Indiana Michigan Power Company; Donald C. Cook Nuclear Plant, Unit 1; Exemption, 59269-59270 [E9-27527]
Download as PDF
Federal Register / Vol. 74, No. 220 / Tuesday, November 17, 2009 / Notices
Dated at Rockville, Maryland, this 6th day
of November 2009.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. E9–27406 Filed 11–13–09; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2009–0503l; Docket No. 50–315]
Indiana Michigan Power Company;
Donald C. Cook Nuclear Plant, Unit 1;
Exemption
1.0
Background
The Indiana Michigan Power
Company (the licensee) is the holder of
Facility Operating License Nos. DPR–58,
which authorizes operation of the
Donald C. Cook Nuclear Plant, Unit 1
(CNP–1). The license provides, among
other things, that the facility is subject
to all rules, regulations, and orders of
the Nuclear Regulatory Commission
(NRC, the Commission) now or hereafter
in effect.
The facility consists of two
pressurized-water reactors located in
Berrien County in Michigan.
mstockstill on DSKH9S0YB1PROD with NOTICES
2.0
Request/Action
Title 10 of the Code of Federal
Regulations (10 CFR), part 26, section
205(d)(4) [10 CFR 26.205(d)(4)] provides
that during the first 60 days of a unit
outage, licensees need not meet the
requirements of 10 CFR 26.205(d)(3) for
individuals specified in 10 CFR
26.4(a)(1) through 10 CFR 26.4(a)(4),
while those individuals are working on
outage activities. However, 10 CFR
26.205(d)(4) also provides that the
licensee shall ensure that the
individuals specified in 10 CFR
26.4(a)(1) through (a)(3) have at least 3
days off in each successive (i.e., nonrolling) 15-day period and that the
individuals specified in 10 CFR
26.4(a)(4) have at least 1 day off in any
7-day period.
The less restrictive requirements of 10
CFR 26.205(d)(4) would be applied
following a period of normal plant
operation in which the workload and
overtime levels are controlled by 10 CFR
26.205(d)(3). As stated in 10 CFR
26.205(d)(4), the less restrictive work
hour requirements are permitted during
the first 60 days of a unit outage. Since
the current CNP–1 extended outage
commenced in September 2008, the first
60 days of the unit outage have already
elapsed.
VerDate Nov<24>2008
20:50 Nov 16, 2009
Jkt 220001
59269
The licensee adopted the regulations
of 10 CFR 26, subpart I, on October 1,
2009, and has been controlling work
hours accordingly. The proposed
scheduler exemption would allow the
less restrictive working hours of 10 CFR
26.205(d)(4) during a 60-day period
beginning within three days of issuance
of the exemption, rather than during the
first 60 days of the current unit outage
(which commenced in September 2008).
The exemption would include those
operations and maintenance personnel
required to support outage-related
activities, including preparations for
unit restart. The licensee would ensure
that the affected individuals in these
departments would not work excessive
overtime during the period immediately
preceding the application of 10 CFR
26.205(d)(4).
The exemption would continue to
serve the underlying purpose of 10 CFR
26, subpart I, in that assurance would be
provided such that cumulative fatigue of
individuals to safely and competently
perform their duties will not be
compromised.
No Undue Risk to Public Health and
Safety
3.0
Pursuant to 10 CFR 26.9, the
Commission may, upon application by
any interested person or upon its own
initiative, grant exemptions from the
requirements of 10 CFR part 26 when (1)
the exemptions are authorized by law,
will not present an undue risk to public
health or safety, are consistent with the
common defense and security, and are
otherwise in the public interest.
The proposed scheduler exemption
would allow for the use of the less
restrictive work hour requirements of 10
CFR 26.205(d)(4) for operations and
maintenance personnel to support
restart activities for CNP–1, which has
been in an extended outage since
September 20, 2008. This change to the
operation of the plant has no relation to
security issues. Therefore, the common
defense and security is not impacted by
this exemption.
Authorized by Law
Consistent With the Public Interest
This scheduler exemption would
allow the licensee to use the less
restrictive working hour limitations
provided in 10 CFR 26.205(d)(4) during
a 60 day period beginning within three
days of issuance of the exemption.
