Maine Yankee Atomic Power Company; Issuance of Environmental Assessment and Finding of No Significant Impact Regarding a Proposed Exemption, 20607-20608 [E5-1854]
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Federal Register / Vol. 70, No. 75 / Wednesday, April 20, 2005 / Notices
also should arrive early in order to gain
on-time admission to the hearing room.
It is so ordered.
Issued in Rockville, Maryland, on April 13,
2005.
For the Pre-License Application Presiding
Officer Board.
Thomas S. Moore,
Chairman, Administrative Judge.
[FR Doc. E5–1850 Filed 4–19–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket 72–30]
Maine Yankee Atomic Power
Company; Issuance of Environmental
Assessment and Finding of No
Significant Impact Regarding a
Proposed Exemption
Nuclear Regulatory
Commission.
ACTION: Environmental assessment.
AGENCY:
FOR FURTHER INFORMATION CONTACT:
Jeremy A. Smith, Project Manager,
Spent Fuel Project Office, Office of
Nuclear Material Safety and Safeguards,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555. Telephone:
(301) 415–8500; fax number: (301) 415–
8555; e-mail: jas5@nrc.gov.
SUPPLEMENTARY INFORMATION: The U.S.
Nuclear Regulatory Commission (NRC
or the staff) is considering issuance of
an exemption, pursuant to 10 CFR 72.7,
from the provisions of 10 CFR 72.72(d)
to Maine Yankee Atomic Power
Company (Maine Yankee or applicant).
The requested exemption would allow
Maine Yankee to maintain a single set
of spent fuel, high-level radioactive
waste, and reactor-related Greater Than
Class C (GTCC) waste records in
accordance with the requirements of 10
CFR 50.71(d)(1), for the Independent
Spent Fuel Storage Installation (ISFSI)
at Maine Yankee in Wiscasset, Maine.
Environmental Assessment (EA)
Identification of Proposed Action: By
letter dated November 29, 2004, Maine
Yankee requested an exemption from
the requirement in 10 CFR 72.72(d)
which states in part that, ‘‘Records of
spent fuel, high-level radioactive waste,
and reactor-related GTCC waste
containing special nuclear material
meeting the requirements in paragraph
(a) of this section must be kept in
duplicate. The duplicate set of records
must be kept at a separate location
sufficiently remote from the original
records that a single event would not
destroy both sets of records.’’
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14:54 Apr 19, 2005
Jkt 205001
The proposed action before the
Commission is whether to grant this
exemption pursuant to 10 CFR 72.7.
Need for the Proposed Action: The
applicant stated that ISFSI spent-fuel,
high-level radioactive waste, and
reactor-related GTCC waste records will
be maintained in a manner consistent
with the records of Maine Yankee,
which are stored in compliance with the
requirements established in 10 CFR
50.71(d)(1). No exemption is requested
from the 10 CFR 72.72(d) requirements
for the records retention period
requirements. The applicant seeks to
provide consistency in recordkeeping
maintenance for the Maine Yankee
ISFSI spent fuel, high-level radioactive
waste, and reactor-related GTCC waste
records. The exemption request will
also preclude the need to construct and
operate a separate, second records
storage facility to store a duplicate set of
spent-fuel, high-level radioactive waste,
and reactor-related GTCC waste records.
10 CFR 50.71(d)(1) provides
requirements for the maintenance of
nuclear power plant records. The
regulation states:
20607
Records which must be maintained
pursuant to this part may be the original or
a reproduced copy or microform if such
reproduced copy or microform is duly
authenticated by authorized personnel and
the microform is capable of producing a clear
and legible copy after storage for the period
specified by the Commission regulations. The
record may also be stored in electronic media
with the capability of producing legible,
accurate, and complete records during the
required retention period. Records such as
letters, drawings, specifications, must
include all pertinent information such as
stamps, initials, and signatures. The licensee
shall maintain adequate safeguards against
tampering with and loss of records.
location, and assigned responsibility.’’
