[Federal Register Volume 64, Number 129 (Wednesday, July 7, 1999)]
[Notices]
[Pages 36722-36724]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 99-17193]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. STN 50-454, STN 50-455]


Commonwealth Edison Company; Byron Station, Units 1 and 2; 
Environmental Assessment and Finding of No Significant Impact

    The U.S. Nuclear Regulatory Commission (the Commission) is 
considering issuance of amendments to Facility Operating License Nos. 
NPF-37 and NPF-66, issued to Commonwealth Edison Company (ComEd, the 
licensee) for operation of Byron Station, Units 1 and 2, located in 
Ogle County, Illinois.

Environmental Assessment

Identification of the Proposed Action

    The proposed amendments would delete license conditions which have 
been satisfied, revise others to delete parts which are no longer 
applicable or to revise references, and make editorial changes.
    The proposed action is in accordance with the licensee's 
application dated March 14, 1997.

The Need for the Proposed Action

    The NRC, as part of the original licensing process or subsequent 
licensing actions, may impose certain conditions on the license. The 
conditions are listed as part of an attachment to the license. In many 
cases, these conditions require certain actions by the licensee which, 
once completed, are no longer applicable. In order to simplify the 
licenses for Byron, Units 1 and 2, the licensee has proposed to delete 
license conditions which have been satisfied, revise others to delete 
parts which are no longer applicable or to revise references, and make 
editorial changes.

Description of the Proposed Change

    The licensee proposed to modify Unit 1 license condition 2.C.(1), 
``Maximum Power Level,'' to delete references to Attachment 1 to the 
Unit 1 operating

[[Page 36723]]

