[Federal Register Volume 77, Number 53 (Monday, March 19, 2012)]
[Notices]
[Pages 16091-16098]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2012-6547]
[[Page 16091]]
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NUCLEAR REGULATORY COMMISSION
[NRC-2012-0068]
Order Modifying Licenses With Regard to Requirements for
Mitigation Strategies for Beyond-Design-Basis External Events
(Effective Immediately)
In the Matter of:
ALL POWER REACTOR LICENSEES AND Docket Nos. (as shown in Attachment
HOLDERS OF CONSTRUCTION 1) License Nos. (as shown in
PERMITS IN ACTIVE OR DEFERRED Attachment 1) or Construction
STATUS. Permit Nos. (as shown in
Attachment 1))
EA-12-049
I
The Licensees and construction permits (CP) holders \1\ identified
in Attachment 1 to this Order hold licenses and CPs issued by the U.S.
Nuclear Regulatory Commission (NRC or Commission) authorizing operation
and/or construction of nuclear power plants in accordance with the
Atomic Energy Act of 1954, as amended, and Title 10 of the Code of
Federal Regulations (10 CFR) Part 50, ``Domestic Licensing of
Production and Utilization Facilities,'' and Part 52, ``Licenses,
Certifications, and Approvals for Nuclear Power Plants.''
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\1\ CP holders, as used in this Order, includes CPs, in active
or deferred status, as identified in Attachment 1 to this Order
(i.e., Watts Bar, Unit 2; and Bellefonte, Units 1 and 2)
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II
On March 11, 2011, a magnitude 9.0 earthquake struck off the coast
of the Japanese island of Honshu. The earthquake resulted in a large
tsunami, estimated to have exceeded 14 meters (45 feet) in height, that
inundated the Fukushima Dai-ichi nuclear power plant site. The
earthquake and tsunami produced widespread devastation across
northeastern Japan and significantly affected the infrastructure and
industry in the northeastern coastal areas of Japan.
When the earthquake occurred, Fukushima Dai-ichi Units 1, 2, and 3
were in operation and Units 4, 5, and 6 were shut down for routine
refueling and maintenance activities. The Unit 4 reactor fuel was
offloaded to the Unit 4 spent fuel pool (SFP). Following the
earthquake, the three operating units automatically shut down and
offsite power was lost to the entire facility. The emergency diesel
generators (EDGs) started at all six units providing alternating
current (ac) electrical power to critical systems at each unit. The
facility response to the earthquake appears to have been normal.
Approximately 40 minutes following the earthquake and shutdown of
the operating units, the first large tsunami wave inundated the site,
followed by additional waves. The tsunami caused extensive damage to
site facilities and resulted in a complete loss of all ac electrical
power at Units 1 through 5, a condition known as station blackout. In
addition, all direct current electrical power was lost early in the
event on Units 1 and 2 and after some period of time at the other
units. Unit 6 retained the function of one air-cooled EDG. Despite
their actions, the operators lost the ability to cool the fuel in the
Unit 1 reactor after several hours, in the Unit 2 reactor after about
70 hours, and in the Unit 3 reactor after about 36 hours, resulting in
damage to the nuclear fuel shortly after the loss of cooling
capabilities.
Following the events at the Fukushima Dai-ichi nuclear power plant,
the NRC established a senior-level agency task force referred to as the
Near-Term Task Force (NTTF). The NTTF was tasked with conducting a
systematic and methodical review of the NRC regulations and processes
and determining if the agency should make additional improvements to
these programs in light of the events at Fukushima Dai-ichi. As a
result of this review, the NTTF developed a comprehensive set of
recommendations, documented in SECY-11-0093, ``Near-Term Report and
Recommendations for Agency Actions Following the Events in Japan,''
dated July 12, 2011. These recommendations were enhanced by the NRC
staff following interactions with stakeholders. Documentation of the
staff's efforts is contained in SECY-11-0124, ``Recommended Actions to
be Taken Without Delay From the Near-Term Task Force Report,'' dated
September 9, 2011, and SECY-11-0137, ``Prioritization of Recommended
Actions to be Taken in Response to Fukushima Lessons Learned,'' dated
October 3, 2011.
As directed by the Commission's staff requirements memorandum (SRM)
for SECY-11-0093, the NRC staff reviewed the NTTF recommendations
within the context of the NRC's existing regulatory framework and
considered the various regulatory vehicles available to the NRC to
implement the recommendations. SECY-11-0124 and SECY-11-0137
established the staff's prioritization of the recommendations based
upon the potential safety enhancements.
