[Federal Register Volume 75, Number 246 (Thursday, December 23, 2010)]
[Notices]
[Pages 80855-80857]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2010-32246]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-305; NRC-2010-0387]


Dominion Energy Kewaunee, Inc.; Kewaunee Power Station; 
Environmental Assessment and Finding of No Significant Impact

    The U.S. Nuclear Regulatory Commission (NRC) is considering 
issuance of an amendment to Facility Operating License No. DPR-43, 
issued to Dominion Energy Kewaunee, Inc. (DEK, the licensee), for 
operation of the Kewaunee Power Station (KPS) located in Ottawa County, 
Wisconsin, in accordance with Title 10 of the Code of Federal 
Regulations (10 CFR) 50.90. Therefore, as required by 10 CFR 51.21, the 
NRC performed an environmental assessment. Based on the results of the 
environmental assessment, the NRC is issuing a finding of no 
significant impact in accordance with 10 CFR 51.32.

Environmental Assessment

Identification of the Proposed Action

    The proposed action would be a full conversion from the current 
technical specifications (CTS) to the improved technical specifications 
(ITS) consistent with improved standard technical specifications as 
described in NUREG 1431, ``Standard Technical Specifications--
Westinghouse Plants, Rev. 3.0'' (Agencywide Documents Access and 
Management System (ADAMS) Accession No. ML041830612). Standard 
Technical Specifications (STS) Rev. 3.0 is modified by the following 
NRC-approved TS Task Force (TSTF) Travelers: TSTF-475-A, Rev. 1; TSTF-
479-A, Rev. 0; TSTF-482-A, Rev. 0; TSTF-485-A, Rev. 0; TSTF-490-A, Rev. 
0; TSTF-491-A, Rev. 2; TSTF-493, Rev. 4; TSTF-497-A, Rev. 0; and TSTF-
511-A, Rev. 0. The proposed action also encompasses beyond scope issues 
included in the Notice of Consideration of Issuance of Amendment.
    The proposed action is in accordance with the licensee's 
application dated August 24, 2009 (ADAMS Accession No. ML092440398), as 
supplemented by letters dated October 22, 2009 (ADAMS Accession No. 
ML093070092), April 13, 2010 (ADAMS Accession Nos. ML101060517 and 
ML101040090), May 12, 2010 (ADAMS Accession No. ML101380399), July 1, 
2010 (ADAMS Accession No. ML101890176), July 16, 2010 (ADAMS Accession 
No. ML102370370), August 18, 2010 (ADAMS Accession No. ML102371064), 
September 7, 2010 (ADAMS Accession No. ML102730383), September 8, 2010 
(ADAMS Accession No. ML102580700), October 15, 2010 (ADAMS Accession 
No. ML102920037), and December 2, 2010 (ADAMS Accession No. 
ML103400328). The information provided to the NRC staff through the 
joint NRC-DEK ITS conversion Web page, hosted by EXCEL Services 
Corporation (EXCEL) can be found in these supplements.
    To expedite its review of the application, the NRC staff issued its 
requests for additional information (RAI) through the KPS ITS 
Conversion web page and the licensee addressed the RAI by providing 
responses on the Web page. Entry into the database is protected so that 
only the licensee and NRC reviewers can enter information into the 
database to add RAIs (NRC) or provide responses to the RAIs (licensee); 
however, the public can enter the database to read the questions asked 
and the responses provided. To be in compliance with the regulations 
for written communications for license amendment requests, and to have 
the database on the KPS dockets before the amendment is issued, the 
licensee has submitted the information from the database in its 
supplements to the NRC. No further RAI items are being processed prior 
to the issuance of the amendment.
    Members of the public can access the Web site by going to http://www.excelservices.com. Persons who visit the EXCEL Web site and are 
unable to locate Kewaunee ITS Conversion information should contact 
EXCEL directly to acquire archived content. As an alternative, the 
licensee's submitted information cited above is available at the NRC 
Web site (http://www.nrc.gov).