license. Attachment 1 describes preoperational tests, startup tests and 
other items that shall be completed as specified as a condition of the 
license.
    The licensee proposed to delete Unit 1 license condition 2.C.(3), 
``Post-Fuel-Loading Initial Test Program (Section 14, SER [Safety 
Evaluation Report]),'' which states: ``Any changes to the Initial Test 
Program described in Section 14 of the FSAR [Final Safety Analysis 
Report] made in accordance with the provisions of 10 CFR 50.59 shall be 
reported in accordance with 50.59(b) within one month of such change.''
    The licensee proposed to delete Unit 1 license condition 2.C.(4), 
``Seismic and Dynamic Qualification (Section 3.10, SSER [Supplemental 
Safety Evaluation Report] #5)*,'' which states: ``Prior to startup 
following the first refueling outage, the licensee shall completely 
qualify the Westinghouse 7300 Process Protection System (ESE-13), for 
both Nuclear Steam Supply System and Balance of Plant applications, 
including any hardware changes, if found necessary.'' The licensee also 
proposed to delete a related item from license condition 2.D. License 
condition 2.D. lists exemptions from 10 CFR Part 50 that were granted 
with the initial licensing. License condition 2.D.(b) identifies an 
exemption to General Design Criterion-2 (GDC-2) of Appendix A, which 
was granted to allow operation with license condition 2.C.(4).
    The licensee proposed to delete Unit 1 license condition 2.C.(5), 
``Equipment Qualification (Section 3.11, SSER #5, SSER #6),'' which 
states: ``All electrical equipment within the scope of 10 CFR 50.49 
must be environmentally qualified by November 30, 1985.''
    The licensee proposed to delete Unit 1 license condition 2.C.(7), 
``Control Room Human Factors (Section 18.2, SSER #4),'' which states: 
``Unless the staff determines that the test results do not support the 
change, the licensee shall, prior to startup following the first 
refueling outage, move the range and volume controls for the SOURCE 
RANGE nuclear instrument on Unit 1 from the nuclear instrumentation 
cabinet 1PM07J to the main control board 1PM05J.''
    The licensee proposed to delete Unit 1 license condition 2.C.(8), 
``TMI Item 11.F.1,Iodine/Particulate Sampling (Section 11.5, SSER 
#5),'' which states: ``Prior to startup following the first refueling 
outage, the licensee shall demonstrate that the operating idoline/
particulate sampling system will perform its intended function.''
    The licensee proposed to delete Unit 1 license condition 2.C.(9), 
``Emergency Response Capability (NUREG-0737, Supplement #1),'' which 
states: ``The licensee shall complete the emergency response 
capabilities as required by Attachment 2 to this license, which is 
incorporated into this license.'' Attachment 2 lists the following five 
separate emergency response issues.
    Number 1, ``Detailed Control Room Design Review (DCRDR),'' which 
states: ``The license shall submit the final summary report for the 
DCRDR by December 1, 1986.''
    Number 2, ``Regulatory Guide 1.97, Revision 2 Compliance,'' which 
states: ``The licensee shall submit by March 1, 1987, a preliminary 
report describing how the requirements of Regulatory Guide 1.97, 
Revision 2 have been or will be met. The licensee shall submit by 
September 1, 1987, the final report and a schedule for implementation 
(assuming the NRC approves the DCRDR by March 1, 1987).''
    Number 3, ``Upgrade Emergency Operating Procedures (EOPs),'' which 
states: ``The licensee shall submit a Procedures Generation Package 
within 3 months of NRC approval of Westinghouse Owners Group (WOG) 
Emergency Procedure Guidelines (EPG) Revision 1. The licensee shall 
implement the upgraded EOPs based on WOG EOPs Revision 1 within 12 
months of NRC approval of WOG EPG Revision 1.''
    Number 4, ``Emergency Response Facilities,'' which states: ``The 
licensee shall implement the Emergency Response Facility meteorological 
A-model by January 1, 1986.''
    Number 5, ``Safety Parameter Display System (SPDS),'' which states: 
``The licensee shall have SPDS operational by March 30, 1985.''
    The licensee proposed to delete Unit 1 license condition 2.C.(10), 
``Reliability of Diesel-Generators (Section 9.5.4.1, SER, SSER #5)*,'' 
which states: ``Prior to startup following the first refueling outage, 
the controls and monitoring instrumentation on the local control panels 
shall be dynamically qualified for their location or shall be installed 
on a free standing floor mounted panel in such a manner (including the 
use of vibration isolation mounts as necessary) that there is 
reasonable assurance that any induced vibrations will not result in 
cyclic fatigue for the expected life of the instrument.''
    The licensee proposed to delete Unit 1 license condition 2.C.(11), 
``Generic Letter 83-28 (Required Actions Based on Generic Implications 
of Salem ATWS [anticipated transient without scram] Events),'' which 
states: ``The licensee shall submit responses to and implement the 
requirements of Generic Letter 83-28 on a schedule which is consistent 
with that given in its letters dated November 5, 1983, February 29, 
1984, June 1, 1984 and October 10, 1984.''
    The licensee proposed to delete Unit 1 license condition 2.C.(12), 
``Formal Federal Emergency Management Agency Finding,'' which states: 
``In the event that the NRC finds that the lack of progress in 
completion of the procedures in the Federal Emergency Management 
Agency's final rule, 44 CFR Part 350, is an indication that a major 
substantive problem exists in achieving or maintaining an adequate 
state of emergency preparedness, the provisions of 10 CFR Sections 
50.54(s)(2) will apply.''
    The licensee proposed to delete Unit 1 license condition 2.C.(13), 
``Control Room Ventilation System (Section 6.5.1, SSER #5, SSER #6)*,'' 
which states: ``Prior to July 1, 1985, the licensee shall incorporate 
modifications, as necessary, to ensure that the control room 
ventilation system may be used during an accident to protect operators 
within the criteria specified in 10 CFR 50, Appendix A, General Design 
Criteria 19.''
    The licensee proposed to delete Unit 1 license condition 2.C.(14), 
``Turbine Missiles (Section 3.5.1.3, SSER #5),'' which states: ``The 
licensee shall volumetrically inspect all three low pressure turbine 
rotors by mevery third refueling outage, until a turbine system 
maintenance program based on the manufacturer's calculations of missile 
generation probabilities is approved by the staff.''
    The licensee proposed to delete Unit 1 license condition 2.C.(15), 
``Operating Staff Experience Requirements (Section 13.1.2.1, SSER 
#5),'' which states: ``The licensee shall have a licensed senior 
operator on each shift who has had at least six months of hot operating 
experience on a similar type plant, including at least six weeks at 
power levels greater than 20 percent of full power, and who has had 
start-up and shutdown experience, except as follows. For those shifts 
where such an individual is not available on the plant staff, an 
advisor shall be provided who has had at least four years of power 
plant experience, including two years of nuclear plant experience, and 
who has had at least one year of experience on shift as a licensed 
senior operator at a similar type facility. Use of advisors who were 
licensed only at the RO [reactor operator] level will be evaluated on a 
case-by-case basis. Advisors shall be trained on plant procedures, 
technical specifications and plant systems, and shall be examined on 
these