Since receiving the Commission's direction in SRM-SECY-11-0124 and
SRM-SECY-11-0137, the NRC staff conducted public meetings to discuss
enhanced mitigation strategies intended to maintain or restore core
cooling, containment, and SFP cooling capabilities following beyond-
design-basis external events. At these meetings, the industry described
its proposal for a Diverse and Flexible Mitigation Capability (FLEX),
as documented in the Nuclear Energy Institute's (NEI's) letter dated
December 16, 2011 (Agency Documents Access and Management System
(ADAMS) Accession No. ML11353A008). FLEX is proposed as a strategy to
fulfill the key safety functions of core cooling, containment
integrity, and spent fuel cooling. Stakeholder input influenced the
staff to pursue a more performance-based approach to improve the safety
of operating power reactors than envisioned in NTTF Recommendation 4.2,
SECY-11-0124, and SECY-11-0137.
Current regulatory requirements and existing plant capabilities
allow the NRC to conclude that a sequence of events such as the
Fukushima Dai-ichi accident is unlikely to occur in the U.S. Therefore,
continued operation and continued licensing activities do not pose an
imminent threat to public health and safety. However, NRC's assessment
of new insights from the events at Fukushima Dai-ichi leads the staff
to conclude that additional requirements must be imposed on Licensees
or CP holders to increase the
[[Page 16092]]
capability of nuclear power plants to mitigate beyond-design-basis
external events. These additional requirements are needed to provide
adequate protection to public health and safety, as set forth in
Section III of this Order.
Guidance and strategies required by this Order would be available
if the loss of power, motive force, and normal access to the ultimate
heat sink to prevent fuel damage in the reactor and SFP, affected all
units at a site simultaneously. This Order requires a three-phase
approach for mitigating beyond-design-basis external events. The
initial phase requires the use of installed equipment and resources to
maintain or restore core cooling, containment, and SFP cooling. The
transition phase requires providing sufficient, portable, onsite
equipment and consumables to maintain or restore these functions until
they can be accomplished with resources brought from off site. The
final phase requires obtaining sufficient offsite resources to sustain
those functions indefinitely.
Additional details on an acceptable approach for complying with
this Order will be contained in final Interim Staff Guidance (ISG)
scheduled to be issued by the NRC in August 2012. This guidance will
also include a template to be used for the plan that will be submitted
in accordance with Section IV, Condition C.1 below.
III
Reasonable assurance of adequate protection of the public health
and safety and assurance of the common defense and security are the
fundamental NRC regulatory objectives. Compliance with NRC requirements
plays a critical role in giving the NRC confidence that Licensees or CP
holders are maintaining an adequate level of public health and safety
and common defense and security. While compliance with NRC requirements
presumptively assures adequate protection, new information may reveal
that additional requirements are warranted. In such situations, the
Commission may act in accordance with its statutory authority under
Section 161 of the Atomic Energy Act of 1954, as amended, to require
Licensees or CP holders to take action in order to protect health and
safety and common defense and security.
To protect public health and safety from the inadvertent release of
radioactive materials, the NRC's defense-in-depth strategy includes
multiple layers of protection: (1) Prevention of accidents by virtue of
the design, construction, and operation of the plant; (2) mitigation
features to prevent radioactive releases should an accident occur; and
(3) emergency preparedness programs that include measures such as
sheltering and evacuation. The defense-in-depth strategy also provides
for multiple physical barriers to contain the radioactive materials in
the event of an accident. The barriers are the fuel cladding, the
reactor coolant pressure boundary, and the containment. These defense-
in-depth features are embodied in the existing regulatory requirements
and thereby provide adequate protection of the public health and
safety.
Following the events of September 11, 2001, the NRC issued Order
EA-02-026, dated February 25, 2002, which required Licensees to develop
mitigating strategies related to the key safety functions of core
cooling, containment, and SFP cooling. NEI Document 06-12, ``B.5.b
Phase 2 & 3 Submittal Guideline'' (ADAMS Accession No. ML070090060)
provides guidelines that describe the necessary mitigating strategies.
The NRC endorsed these guidelines in a letter dated December 22, 2006,
designated as Official Use Only. Those mitigating strategies were
developed in the context of a localized event that was envisioned to
challenge portions of a single unit. The events at Fukushima, however,
demonstrate that beyond-design-basis external events may adversely
affect: (1) More than one unit at a site with two or more units, and
(2) multiple safety functions at each of several units located on the
same site.