ANSI N.45.2.9–1974 also satisfies the
requirements of 10 CFR 72.72 by
providing for adequate maintenance of
records regarding the identity and
history of the spent fuel in storage. Such
records would be subject to and need to
be protected from the same types of
degradation mechanisms as nuclear
power plant Quality Assurance records.
Environmental Impacts of the
Proposed Action: An exemption from
the requirement to store a duplicate set
of ISFSI records at a separate location
has no impact on the environment.
Storage of records does not change the
methods by which spent fuel will be
handled and stored at the Maine Yankee
ISFSI and does not change the amount
of effluents, radiological or
nonradiological, associated with the
ISFSI.
Alternative to the Proposed Action:
Since there is no environmental impact
associated with the proposed action,
alternatives are not evaluated other than
the no action alternative. The alternative
to the proposed action would be to deny
approval of the exemption and,
therefore, not allow storage of ISFSI
spent fuel records at a single qualified
record storage facility. The no action
alternative would require the applicant
to construct or identify a separate
storage facility; therefore, the
environmental impacts of the proposed
action would be less than, or the same
as, the no action alternative.
Agencies and Persons Consulted: On
March 28, 2005, Maine State Nuclear
Safety Inspector Mr. Patrick Dostie was
contacted regarding the environmental
assessment for the proposed action and
had no comments.
Regulatory Guide 1.88, ‘‘Collection,
Storage, and Maintenance of Nuclear
Power Plant Quality Assurance
Records,’’ establishes guidance for the
storage of nuclear plant quality
assurance records. Maine Yankee plans
to implement Revision 2 of Regulatory
Guide 1.88, with minor exceptions
described in the Maine Yankee Quality
Assurance Plan (QAP).
The requirements in ANSI N45.2.9–
1974 have been endorsed by the NRC in
Regulatory Guide 1.88 as adequate for
satisfying the recordkeeping
requirements of 10 CFR Part 50,
Appendix B, which states in part that
‘‘records shall be identifiable and
retrievable.’’ Additionally, conditions in
10 CFR Part 50, Appendix B establish
that ‘‘[c]onsistent with applicable
regulatory requirements (including 10
CFR 50.71(d)(1)), the applicant shall
establish requirements concerning
record retention, such as duration,
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 Environmental Assessment,
the Commission finds that the proposed
action of granting the exemption from
10 CFR 72.72(d), so that Maine Yankee
may store spent fuel records for the
ISFSI in a single records storage facility
which meets the requirements of ANSI
N.45.2.9–1974, with the given exception
listed in the Maine Yankee QAP, 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 necessary.
The request for exemption was
docketed under 10 CFR Part 72, Docket
72–30. For further details with respect
to this exemption request, see the Maine
Yankee letter requesting the exemption
PO 00000
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20APN1
20608
Federal Register / Vol. 70, No. 75 / Wednesday, April 20, 2005 / Notices
dated November 29, 2004. Supporting
documentation is available for
inspection at the NRC’s Public
Electronic Reading Room at https://
www.nrc.gov/reading-rm/adams.html. A
copy of the Finding of No Significant
Impact can be found at this site using
the Agencywide Documents Access and
Management System (ADAMS). These
documents may also be viewed
electronically on the public computers
located at the NRC’s Public Document
Room (PDR), O1–F21, One White Flint
North, 11555 Rockville Pike, Rockville,
MD 20852. The PDR reproduction
contractor will copy documents for a
fee. 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 at 1–800–397–4209 or
(301) 415–4737, or by e-mail to
pdr@nrc.gov.
Dated at Rockville, Maryland, this 13th day
of April 2005.
For the Nuclear Regulatory Commission.
Jeremy A. Smith,
Project Manager, Spent Fuel Project Office,
Office of Nuclear Material Safety and
Safeguards.
[FR Doc. E5–1854 Filed 4–19–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards; Subcommittee Meeting on
Planning and Procedures; Notice of
Meeting
The ACRS Subcommittee on Planning
and Procedures will hold a meeting on
May 4, 2005, Room T–2B1, 11545
Rockville Pike, Rockville, Maryland.