[[Page 36724]]

topics at a level sufficient to assure familiarity with the plant. For 
each shift, the remainder of the shift crew shall be trained as to the 
role of the advisors. These advisors shall be retained until the 
experience levels identified in the first sentence above have been 
achieved. The NRC shall be notified at least 30 days prior to the date 
that the licensee proposes to release the advisors from further 
service.''
    The licensee proposed to revise Unit 1 license condition 2.D. to 
delete the list of exemptions from 10 CFR Part 50 and replace it with a 
statement that no exemptions from 10 CFR Part 50 are required.
    The licensee proposed to modify Unit 2 license condition 2.C.(1), 
``Maximum Power Level,'' to delete references to Attachment 1 to the 
Unit 1 operating license. Attachment 1 describes preoperational tests, 
ventilation tests and fire barrier sealing that shall be completed as 
specified as a condition of the license. Attachment 1, Item A., 
required that preoperational tests and test deficiencies documented in 
licensee letters dated November 3, 1986, and January 14, 1987, be 
completed in accordance with the licensee's schedule commitments.
    The licensee proposed to revise Unit 2 license condition 2.C.(2), 
``Technical Specifications and Environmental Protection Plan,'' to 
delete references to Attachment 2.
    The licensee proposed to delete Unit 2 license condition 2.C.(3), 
``Initial Test Program,'' which states: ``Any changes to the Initial 
Startup Test Program described in Chapter 14 of the FSAR made in 
accordance with the provisions of 10 CFR 50.59 shall be reported in 
accordance with 50.59(b) within one month of such change.''
    The licensee proposed to delete Unit 2 license condition 2.C.(4), 
``Regulatory Guide 1.97, Revision 2 Compliance,'' which states: ``The 
licensee shall submit by March 1, 1987, a preliminary report describing 
how the requirements of Regulatory Guide 1.97, Revision 2 have been or 
will be met. The licensee shall submit by September 1, 1987, the final 
report and a schedule for implementation (assuming the NRC approves the 
DCRDR by March 1, 1987).''
    The licensee proposed to revise Unit 2 license condition 2.D. to 
delete the list of exemptions from 10 CFR Part 50 and replace it with a 
statement that no exemptions from 10 CFR Part 50 are required.
    The licensee also proposed certain editorial changes.

Environmental Impacts of the Proposed Action

    The Commission has completed its environmental evaluation of the 
proposed action and concludes that the proposed amendment would not 
increase the probability or consequences of accidents previously 
analyzed and would not affect facility radiation levels or facility 
radiological effluents.
    The proposed action will not increase the probability or 
consequences of accidents, no changes are being made in the types of 
any effluents that may be released off site, and there is no 
significant increase in occupational or public radiation exposure. 
Therefore, there are no significant radiological environmental impacts 
associated with the proposed action.
    With regard to potential non-radiological impacts, the proposed 
action does not involve any historic sites. It does not affect non-
radiological plant effluents and has no other environmental impact. 
Therefore, there are no significant non-radiological environmental 
impacts associated with the proposed action.
    Accordingly, the Commission concludes that there are no significant 
environmental impacts associated with the proposed action.

Alternatives to the Proposed Action

    As an alternative to the proposed action, the staff considered 
denial of the proposed action (i.e., the ``no-action'' alternative). 
Denial of the application would result in no change in current 
environmental impacts. The environmental impacts of the proposed action 
and the alternative action are similar.

Alternative Use of Resources

    This action does not involve the use of any resources not 
previously considered in the Final Environmental Statement for Byron 
Station, Units 1 and 2.

Agencies and Persons Consulted

    In accordance with its stated policy, on May 28, 1999, the staff 
consulted with the Illinois State official, Mr. Frank Niziolek, of the 
Illinois Department of Nuclear Safety, regarding the environmental 
impact of the proposed action. The State official had no comments.

Finding of No Significant Impact

    On the basis of 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 action.
    For further details with respect to the proposed action, see the 
licensee's letter dated March 14, 1997, 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 Byron Public Library District, 109 N. 
Franklin, P.O. Box 434, Byron, Illinois 61010.

    Dated at Rockville, Maryland, this 29th day of June 1999.

    For the Nuclear Regulatory Commission.
Anthony J. Mendiola,
Chief, Section 2, Project Directorate III, Division of Licensing 
Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. 99-17193 Filed 7-6-99; 8:45 am]
BILLING CODE 7590-01-P