policy, on August 18, 1995, the NRC
staff consulted with the Illinois State Official, Mr. Frank Niziolek;
Head, Reactor Safety Section; Division of Engineering; Illinois
Department of Nuclear Safety; regarding the environmental impact of the
proposed action. The State official had no comments.
Finding of No Significant Impact
Based upon the environmental assessment, the Commission concludes
that the proposed action will not have a significant effect on the
quality of the human environment. Accordingly, the Commission has
determined not to prepare an environmental impact statement for the
proposed exemption.
For further details with respect to this action, see the licensee's
letter dated August 16, 1995, which is 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
located at the Waukegan Public Library, 128 N. County Street, Waukegan,
Illinois.
Dated at Rockville, Maryland, this 25th day of August 1995.
For the Nuclear Regulatory Commission.
George F. Dick,
Acting Director, Project Directorate III-2, Division of Reactor
Projects--III/IV, Office of Nuclear Reactor Regulation.
[FR Doc. 95-21619 Filed 8-30-95; 8:45 am]
BILLING CODE 7590-01-P