The entire meeting will be open to
public attendance, with the exception of
a portion that may be closed pursuant
to 5 U.S.C. 552b(c)(2) and (6) to discuss
organizational and personnel matters
that relate solely to the internal
personnel rules and practices of the
ACRS, and information the release of
which would constitute a clearly
unwarranted invasion of personal
privacy.
The agenda for the subject meeting
shall be as follows:
Wednesday, May 4, 2005–10 a.m.–11:30
a.m.
The Subcommittee will discuss
proposed ACRS activities and related
matters. The Subcommittee will gather
information, analyze relevant issues and
facts, and formulate proposed positions
and actions, as appropriate, for
deliberation by the full Committee.
VerDate jul<14>2003
14:54 Apr 19, 2005
Jkt 205001
Members of the public desiring to
provide oral statements and/or written
comments should notify the Designated
Federal Official, Mr. Sam Duraiswamy
(telephone: 301–415–7364) between
7:30 a.m. and 4:15 p.m. (ET) five days
prior to the meeting, if possible, so that
appropriate arrangements can be made.
Electronic recordings will be permitted
only during those portions of the
meeting that are open to the public.
Further information regarding this
meeting can be obtained by contacting
the Designated Federal Official between
7:30 a.m. and 4:15 p.m. (ET). Persons
planning to attend this meeting are
urged to contact the above named
individual at least two working days
prior to the meeting to be advised of any
potential changes in the agenda.
Dated: April 13, 2005.
Michael L. Scott,
Branch Chief, ACRS/ACNW.
[FR Doc. E5–1851 Filed 4–19–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards; Subcommittee Meeting on
Fire Protection; Notice of Meeting
The ACRS Subcommittee on Fire
Protection will hold a meeting on May
4, 2005, Room T–2B3, 11545 Rockville
Pike, Rockville, Maryland.
The entire meeting will be open to
public attendance.
The agenda for the subject meeting
shall be as follows:
Wednesday, May 4 , 2005—8:30 a.m.
until 3 p.m.
The purpose of this meeting is to
discuss the NRC/EPRI joint work on the
improved fire risk assessment
methodology. The Subcommittee will
discuss NUREG/CR–6850, ‘‘EPRI/NRC–
RES Fire PRA Methodology for Nuclear
Power Facilities.’’ The Subcommittee
will also discuss the NRC staff’s efforts
on verification and validation of fire
models. The Subcommittee will hear
presentations by and hold discussions
with the NRC staff, representatives of
the EPRI, and other interested persons
regarding this matter. The
Subcommittee will gather information,
analyze relevant issues and facts, and
formulate proposed positions and
actions, as appropriate, for deliberation
by the full Committee.
Members of the public desiring to
provide oral statements and/or written
comments should notify the Designated
Federal Official, Mr. Hossein P.
Nourbakhsh (Telephone: 301–415–5622)
PO 00000
Frm 00094
Fmt 4703
Sfmt 4703
five days prior to the meeting, if
possible, so that appropriate
arrangements can be made. Electronic
recordings will be permitted.
Further information regarding this
meeting can be obtained by contacting
the Designated Federal Official or the
Cognizant Staff Engineer between 7:30
a.m. and 4:15 p.m. (ET). Persons
planning to attend this meeting are
urged to contact one of the above named
individuals at least two working days
prior to the meeting to be advised of any
potential changes to the agenda.
Dated: April 13, 2005.
Michael L. Scott,
Branch Chief, ACRS/ACNW.
[FR Doc. E5–1852 Filed 4–19–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards; Meeting Notice
In accordance with the purposes of
Sections 29 and 182b. of the Atomic
Energy Act (42 U.S.C. 2039, 2232b), the
Advisory Committee on Reactor
Safeguards (ACRS) will hold a meeting
on May 5–6, 2005, 11545 Rockville Pike,
Rockville, Maryland. The date of this
meeting was previously published in
the Federal Register on Wednesday,
November 24, 2004 (69 FR 68412).