Because CNP–1 was already in an
extended outage during the
implementation of 10 CFR part 26,
Subpart I, the licensee has not been able
to apply the less restrictive working
hours provided for in 10 CFR
26.205(d)(4). This scheduler exemption
would merely place CNP–1 in a similar
position as licensees with outages that
commenced after implementing Subpart
I. As stated above, 10 CFR 26.9 allows
the NRC to grant exemptions from the
requirements of 10 CFR Part 26. The
NRC staff has determined that granting
of the licensee’s proposed exemption
will not result in a violation of the
Atomic Energy Act of 1954, as amended,
or the Commission’s regulations.
Therefore, the exemption is authorized
by law.
The proposed scheduler exemption
would allow the licensee to implement
the less restrictive work hour
requirements of 10 CFR 26.205(d)(4) to
allow flexibility in scheduling required
days off while accommodating the more
intensive work schedules that
accompany a unit outage. During the
CNP–1 restart period, the workload for
operations and maintenance personnel
will undergo a temporary but significant
increase due to filling, venting, flushing,
calibration, and testing evolutions
necessitated by the repairs to the
secondary and electrical generation
systems and components. These
evolutions are in addition to the normal
unit startup activities involving
operation and surveillance testing of
primary systems and components.
Ensuring a sufficient number of
qualified personnel are available to
support these activities is in the interest
of overall public health and safety.
Therefore, this scheduler exemption is
consistent with the public interest.
PO 00000
Discussion
Frm 00157
Fmt 4703
Sfmt 4703
The underlying purpose of 10 CFR
26.205(d)(4) is to provide licensees
flexibility in scheduling required days
off while accommodating the more
intense work schedules associated with
a unit outage, while assuring that
cumulative fatigue does not compromise
the abilities of individuals to safely and
competently perform their duties.
Therefore, no new accident precursors
are created by invoking the less
restrictive work hour limitations on a
date commensurate with the start of
those activities supporting the restart of
CNP–1, provided that the licensee has
effectively managed fatigue for the
affected individuals prior to this date.
Thus, the probability of postulated
accidents is not increased. Also, based
on the above, the consequences of
postulated accidents are not increased.
Therefore, there is no undue risk to
public health and safety.
Consistent With Common Defense and
Security
E:\FR\FM\17NON1.SGM
17NON1
59270
Federal Register / Vol. 74, No. 220 / Tuesday, November 17, 2009 / Notices
4.0 Conclusion
Accordingly, the Commission has
determined that, pursuant to 10 CFR
26.9, the exemption is authorized by
law, will not endanger life or property
nor present an undue risk to the public
health and safety, is consistent with the
common defense and security, and is
otherwise in the public interest.
Therefore, the Commission hereby
grants Indiana Michigan Power
Company an exemption from the
requirements of 10 CFR 26.205(d)(4) for
the Donald C. Cook Nuclear Plant, Unit
1.
Pursuant to 10 CFR 51.32, the
Commission has determined that the
granting of this exemption will not have
a significant effect on the quality of the
human environment (74 FR 58063).
This exemption is effective upon
issuance, and implementation of the
work hour limitations as specified in 10
CFR 26.205(d)(4) for CNP–1 operations
and maintenance personnel working on
outage activities associated with unit
restart will commence no later than
November 13, 2009. The licensee may
implement the work hour provisions of
10 CFR 26.205(d)(4) for 60 days or until
completion of the current CNP–1 forced
outage, whichever is shorter. The
licensee may implement the provisions
of 10 CFR 26.205(d)(6), if applicable.
Dated at Rockville, Maryland, this 10th day
of November 2009.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. E9–27527 Filed 11–16–09; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
mstockstill on DSKH9S0YB1PROD with NOTICES
Advisory Committee on Reactor
Safeguards
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 December 3–5, 2009, 11545 Rockville
Pike, Rockville, Maryland. The date of
this meeting was previously published
in the Federal Register on Monday,
October 14, 2009, (74 FR 52829–52830).