The events at Fukushima further highlight the possibility that
extreme natural phenomena could challenge the prevention, mitigation,
and emergency preparedness defense-in-depth layers. To address the
uncertainties associated with beyond-design-basis external events, the
NRC is requiring additional defense-in-depth measures at licensed
nuclear power reactors so that the NRC can continue to have reasonable
assurance of adequate protection of public health and safety in
mitigating the consequences of a beyond-design-basis external event.
The strategies and guidance developed and implemented by Licensees
or CP holders in response to the requirements imposed by this Order
will provide the necessary capabilities to supplement those of the
permanently installed plant structures, systems, and components that
could become unavailable following beyond-design-basis external events.
These strategies and guidance will enhance the safety and preparedness
capabilities established following September 11, 2001, and codified as
10 CFR 50.54(hh)(2). In order to address the potential for more
widespread effects of beyond design basis external events, this Order
requires strategies with increased capacity to implement protective
actions concurrently at multiple units at a site. The strategies shall
be developed to add multiple ways to maintain or restore core cooling,
containment and SFP cooling capabilities in order to improve the
defense-in-depth of licensed nuclear power reactors.
The Commission has determined that ensuring adequate protection of
public health and safety requires that power reactor Licensees and CP
holders develop, implement and maintain guidance and strategies to
restore or maintain core cooling, containment, and SFP cooling
capabilities in the event of a beyond-design-basis external event.
These new requirements provide a greater mitigation capability
consistent with the overall defense-in-depth philosophy, and,
therefore, greater assurance that the challenges posed by beyond-
design-basis external events to power reactors do not pose an undue
risk to public health and safety. In order to provide reasonable
assurance of adequate protection of public health and safety, all
operating reactor licenses and CPs under Part 50 identified in
Attachment 1 to this Order shall be modified to include the
requirements identified in Attachment 2 to this Order. All combined
licenses (COLs) under 10 CFR part 52 identified in Attachment 1 to this
Order shall be modified to include the requirements identified in
Attachment 3 to this Order.
Accordingly, the NRC has concluded that these measures are
necessary to ensure adequate protection of public health and safety
under the provisions of the backfit rule, 10 CFR 50.109(a)(4)(ii), and
is requiring Licensee or CP holder action. In addition, pursuant to 10
CFR 2.202, the NRC finds that the public health, safety and interest
require that this Order be made immediately effective.
IV
Accordingly, pursuant to Sections 161b, 161i, 161o, and 182 of the
Atomic Energy Act of 1954, as amended, and the Commission's regulations
in 10 CFR 2.202, and 10 CFR Parts 50 and 52, it is hereby ordered,
effective immediately, that all licenses and construction permits
identified in attachment 1 to this order are modified as follows:
A. 1. All holders of CPs issued under Part 50 shall,
notwithstanding the provisions of any Commission regulation or CPs to
the contrary, comply with the requirements described in Attachment 2 to
this Order except to the extent that a more stringent
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requirement is set forth in the CP. These CP holders shall complete
full implementation prior to issuance of an operating license.
2. All holders of operating licenses issued under Part 50 shall,
notwithstanding the provisions of any Commission regulation or license
to the contrary, comply with the requirements described in Attachment 2
to this Order except to the extent that a more stringent requirement is
set forth in the license. These Licensees shall promptly start
implementation of the requirements in Attachment 2 to the Order and
shall complete full implementation no later than two (2) refueling
cycles after submittal of the overall integrated plan, as required in
Condition C.1.a, or December 31, 2016, whichever comes first.
3. All holders of COLs issued under Part 52 shall, notwithstanding
the provisions of any Commission regulation or license to the contrary,
comply with the requirements described in Attachment 3 to this Order
except to the extent that a more stringent requirement is set forth in
the license. These Licensees shall promptly start implementation of the
requirements in Attachment 3 to the Order and shall complete full
implementation prior to initial fuel load.
B.1. All Licensees and CP holders shall, within twenty (20) days of
the date of this Order, notify the Commission, (1) if they are unable
to comply with any of the requirements described in Attachment 2 or
Attachment 3, (2) if compliance with any of the requirements is
unnecessary in their specific circumstances, or (3) if implementation
of any of the requirements would cause the Licensee or CP holder to be
in violation of the provisions of any Commission regulation or the
facility license. The notification shall provide the Licensee's or CP
holder's justification for seeking relief from or variation of any
specific requirement.
