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Yankee Atomic Electric Company; Issuance of Environmental Assessment and Finding of No Significant Impact for the Proposed Exemption
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[Federal Register: July 29, 2002 (Volume 67, Number 145)]
[Notices]
[Page 49046-49047]
From the Federal Register Online via GPO Access [wais.access.gpo.gov]
[DOCID:fr29jy02-73]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 72-31]
Yankee Atomic Electric Company; Issuance of Environmental
Assessment and Finding of No Significant Impact for the Proposed
Exemption
The U.S. Nuclear Regulatory Commission (NRC or Commission) is
considering issuance of an exemption, pursuant to 10 CFR 72.7, from the
provisions of 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A), and 72.214 to
the Yankee Atomic Electric Company (YAEC). The requested exemption
would allow YAEC to deviate from the requirements of Certificate of
Compliance No. 1025 (the Certificate), Appendix A, Technical
Specifications (TS), Table A2-2, Intact Fuel Assembly Characteristics
for the NAC-MPC. The exemption would modify the specified fuel
enrichment parameters to incorporate fuel enrichment fabrication
tolerances into the Yankee-Class fuel parameters which would allow YAEC
to maintain continuity of the fuel loading campaign at Yankee Nuclear
Power Station (YNPS) in Rowe, Massachusetts.
[[Page 49047]]
Environmental Assessment (EA)
Identification of Proposed Action: By letter dated May 10, 2002,
YAEC requested an exemption from the requirements of 10 CFR
72.212(a)(2), 72.212(b)(2)(i)(A), and 72.214 to deviate from the
requirements of Certificate of Compliance No. 1025, Appendix A, Table
A2-2. YAEC is a general licensee, authorized by NRC to use spent fuel
storage casks approved under 10 CFR part 72, subpart K.
YAEC plans to use the NAC-MPC cask system to store spent nuclear
fuel, generated at YNPS, at an independent spent fuel storage
installation (ISFSI) located in Rowe, Massachusetts, on the YNPS site.
The YNPS ISFSI has been constructed for interim dry storage of spent
nuclear fuel.
By exempting YAEC from 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A), and
72.214, YAEC will be authorized to store fuel with enrichments 0.03 wt
% U-235 larger than those enrichments specified in the existing
technical specifications for Yankee-Class fuel. The revised fuel
enrichment parameters for the Yankee-Class fuel are as follows (all
enrichments are in wt % of U-235):
Combustion Engineering Type A.... Maximum--3.93 Minimum--3.66
Combustion Engineering Type B.... Maximum--3.93 Minimum--3.66
Exxon Type A..................... Maximum--4.03 Minimum--3.46
Exxon Type B..................... Maximum--4.03 Minimum--3.46
Westinghouse Type A.............. Maximum--4.97 Minimum--4.90
Westinghouse Type B.............. Maximum--4.97 Minimum--4.90
United Nuclear Type A............ Maximum--4.03 Minimum--3.96
United Nuclear Type B............ Maximum--4.03 Minimum--3.96
The specifications above would be in lieu of those in the current
Certificate of Compliance No. 1025, Rev. 1, Appendix A, Table A2-2. The
proposed action before the Commission is whether to grant this
exemption under 10 CFR 72.7.
On April 18, 2002, the Certificate holder, NAC International (NAC),
submitted to the NRC an application to amend Certificate of Compliance
No. 1025. The requested amendment includes the same revisions to Table
A2-2 in Appendix A to the Certificate as requested in this exemption.
The NRC staff has reviewed the application and agreed with the
applicant's conclusion that the NAC-MPC system is not significantly
affected by increasing the enrichment by 0.03 wt % above the previous
design basis enrichment and does not impact the ability of the NAC-MPC
to meet the requirements of 10 CFR part 72.
Need for the Proposed Action: The revised Table A2-2 will authorize
for storage, fuel with enrichments that incorporate enrichment
fabrication tolerances for the Yankee-Class fuel. This will allow YAEC
to maintain continuity of fuel loading activities to permit inspection
of the fuel assemblies in the lower tier of the spent fuel pool. The
exemption will also support YAEC's goal of a timely decommissioning of
the YNPS site. The overall result of not granting the exemption would
be unnecessary delays in schedule and delayed completion of
decommissioning activities with negligible impact on safety. Because
the 10 CFR part 72 rulemaking to amend the Certificate will not be
completed prior to the date that YNPS plans to begin loading fuel into
the NAC-MPC cask systems, the NRC is proposing to grant this exemption
based on the staff's technical review of information submitted by YAEC
and NAC.
Environmental Impacts of the Proposed Action: The Commission has
already determined that spent fuel can be stored safely and without
significant environmental impact at an onsite ISFSI in the NAC-MPC cask
system (65 FR 12444, dated March 9, 2000). Staff's review of NAC's
application for an amendment of its Certificate confirmed that changes
in fuel parameters to take into account fabrication tolerances for
enrichment will not increase the probability or consequences of
accidents. No changes have been requested to the types or quantities of
any radiological effluents that may be released offsite, and there is
no significant increase in occupational or public radiation exposure.
There are no significant radiological environmental impacts associated
with the proposed action.
Alternative to the Proposed Action: Since there is no significant
environmental impact associated with the proposed action, alternatives
with equal or greater environmental impact are not evaluated. The
alternative to the proposed action would be to deny approval of the
exemption and use the fuel assembly parameters table in the current
Certificate. Denial of the exemption will result in unnecessary delays
in schedules and delayed completion of decommissioning activities. With
the proposed actions, the applicant continues to meet all applicable
safety requirements.
Agencies and Persons Consulted: On July 9, 2002, Mr. Jim
Muckerhide, Nuclear Engineer, Nuclear Safety, Massachusetts Emergency
Management Agency was contacted about the Environmental Assessment for
the proposed action and had no comments.
Finding of No Significant Impact
The environmental impacts of the proposed action have been reviewed
in accordance with the requirements set forth in 10 CFR Part 51. Based
upon the foregoing EA, the Commission finds that the proposed action of
granting an exemption from 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A), and
72.214 allowing YAEC to use revised intact fuel enrichment parameters
in Table A2-2 at YNPS ISFSI will not significantly impact the quality
of the human environment. Accordingly, the Commission has determined
that an environmental impact statement for the proposed exemption is
not warranted.
The request for the exemption was docketed under 10 CFR Part 71,
Docket 72-31. For further details with respect to this action, see the
exemption request dated May 10, 2002. The NRC maintains an Agencywide
Documents Access and Management System (ADAMS), which provides text and
image files of NRC's public documents. These documents may be accessed
through the NRC's Public Electronic Reading Room on the Internet at
http://www.nrc.gov/reading-rm/adams.html. 
If you do not have
access to ADAMS or if there are problems in accessing the documents located
in ADAMS, contact the NRC Public Document Room (PDR) Reference staff at 1-
800-397-4209, 301-415-4737 or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 24th day of July, 2002.
For the Nuclear Regulatory Commission.
M. Wayne Hodges,
Acting Director, Spent Fuel Project Office, Office of Nuclear Material
Safety and Safeguards.
[FR Doc. 02-19197 Filed 7-26-02; 8:45 am]
BILLING CODE 7590-01-P