Thursday, May 5, 2005, Conference
Room T–2B3, Two White Flint North,
Rockville, Maryland
8:30 a.m.–8:35 a.m.: Opening
Remarks by the ACRS Chairman
(Open)—The ACRS Chairman will make
opening remarks regarding the conduct
of the meeting. 8:35 a.m.–10 a.m.: Final
Review of the License Renewal
Application for Arkansas Nuclear One,
Unit 2 (ANO–2) (Open)—The Committee
will hear presentations by and hold
discussions with representatives of the
Entergy Operations, Inc. and the NRC
staff regarding the license renewal
application for ANO–2 and the
associated final Safety Evaluation
Report prepared by the NRC staff.
10:15 a.m.–11:45 a.m.: Draft Final
Revisions to Standard Review Plan
(SRP), Chapter 13, ‘‘Conduct of
Operations’’ (Open)—The Committee
will hear presentations by and hold
discussions with representatives of the
NRC staff regarding the draft final
revisions to Sections 13.1.2–13.1.3,
‘‘Operating Organization,’’ of SRP
Chapter 13 and related NUREG–1791,
‘‘Guidance for Assessing Exemption
Requests from the Nuclear Power Plant
Licensed Operator Staffing
E:\FR\FM\20APN1.SGM
20APN1
Agencies
[Federal Register Volume 70, Number 75 (Wednesday, April 20, 2005)]
[Notices]
[Pages 20607-20608]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-1854]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket 72-30]
Maine Yankee Atomic Power Company; Issuance of Environmental
Assessment and Finding of No Significant Impact Regarding a Proposed
Exemption
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental assessment.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Jeremy A. Smith, Project Manager,
Spent Fuel Project Office, Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555.
Telephone: (301) 415-8500; fax number: (301) 415-8555; e-mail:
jas5@nrc.gov.
SUPPLEMENTARY INFORMATION: The U.S. Nuclear Regulatory Commission (NRC
or the staff) is considering issuance of an exemption, pursuant to 10
CFR 72.7, from the provisions of 10 CFR 72.72(d) to Maine Yankee Atomic
Power Company (Maine Yankee or applicant). The requested exemption
would allow Maine Yankee to maintain a single set of spent fuel, high-
level radioactive waste, and reactor-related Greater Than Class C
(GTCC) waste records in accordance with the requirements of 10 CFR
50.71(d)(1), for the Independent Spent Fuel Storage Installation
(ISFSI) at Maine Yankee in Wiscasset, Maine.
Environmental Assessment (EA)
Identification of Proposed Action: By letter dated November 29,
2004, Maine Yankee requested an exemption from the requirement in 10
CFR 72.72(d) which states in part that, ``Records of spent fuel, high-
level radioactive waste, and reactor-related GTCC waste containing
special nuclear material meeting the requirements in paragraph (a) of
this section must be kept in duplicate. The duplicate set of records
must be kept at a separate location sufficiently remote from the
original records that a single event would not destroy both sets of
records.''
The proposed action before the Commission is whether to grant this
exemption pursuant to 10 CFR 72.7.
Need for the Proposed Action: The applicant stated that ISFSI
spent-fuel, high-level radioactive waste, and reactor-related GTCC
waste records will be maintained in a manner consistent with the
records of Maine Yankee, which are stored in compliance with the
requirements established in 10 CFR 50.71(d)(1). No exemption is
requested from the 10 CFR 72.72(d) requirements for the records
retention period requirements. The applicant seeks to provide
consistency in recordkeeping maintenance for the Maine Yankee ISFSI
spent fuel, high-level radioactive waste, and reactor-related GTCC
waste records. The exemption request will also preclude the need to
construct and operate a separate, second records storage facility to
store a duplicate set of spent-fuel, high-level radioactive waste, and
reactor-related GTCC waste records.