The Need for the Proposed Action:

    The Commission's ``Proposed Policy Statement on Technical 
Specifications Improvements for Nuclear Power Reactors'' (52 FR 3788), 
dated February 6, 1987, contained an Interim Policy Statement that set 
forth objective criteria for determining which regulatory requirements 
and operating restrictions should be included in the technical 
specifications (TS). When it issued the Interim Policy Statement, the 
Commission also requested comments on it. Subsequently, to implement 
the Interim Policy Statement, each reactor vendor owners group and the 
NRC staff began developing standard TS (STS) for reactors supplied by 
each vendor. The Commission then published its ``Final Policy Statement 
on Technical Specifications Improvements for Nuclear Power Reactors'' 
(58 FR 39132), dated July 22, 1993, in which it

[[Page 80856]]

addressed comments received on the Interim Policy Statement, and 
incorporated experience in developing the STS. The Final Policy 
Statement formed the basis for a revision to 10 CFR 50.36 (60 FR 
36953), dated July 19, 1995, that codified the criteria for determining 
the content of TSs. The NRC Committee to Review Generic Requirements 
reviewed the STS, made note of their safety merits, and indicated its 
support of conversion by operating plants to the STS.
    For KPS the following document the STS and form the basis for the 
KPS conversion to the ITS:
    NUREG-1431, Rev. 3.0, and the following NRC approved TSTF 
Travelers:
    1. TSTF-475-A, Rev. 1 ``Control Rod Notch Testing Frequency and 
[source range monitor] SRM Insert Control Rod Action'',
    2. TSTF-479-A, Rev. 0 ``Changes to Reflect Revision of 10 CFR 
50.55a'',
    3. TSTF-482-A, Rev. 0 ``Correct LCO 3.0.6 Bases'',
    4. TSTF-485-A, Rev. 0 ``Correct Example 1.4-1'',
    5. TSTF-490-A, Rev. 0 ``Deletion of E Bar Definition and Revision 
to [Reactor Coolant System] RCS Specific Activity Technical 
Specification'',
    6. TSTF-491-A, Rev. 2 ``Removal of Main Steam and Main Feedwater 
Valve Isolation Times from Technical Specifications'',
    7. TSTF 493, Rev. 4 ``Clarify Application of Setpoint Methodology 
for [Limiting Safety System Setting] LSSS Functions'',
    8. TSTF-497-A, Rev. 0 ``Limit Inservice Testing Program SR 3.0.2 
Application to Frequencies of 2 Years or Less'',
    9. TSTF-511-A, Rev. 0 ``Eliminate Working Hour Restrictions from TS 
5.2.2 to Support Compliance with 10 CFR Part 26.''
    The proposed changes to the CTS are based on NUREG-1431, Rev. 3.0, 
associated TSTF documents, and the guidance provided in the Final 
Policy Statement. The objective of this action is to rewrite, reformat, 
and streamline the CTS (i.e., to convert the CTS to the ITS). Emphasis 
was placed on human factors principles to improve clarity and 
understanding. The ITS Bases section has been significantly expanded to 
clarify and better explain the purpose and foundation of each 
specification.
    In addition to NUREG-1431, Rev. 3.0, and associated TSTF documents, 
portions of the CTS were also used as the bases for the development of 
the KPS ITS. The NRC staff discussed plant-specific issues (i.e., 
unique design features, requirements, and operating practices) with the 
licensee.
    Relocated specifications include those changes to the CTS that 
relocate certain requirements, which do not meet the 10 CFR 50.36 
selection criteria. These requirements may be relocated to the Bases 
section, the KPS Updated Safety Analysis Report (USAR), the core 
operating limits report, the operational quality assurance plan, plant 
procedures, or other licensee-controlled documents. Relocation of 
requirements to licensee-controlled documents does not eliminate them, 
but rather, places them under more appropriate regulatory controls 
(i.e. 10 CFR 50.54(a)(3) and 10 CFR 50.59) to manage their 
implementation and future changes.
    The proposed action is necessary to allow the licensee to implement 
the ITS. The ITS are based on Westinghouse STS and they are considered 
an improvement over the CTS.