Thursday, December 3, 2009,
Conference Room T2–B3, 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
VerDate Nov<24>2008
20:50 Nov 16, 2009
Jkt 220001
opening remarks regarding the conduct
of the meeting.
8:35 a.m.–10 a.m.: License Renewal
Application for the Prairie Island
Nuclear Generating Plant, Units 1 and
2 (Open)—The Committee will hear
presentations by and hold discussions
with representatives of the NRC staff
and Northern States Power Company
regarding the license renewal
application for the Prairie Island
Nuclear Generating Plant, Units 1 and 2,
the associated NRC staff’s final Safety
Evaluation Report (SER), and related
matters.
10:15 a.m.–12:15 p.m.: Draft Final
Regulatory Guide 1.205, ‘‘RiskInformed, Performance-Based Fire
Protection for Existing Light-Water
Nuclear Power Plants,’’ and Draft Final
Standard Review Plan (SRP) Section
9.5.1.2, ‘‘Risk-Informed, PerformanceBased Fire Protection’’ (Open)—The
Committee will hear presentations by
and hold discussions with
representatives of the NRC staff and the
industry regarding draft final Regulatory
Guide 1.205, ‘‘Risk-Informed,
Performance-Based Fire Protection for
existing Light-Water Nuclear Power
Plants,’’ draft final SRP Section 9.5.1.2,
‘‘Risk-Informed, Performance-Based Fire
Protection,’’ NRC staff’s resolution of
public comments, and related matters.
1:15 p.m.–3:15 p.m.: Long-Term Core
Cooling Approach for the Economic
Simplified Boiling Water Reactor
(ESBWR) Design (Open/Closed)—The
Committee will hear presentations by
and hold discussions with
representatives of the NRC staff and
General Electric—Hitachi Nuclear
Energy (GEH) regarding the long-term
core cooling approach for the ESBWR
design. [Note: A portion of this session
may be closed to protect information
that is proprietary to GEH or its
contractors pursuant to 5 U.S.C. 552b
(c)(4).]
3:30 p.m.–5 p.m.: Draft Final Revision
1 to Regulatory Guide 1.151 (DG–1178),
‘‘Instrument Sensing Lines’’ (Open)—
The Committee will hear presentations
by and hold discussions with
representatives of the NRC staff
regarding draft final Revision 1 to
Regulatory Guide 1.151 (DG–1178),
‘‘Instrument Sensing Lines,’’ NRC staff’s
resolution of public comments, and
related matters.
5:15 p.m.–5:45 p.m.: Subcommittee
Reports (Open)—The Committee will
hear reports by and hold discussions
with the Chairmen of the Reliability &
PRA and the AP1000 Subcommittees
regarding: NRC’s proposed policy
statement on Safety Culture, and
Chapters 7 and 9 of the draft SER
associated with the AP1000 Design
PO 00000
Frm 00158
Fmt 4703
Sfmt 4703
Control Document Amendment that
were discussed on November 12, and
November 19–20, 2009, respectively.
5:45 p.m.–7 p.m.: Preparation of
ACRS Reports (Open)—The Committee
will discuss proposed ACRS reports on
matters discussed during this meeting.
Friday, December 4, 2009, Conference
Room T2–B3, 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.–9:15 a.m.: Discussion of
topics for Meeting with the Commission
(Open)—The Committee will discuss
the following topics scheduled for the
meeting with the Commission:
Inspections, Tests, Analyses, and
Acceptance Criteria (ITAAC)/Design
Acceptance Criteria (DAC) Closure
Process; Amendment to the AP1000
Design Control Document; ThreeDimensional Finite Element Analysis of
the Oyster Creek Drywell Shell; Beaver
Valley Containment Liner Corrosion;
and Cyber Security Programs for
Nuclear Power Plants.
9:30 a.m.–11:30 a.m.: Meeting with
the Commission—Commissioner’s
Conference Room, One White Flint
North (Open)—The Committee will
meet with the Commission to discuss
topics listed under the previous item.