2. Any Licensee or CP holder that considers that implementation of
any of the requirements described in Attachment 2 or Attachment 3 to
this Order would adversely impact safe and secure operation of the
facility must notify the Commission, within twenty (20) days of this
Order, of the adverse safety impact, the basis for its determination
that the requirement has an adverse safety impact, and either a
proposal for achieving the same objectives specified in Attachment 2 or
Attachment 3 requirement in question, or a schedule for modifying the
facility to address the adverse safety condition. If neither approach
is appropriate, the Licensee or CP holder must supplement its response
to Condition B.1 of this Order to identify the condition as a
requirement with which it cannot comply, with attendant justifications
as required in Condition B.1.
C.1. a. All holders of operating licenses issued under Part 50
shall by February 28, 2013, submit to the Commission for review an
overall integrated plan including a description of how compliance with
the requirements described in Attachment 2 will be achieved.
b. All holders of CPs issued under Part 50 or COLs issued under
Part 52 shall, within one (1) year after issuance of the final ISG,
submit to the Commission for review an overall integrated plan
including a description of how compliance with the requirements
described in Attachment 2 or Attachment 3 will be achieved.
2. All Licensees and holders of CPs shall provide an initial status
report sixty (60) days following issuance of the final ISG and at six
(6)-month intervals following submittal of the overall integrated plan,
as required in Condition C.1, which delineates progress made in
implementing the requirements of this Order.
3. All Licensees and CP holders shall report to the Commission when
full compliance with the requirements described in Attachment 2 or
Attachment 3 is achieved.
Licensee or CP holders responses to Conditions B.1, B.2, C.1, C.2,
and C.3, above shall be submitted in accordance with 10 CFR 50.4 and 10
CFR 52.3, as applicable.
As applicable, the Director, Office of Nuclear Reactor Regulation
or the Director, Office of New Reactors may, in writing, relax or
rescind any of the above conditions upon demonstration by the Licensee
or CP holder of good cause.
V
In accordance with 10 CFR 2.202, the Licensee or CP holder must,
and any other person adversely affected by this Order may, submit an
answer to this Order, and may request a hearing on this Order, within
20 days of the date of this Order. Where good cause is shown,
consideration will be given to extending the time to answer or to
request a hearing. A request for extension of time in which to submit
an answer or request a hearing must be made in writing to the Director,
Office of Nuclear Reactor Regulation or to the Director, Office of New
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and
include a statement of good cause for the extension. The answer may
consent to this Order.
If a hearing is requested by a Licensee, CP holder or a person
whose interest is adversely affected, the Commission will issue an
Order designating the time and place of any hearings. If a hearing is
held, the issue to be considered at such hearing shall be whether this
Order should be sustained. Pursuant to 10 CFR 2.202(c)(2)(i), the
licensee, CP holder or any other person adversely affected by this
Order, may, in addition to demanding a hearing, at the time the answer
is filed or sooner, move the presiding officer to set aside the
immediate effectiveness of the Order on the ground that the Order,
including the need for immediate effectiveness, is not based on
adequate evidence but on mere suspicion, unfounded allegations, or
error.
All documents filed in NRC adjudicatory proceedings, including a
request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC E-Filing rule (72 FR 49139,
August 28, 2007). The E-Filing process requires participants to submit
and serve all adjudicatory documents over the internet, or in some
cases to mail copies on electronic storage media. Participants may not
submit paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at (301) 415-1677, to request (1) a digital ID certificate,
which allows the participant (or its counsel or representative) to
digitally sign documents and access the E-Submittal server for any
proceeding in which it is participating; and (2) advise the Secretary
that the participant will be submitting a request or petition for
hearing (even in instances in which the participant, or its counsel or
representative, already holds an NRC-issued digital ID certificate).
Based upon this information, the Secretary will establish an electronic
docket for the hearing in this proceeding if the Secretary has not
already established an electronic docket.
Information about applying for a digital ID certificate is
available on
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NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing the E-
Submittal server are detailed in NRC's ``Guidance for Electronic
Submission,'' which is available on the agency's public Web site at
http://www.nrc.gov/site-help/e-submittals.html. Participants may
attempt to use other software not listed on the web site, but should
note that the NRC's E-Filing system does not support unlisted software,
and the NRC Meta System Help Desk will not be able to offer assistance
in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, web-based submission form. In order to
serve documents through the Electronic Information Exchange, users will
be required to install a web browser plug-in from the NRC web site.
