[Federal Register Volume 60, Number 172 (Wednesday, September 6, 1995)]
[Notices]
[Pages 46319-46321]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 95-22041]



-----------------------------------------------------------------------

[[Page 46320]]


NUCLEAR REGULATORY COMMISSION
[Docket No. 50-302]


Florida Power Co.; Environmental Assessment and Finding of No 
Significant Impact

    The U. S. Nuclear Regulatory Commission (the Commission) is 
considering issuance of an exemption from certain requirements of its 
regulations to Facility Operating License No. DPR-72, issued to Florida 
Power Corporation, (the licensee), for operation of the Crystal River 
Unit 3 Nuclear Generating Plant (CR3), located in Citrus County, 
Florida.

Environmental Assessment

Identification of Proposed Action

    The proposed action is in accordance with the licensee's 
application dated May 19, 1995, as supplemented August 8, 1995, for 
exemption from certain requirements of Title 10 Code of Federal 
Regulations, part 50 (10 CFR part 50), Appendix J, ``Primary Reactor 
Containment Leakage Testing for Water Cooled Power Reactors,'' 
Paragraph III.D.1.(a), relating to Integrated Leak Rate Test (ILRT) 
frequency. The proposed exemption would allow CR3 a one-time interval 
extension for the Type A test (containment integrated leak rate test) 
by approximately 24 months from the spring 1996 refueling outage to the 
spring 1998 refueling outage.

The Need for the Proposed Action

    Pursuant to 10 CFR part 50, Appendix A, ``General Design Criteria 
for Nuclear Power Plants,'' criterion 16, ``Containment design,'' the 
``[r]eactor containment and associated systems shall be provided to 
establish an essentially leak-tight barrier against the uncontrolled 
release of radioactivity to the environment and to assure that the 
containment design conditions important to safety are not exceeded for 
as long as postulated accident conditions require.'' 10 CFR 50.54, 
``Conditions of License,'' paragraph O, states that ``[p]rimary reactor 
containments for water cooled power reactors shall be subject to the 
requirements set forth in Appendix J to this part.'' 10 CFR part 50, 
Appendix J, requires periodic verification by tests of the leak-tight 
integrity of the primary reactor containment and establishes the 
acceptance criteria for such tests. The purposes of the tests are to 
assure that periodic surveillance of reactor containment penetrations 
is performed so that proper maintenance and repairs are made during the 
service life of the containment and leakage through the primary reactor 
containment shall not exceed allowable leakage rate values as specified 
in the technical specifications or associated bases. Paragraph III.D.1 
specifies that a set of three Type A tests is to be performed at 
approximately equal intervals during each 10-year service period. Such 
tests are to be limited to periods when the plant is non-operational 
and secured in the shutdown condition under the administrative controls 
and in accordance with the safety procedures defined in the license.
    For CR3, the next available opportunity for performing the ILRT 
would be in Spring 1996. The licensee requested a one-time interval 
extension for the ILRT by approximately 24 months from the Spring 1996 
refueling outage to the Spring 1998 refueling outage. The licensee 
indicated that approval of its request would save over two million 
dollars and would reduce personnel radiation exposure. The proposed 
action is needed to permit the licensee to defer the ILRT.

Environmental Impacts of the Proposed Action

    The Commission has completed its evaluation of the proposed action 
and concludes that the proposed one-time exemption would not increase 
the probability or consequences of accidents previously analyzed and 
the proposed one-time exemption would not affect facility radiation 
levels or facility radiological effluents.
    In support of its exemption request, the licensee submitted 
information pertaining to Types A, B and C testing history, structural 
capability, and risk assessment.
    Two ILRTs have been performed during the last seven years with 
successful results. There have been no permanent or temporary 
modifications to the containment structure, liner or penetrations since 
the last Type A test, and no future modifications are planned prior to 
the 1998 refueling outage which could adversely affect the Type A test 
results.
    The licensee will continue to be required to conduct the Type B and 
C local leak rate tests which are, in general, the principal means of 
detecting containment leakage paths with the Type A tests confirming 
the Type B and C test results. Types B and C testing history at CR3 
shows that the overall combined as-found leakage has been less than the 
allowed combined leakage rate of 0.6 La (266,431 SCCM) at the 
calculated maximum peak containment pressure as specified in Appendix 
J. The NRC staff considers that these inspections provide the necessary 
level of confidence in the continued integrity of the containment 
boundary. It is also noted that the licensee, as a condition of the 
proposed exemption, will perform the visual containment inspection 
although it is required by Appendix J to be performed only in 
conjunction with Type A tests. The NRC staff considers that these 
inspections, though limited in scope, provide an important added level 
of confidence in the continued integrity of the containment boundary. 
The change will not increase the probability or consequences of 
accidents, no changes are being made in the types or amounts of any 
effluents that may be released offsite, and there is no significant 
increase in the allowable individual or cumulative occupational 
radiation exposure. Accordingly, the Commission concludes that there 
are no significant radiological environmental impacts associated with 
the proposed action.
    With regard to potential nonradiological impacts, the proposed 
action does involve features located entirely within the restricted 
area as defined in 10 CFR Part 20. 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 action.

Alternatives to the Proposed Action

    Since the Commission has concluded there is no significant 
environmental impact associated with the proposed action, any 
alternatives with equal or greater environmental impact need not be 
evaluated. As an alternative to the proposed action, the NRC staff 
considered denial of the proposed action. Denial of the application 
would result in no change in current environmental impacts.
Alternative Use of Resources

    This action did not involve the use of any resources not previously 
considered in the Final Environmental Statements related to operation 
of Crystal River Unit 3, dated May 1973.

Agencies and Persons Consulted

    In accordance with its stated policy, on August 28, 1995, the NRC 
staff consulted with the State of Florida official, Dr. Lyle Jerretti, 
Office of Radiation Control, regarding the environmental impact of the 
proposed action. The State official had no comments.

Finding of No Significant Impact

    The Commission has determined not to prepare an environmental 
impact statement for the proposed exemption. Based upon the foregoing 
environmental 

[[Page 46321]]
assessment, the Commission concludes that the proposed action will not 
have a significant effect on the quality of the human environment.
    For further details with respect to this action, see the request 
for exemption dated May 19, 1995, as supplemented August 8, 1995, which 
are available for public inspection at the Commission's Public Document 
Room, 2120 L Street, NW., Washington, DC and at the local public 
document room located at Coastal Region Library, 8619 W. Crystal 
Street, Crystal River, Florida 32629.

    Dated at Rockville, MD, this 28th day of August 1995.

    For the Nuclear Regulatory Commission,
David B. Matthews,
Director, Project Directorate II-1, Division of Reactor Projects--I/II, 
Office of Nuclear Reactor Regulation.
[FR Doc. 95-22041 Filed 9-5-95; 8:45 am]
BILLING CODE 7590-01-P