1:15 p.m.–2:30 p.m.: Future ACRS
Activities/Report of the Planning and
Procedures Subcommittee (Open/
Closed)—The Committee will discuss
the recommendations of the Planning
and Procedures Subcommittee regarding
items proposed for consideration by the
Full Committee during future ACRS
meetings, including anticipated
workload and member assignments, and
related matters. [Note: A portion of this
session may be closed pursuant to 5
U.S.C. 552b (c)(2) and (6) to discuss
organizational and personnel matters
that relate solely to internal personnel
rules and practices of ACRS, and
information the release of which would
constitute a clearly unwarranted
invasion of personal privacy.]
2:30 p.m.–2:45 p.m.: Reconciliation of
ACRS Comments and
Recommendations (Open)—The
Committee will discuss the responses
from the NRC Executive Director for
Operations to comments and
recommendations included in recent
ACRS reports and letters.
2:45 p.m.–3 p.m.: Election of ACRS
Officers for CY–2010 (Open)—The
Committee will elect the Chairman and
Vice-Chairman for the ACRS and
E:\FR\FM\17NON1.SGM
17NON1
Agencies
[Federal Register Volume 74, Number 220 (Tuesday, November 17, 2009)]
[Notices]
[Pages 59269-59270]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-27527]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2009-0503l; Docket No. 50-315]
Indiana Michigan Power Company; Donald C. Cook Nuclear Plant,
Unit 1; Exemption
1.0 Background
The Indiana Michigan Power Company (the licensee) is the holder of
Facility Operating License Nos. DPR-58, which authorizes operation of
the Donald C. Cook Nuclear Plant, Unit 1 (CNP-1). The license provides,
among other things, that the facility is subject to all rules,
regulations, and orders of the Nuclear Regulatory Commission (NRC, the
Commission) now or hereafter in effect.
The facility consists of two pressurized-water reactors located in
Berrien County in Michigan.
2.0 Request/Action
Title 10 of the Code of Federal Regulations (10 CFR), part 26,
section 205(d)(4) [10 CFR 26.205(d)(4)] provides that during the first
60 days of a unit outage, licensees need not meet the requirements of
10 CFR 26.205(d)(3) for individuals specified in 10 CFR 26.4(a)(1)
through 10 CFR 26.4(a)(4), while those individuals are working on
outage activities. However, 10 CFR 26.205(d)(4) also provides that the
licensee shall ensure that the individuals specified in 10 CFR
26.4(a)(1) through (a)(3) have at least 3 days off in each successive
(i.e., non-rolling) 15-day period and that the individuals specified in
10 CFR 26.4(a)(4) have at least 1 day off in any 7-day period.
The less restrictive requirements of 10 CFR 26.205(d)(4) would be
applied following a period of normal plant operation in which the
workload and overtime levels are controlled by 10 CFR 26.205(d)(3). As
stated in 10 CFR 26.205(d)(4), the less restrictive work hour
requirements are permitted during the first 60 days of a unit outage.
Since the current CNP-1 extended outage commenced in September 2008,
the first 60 days of the unit outage have already elapsed.
The licensee adopted the regulations of 10 CFR 26, subpart I, on
October 1, 2009, and has been controlling work hours accordingly. The
proposed scheduler exemption would allow the less restrictive working
hours of 10 CFR 26.205(d)(4) during a 60-day period beginning within
three days of issuance of the exemption, rather than during the first
60 days of the current unit outage (which commenced in September 2008).
The exemption would include those operations and maintenance personnel
required to support outage-related activities, including preparations
for unit restart. The licensee would ensure that the affected
individuals in these departments would not work excessive overtime
during the period immediately preceding the application of 10 CFR
26.205(d)(4).
The exemption would continue to serve the underlying purpose of 10
CFR 26, subpart I, in that assurance would be provided such that
cumulative fatigue of individuals to safely and competently perform
their duties will not be compromised.
3.0 Discussion
Pursuant to 10 CFR 26.9, the Commission may, upon application by
any interested person or upon its own initiative, grant exemptions from
the requirements of 10 CFR part 26 when (1) the exemptions are
authorized by law, will not present an undue risk to public health or
safety, are consistent with the common defense and security, and are
otherwise in the public interest.