Further information on the web-based submission form, including the
installation of the Web browser plug-in, is available on the NRC's
public Web site at http://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with NRC guidance
available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC Office of the General Counsel and any others
who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System
Help Desk through the ``Contact Us'' link located on the NRC Web site
at http://www.nrc.gov/site-help/e-submittals.html, by email at
[email protected], or by a toll-free call at (866) 672-7640. The
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m.,
Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, Sixteenth
Floor, One White Flint North, 11555 Rockville Pike, Rockville,
Maryland, 20852, Attention: Rulemaking and Adjudications Staff.
Participants filing a document in this manner are responsible for
serving the document on all other participants. Filing is considered
complete by first-class mail as of the time of deposit in the mail, or
by courier, express mail, or expedited delivery service upon depositing
the document with the provider of the service. A presiding officer,
having granted an exemption request from using E-Filing, may require a
participant or party to use E-Filing if the presiding officer
subsequently determines that the reason for granting the exemption from
use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in
NRC's electronic hearing docket, which is available to the public at
http://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the
Commission, or the presiding officer. Participants are requested not to
include personal privacy information, such as social security numbers,
home addresses, or home phone numbers in their filings, unless an NRC
regulation or other law requires submission of such information. With
respect to copyrighted works, except for limited excerpts that serve
the purpose of the adjudicatory filings and would constitute a Fair Use
application, participants are requested not to include copyrighted
materials in their submission.
If a person other than the Licensee or CP holder requests a
hearing, that person shall set forth with particularity the manner in
which his interest is adversely affected by this Order and shall
address the criteria set forth in 10 CFR 2.309(d).
In the absence of any request for hearing, or written approval of
an extension of time in which to request a hearing, the provisions
specified in Section IV above shall be final twenty (20) days from the
date of this Order without further order or proceedings. If an
extension of time for requesting a hearing has been approved, the
provisions specified in Section IV shall be final when the extension
expires if a hearing request has not been received. An answer or a
request for hearing shall not stay the immediate effectiveness of this
order.
For The Nuclear Regulatory Commission.
Dated this 12th day of March 2012.
Eric J. Leeds,
Director, Office of Nuclear Reactor Regulation.
Michael R. Johnson,
Director, Office of New Reactors.
Power Reactor Licensees and Holders of Construction Permits in Active
or Deferred Status
Arkansas Nuclear One
Entergy Operations, Inc., Docket Nos. 50-313 and 50-368, License Nos.
DPR-51 and NPF-6
Mr. Christopher J. Schwarz, Vice President, Operations, Entergy
Operations, Inc., Arkansas Nuclear One, 1448 S.R. 333, Russellville, AR
72802
Beaver Valley Power Station
First Energy Nuclear Operating Co., Docket Nos. 50-334 and 50-412,
License Nos. DPR-66 and NPF-73
Mr. Paul A. Harden, Site Vice President, FirstEnergy Nuclear Operating
Company, Mail Stop A-BV-SEB1, P.O. Box 4, Route 168, Shippingport, PA
15077
Bellefonte Nuclear Power Station
Tennessee Valley Authority, Docket Nos. 50-438 and 50-439, Construction
Permit Nos. CPPR No. 122 and CPPR No. 123
Mr. Michael D. Skaggs, Senior Vice President, Nuclear Generation
Development and Construction, Tennessee Valley Authority, 6A Lookout
Place, 1101 Market Street, Chattanooga, TN 37402-2801
[[Page 16095]]
Braidwood Station
Exelon Generation Co., LLC, Docket Nos. STN 50-456 and STN 50-457,
License Nos. NPF-72 and NPF-77
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
Browns Ferry Nuclear Plant
Tennessee Valley Authority, Docket Nos. 50-259, 50-260 and 50-296,
License Nos. DPR-33, DPR-52 and DPR-68
Mr. Preston D. Swafford, Chief Nuclear Officer and Executive Vice
President, Tennessee Valley Authority, 3R Lookout Place, 1101 Market
Street, Chattanooga, TN 37402-2801
Brunswick Steam Electric Plant
Carolina Power & Light Co., Docket Nos. 50-325 and 50-324, License Nos.