Environmental Impacts of the Proposed Action

    The NRC has completed its environmental assessment of the proposed 
amendment action. The staff concludes that the proposed action to 
convert the CTS for the plant to ITS would not significantly affect 
plant safety and would not have a significant adverse effect on the 
probability of an accident occurring.
    The proposed action would not result in an increased radiological 
hazard beyond those previously analyzed in the Updated Safety Analysis 
Report. There will be no change to radioactive effluents that affect 
radiation exposures to plant workers and members of the public. No 
changes will be made to plant buildings or the site property. 
Therefore, no changes or different types of radiological impacts are 
expected as a result of the proposed action.
    The proposed action does not result in changes to any of the 
following: To land use or water use, or result in changes to the 
quality or quantity of non-radiological effluents. No changes to the 
National Pollution Discharge Elimination System permit are needed. No 
effects on the aquatic or terrestrial habitat in the vicinity or the 
plant, or to threatened, endangered, or protected species under the 
Endangered Species Act, or impacts to essential fish habitat covered by 
the Magnuson-Stevens Act are expected. There are no impacts to the air 
or ambient air quality.
    The proposed action does not have a potential to affect any 
historical or cultural resources because no previously undisturbed area 
will be affected by the proposed amendment. There would be no impact to 
socioeconomic resources. Therefore, no changes to or different types of 
non-radiological environmental impacts are expected as a result of the 
proposed action.
    Accordingly, the NRC concludes that there are no significant 
environmental impacts associated with the proposed action, and thus, 
the proposed action will not have a significant effect on the quality 
of the human environment. The details of the NRC staff's safety 
evaluation will be provided with the license amendment approving the 
conversion to the approved technical specifications that will be issued 
to the licensee.

Environmental Impacts of the 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. Thus, the environmental impacts of the proposed 
action and the ``no-action'' alternative are similar.

Alternative Use of Resources

    The action does not involve the use of any different resources than 
those previously considered in the ``Final Environmental Statement for 
the KPS,'' dated December, 1972, and the ``Generic Environmental Impact 
Statement for License Renewal of Nuclear Plants [NUREG 1437], 
Supplement 40, Regarding Kewaunee Power Station, Final Report,'' dated 
August 2010 (ADAMS Accession No. ML102150106).

Agencies and Persons Consulted

    On September 23, 2010, the NRC staff consulted with the Wisconsin 
State official, Jeff Kitsembel, Nuclear Engineer, of the Public Service 
Commission of Wisconsin and the State Liaison Official for Wisconsin, 
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 NRC concludes 
that the proposed action will not have a significant effect on the 
quality of the human environment. Accordingly, the NRC 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 previously referenced application letter and its 
supplemental letters. The information provided to the NRC staff through 
the joint NRC-DEK ITS

[[Page 80857]]

conversion web page, hosted by Excel Services Corporation, can be found 
in the application document and its supplements.
    Documents may be examined, and/or copied for a fee, at the NRC's 
Public Document Room (PDR), located at One White Flint North, Public 
File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, 
Maryland. Publicly available records will be accessible electronically 
from the ADAMS Public Electronic Reading Room on the Internet at the 
NRC Web site, http://www.nrc.gov/reading-rm/adams.html.
    Persons who do not have access to ADAMS or who encounter problems 
in accessing the documents located in ADAMS should contact the NRC PDR 
Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or send 
an e-mail to [email protected].

    Dated at Rockville, Maryland, this 8th day of December 2010.

    For the Nuclear Regulatory Commission.
Peter S. Tam,
Senior Project Manager, Plant Licensing Branch III-1, Division of 
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2010-32246 Filed 12-22-10; 8:45 am]
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