10 CFR 50.71(d)(1) provides requirements for the maintenance of
nuclear power plant records. The regulation states:
Records which must be maintained pursuant to this part may be
the original or a reproduced copy or microform if such reproduced
copy or microform is duly authenticated by authorized personnel and
the microform is capable of producing a clear and legible copy after
storage for the period specified by the Commission regulations. The
record may also be stored in electronic media with the capability of
producing legible, accurate, and complete records during the
required retention period. Records such as letters, drawings,
specifications, must include all pertinent information such as
stamps, initials, and signatures. The licensee shall maintain
adequate safeguards against tampering with and loss of records.
Regulatory Guide 1.88, ``Collection, Storage, and Maintenance of
Nuclear Power Plant Quality Assurance Records,'' establishes guidance
for the storage of nuclear plant quality assurance records. Maine
Yankee plans to implement Revision 2 of Regulatory Guide 1.88, with
minor exceptions described in the Maine Yankee Quality Assurance Plan
(QAP).
The requirements in ANSI N45.2.9-1974 have been endorsed by the NRC
in Regulatory Guide 1.88 as adequate for satisfying the recordkeeping
requirements of 10 CFR Part 50, Appendix B, which states in part that
``records shall be identifiable and retrievable.'' Additionally,
conditions in 10 CFR Part 50, Appendix B establish that ``[c]onsistent
with applicable regulatory requirements (including 10 CFR 50.71(d)(1)),
the applicant shall establish requirements concerning record retention,
such as duration, location, and assigned responsibility.'' ANSI
N.45.2.9-1974 also satisfies the requirements of 10 CFR 72.72 by
providing for adequate maintenance of records regarding the identity
and history of the spent fuel in storage. Such records would be subject
to and need to be protected from the same types of degradation
mechanisms as nuclear power plant Quality Assurance records.
Environmental Impacts of the Proposed Action: An exemption from the
requirement to store a duplicate set of ISFSI records at a separate
location has no impact on the environment. Storage of records does not
change the methods by which spent fuel will be handled and stored at
the Maine Yankee ISFSI and does not change the amount of effluents,
radiological or nonradiological, associated with the ISFSI.
Alternative to the Proposed Action: Since there is no environmental
impact associated with the proposed action, alternatives are not
evaluated other than the no action alternative. The alternative to the
proposed action would be to deny approval of the exemption and,
therefore, not allow storage of ISFSI spent fuel records at a single
qualified record storage facility. The no action alternative would
require the applicant to construct or identify a separate storage
facility; therefore, the environmental impacts of the proposed action
would be less than, or the same as, the no action alternative.
Agencies and Persons Consulted: On March 28, 2005, Maine State
Nuclear Safety Inspector Mr. Patrick Dostie was contacted regarding 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 Environmental Assessment, the Commission finds that
the proposed action of granting the exemption from 10 CFR 72.72(d), so
that Maine Yankee may store spent fuel records for the ISFSI in a
single records storage facility which meets the requirements of ANSI
N.45.2.9-1974, with the given exception listed in the Maine Yankee QAP,
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 necessary.
The request for exemption was docketed under 10 CFR Part 72, Docket
72-30. For further details with respect to this exemption request, see
the Maine Yankee letter requesting the exemption
[[Page 20608]]
dated November 29, 2004. Supporting documentation is available for
inspection at the NRC's Public Electronic Reading Room at https://
www.nrc.gov/reading-rm/adams.html. A copy of the Finding of No
Significant Impact can be found at this site using the Agencywide
Documents Access and Management System (ADAMS). These documents may
also be viewed electronically on the public computers located at the
NRC's Public Document Room (PDR), O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor
will copy documents for a fee. 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 at 1-800-397-4209 or (301)
415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 13th day of April 2005.
For the Nuclear Regulatory Commission.
Jeremy A. Smith,
Project Manager, Spent Fuel Project Office, Office of Nuclear Material
Safety and Safeguards.
[FR Doc. E5-1854 Filed 4-19-05; 8:45 am]
BILLING CODE 7590-01-P