Authorized by Law
This scheduler exemption would allow the licensee to use the less
restrictive working hour limitations provided in 10 CFR 26.205(d)(4)
during a 60 day period beginning within three days of issuance of the
exemption. Because CNP-1 was already in an extended outage during the
implementation of 10 CFR part 26, Subpart I, the licensee has not been
able to apply the less restrictive working hours provided for in 10 CFR
26.205(d)(4). This scheduler exemption would merely place CNP-1 in a
similar position as licensees with outages that commenced after
implementing Subpart I. As stated above, 10 CFR 26.9 allows the NRC to
grant exemptions from the requirements of 10 CFR Part 26. The NRC staff
has determined that granting of the licensee's proposed exemption will
not result in a violation of the Atomic Energy Act of 1954, as amended,
or the Commission's regulations. Therefore, the exemption is authorized
by law.
No Undue Risk to Public Health and Safety
The underlying purpose of 10 CFR 26.205(d)(4) is to provide
licensees flexibility in scheduling required days off while
accommodating the more intense work schedules associated with a unit
outage, while assuring that cumulative fatigue does not compromise the
abilities of individuals to safely and competently perform their
duties. Therefore, no new accident precursors are created by invoking
the less restrictive work hour limitations on a date commensurate with
the start of those activities supporting the restart of CNP-1, provided
that the licensee has effectively managed fatigue for the affected
individuals prior to this date. Thus, the probability of postulated
accidents is not increased. Also, based on the above, the consequences
of postulated accidents are not increased. Therefore, there is no undue
risk to public health and safety.
Consistent With Common Defense and Security
The proposed scheduler exemption would allow for the use of the
less restrictive work hour requirements of 10 CFR 26.205(d)(4) for
operations and maintenance personnel to support restart activities for
CNP-1, which has been in an extended outage since September 20, 2008.
This change to the operation of the plant has no relation to security
issues. Therefore, the common defense and security is not impacted by
this exemption.
Consistent With the Public Interest
The proposed scheduler exemption would allow the licensee to
implement the less restrictive work hour requirements of 10 CFR
26.205(d)(4) to allow flexibility in scheduling required days off while
accommodating the more intensive work schedules that accompany a unit
outage. During the CNP-1 restart period, the workload for operations
and maintenance personnel will undergo a temporary but significant
increase due to filling, venting, flushing, calibration, and testing
evolutions necessitated by the repairs to the secondary and electrical
generation systems and components. These evolutions are in addition to
the normal unit startup activities involving operation and surveillance
testing of primary systems and components. Ensuring a sufficient number
of qualified personnel are available to support these activities is in
the interest of overall public health and safety. Therefore, this
scheduler exemption is consistent with the public interest.
[[Page 59270]]
4.0 Conclusion
Accordingly, the Commission has determined that, pursuant to 10 CFR
26.9, the exemption is authorized by law, will not endanger life or
property nor present an undue risk to the public health and safety, is
consistent with the common defense and security, and is otherwise in
the public interest. Therefore, the Commission hereby grants Indiana
Michigan Power Company an exemption from the requirements of 10 CFR
26.205(d)(4) for the Donald C. Cook Nuclear Plant, Unit 1.
Pursuant to 10 CFR 51.32, the Commission has determined that the
granting of this exemption will not have a significant effect on the
quality of the human environment (74 FR 58063).
This exemption is effective upon issuance, and implementation of
the work hour limitations as specified in 10 CFR 26.205(d)(4) for CNP-1
operations and maintenance personnel working on outage activities
associated with unit restart will commence no later than November 13,
2009. The licensee may implement the work hour provisions of 10 CFR
26.205(d)(4) for 60 days or until completion of the current CNP-1
forced outage, whichever is shorter. The licensee may implement the
provisions of 10 CFR 26.205(d)(6), if applicable.
Dated at Rockville, Maryland, this 10th day of November 2009.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. E9-27527 Filed 11-16-09; 8:45 am]
BILLING CODE 7590-01-P