DPR-71 and DPR-62
Mr. Michael J. Annacone, Vice President, Carolina Power & Light
Company, Brunswick Steam Electric Plant, P.O. Box 10429, Southport, NC
28461
Byron Station
Exelon Generation Co., LLC, Docket Nos. STN 50-454 and STN 50-455,
License Nos. NPF-37 and NPF-66
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
Callaway Plant
Union Electric Co., Docket No. 50-483, License No. NPF-30
Mr. Adam C. Heflin, Senior Vice President and Chief Nuclear Officer,
Union Electric Company, P.O. Box 620, Fulton, MO 65251
Calvert Cliffs Nuclear Power Plant
Calvert Cliffs Nuclear Power Plant, LLC, Docket Nos. 50-317 and 50-318,
License Nos. DPR-53 and DPR-69
Mr. George H. Gellrich, Vice President, Calvert Cliffs Nuclear Power
Plant, LLC, Calvert Cliffs Nuclear Power Plant, 1650 Calvert Cliffs
Parkway, Lusby, MD 20657-4702
Catawba Nuclear Station
Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, License Nos.
NPF-35 and NPF-52
Mr. James R. Morris, Site Vice President, Duke Energy Carolinas, LLC,
Catawba Nuclear Station, 4800 Concord Road, York, SC 29745
Clinton Power Station
Exelon Generation Co., LLC, Docket No. 50-461, License No. NPF-62
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
Columbia Generating Station
Energy Northwest, Docket No. 50-397, License No. NPF-21
Mr. Mark E. Reddemann, Chief Executive Officer, Energy Northwest, MD
1023, P.O. Box 968, Richland, WA 99352
Comanche Peak Nuclear Power Plant
Luminant Generation Co., LLC, Docket Nos. 50-445 and 50-446, License
Nos. NPF-87 and NPF-89
Mr. Rafael Flores, Senior Vice President and Chief Nuclear Officer,
Luminant Generation Company, LLC, Attn: Regulatory Affairs, P.O. Box
1002, Glen Rose, TX 76043
Cooper Nuclear Station
Nebraska Public Power District, Docket No. 50-298, License No. DPR-46
Mr. Brian J. O'Grady, Vice President--Nuclear and Chief Nuclear
Officer, Nebraska Public Power District, 72676 648A Avenue, P.O. Box
98, Brownville, NE 68321
Crystal River Nuclear Generating Plant
Florida Power Corp., Docket No. 50-302, License No. DPR-72
Mr. Jon A. Franke, Vice President, Attn: Supervisor, Licensing &
Regulatory Affairs, Progress Energy, Inc., Crystal River Nuclear Plant
(NA2C), 15760 West Power Line Street, Crystal River, FL 34428-6708
Davis-Besse Nuclear Power Station
First Energy Nuclear Operating Co., Docket No. 50-346, License No. NPF-
3
Mr. Barry S. Allen, Site Vice President, FirstEnergy Nuclear Operating
Company, c/o Davis-Besse NPS, 5501 N. State Route 2, Oak Harbor, OH
43449-9760
Diablo Canyon Power Plant
Pacific Gas & Electric Co., Docket Nos. 50-275 and 50-323, License Nos.
DPR-80 and DPR-82
Mr. John T. Conway, Senior Vice President--Energy Supply and Chief
Nuclear Officer, Pacific Gas and Electric Company, Diablo Canyon Power
Plant, 77 Beale Street, Mail Code B32, San Francisco, CA 94105
Donald C. Cook Nuclear Plant
Indiana Michigan Power Co., Docket Nos. 50-315 and 50-316, License Nos.
DPR-58 and DPR-74
Mr. Lawrence J. Weber, Senior Vice President and Chief Nuclear Officer,
Indiana Michigan Power Company, Nuclear Generation Group, One Cook
Place, Bridgman, MI 49106
Dresden Nuclear Power Station
Exelon Generation Co., LLC, Docket Nos. 50-237 and 50-249, License Nos.
DPR-19 and DPR-25
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
Duane Arnold Energy Center
NextEra Energy Duane Arnold, LLC, Docket No. 50-331, License No. DPR-49
Mr. Peter Wells, Site Vice President, NextEra Energy, Duane Arnold
Energy Center, 3277 DAEC Road, Palo, IA 52324-9785
Edwin I. Hatch Nuclear Plant
Southern Nuclear Operating Co., Docket Nos. 50-321 and 50-366, License
Nos. DPR-57 and NPF-5
Mr. Dennis R. Madison, Vice President, Southern Nuclear Operating
Company, Inc., Edwin I. Hatch Nuclear Plant, 11028 Hatch Parkway North,
Baxley, GA 31513
Fermi
Detroit Edison Co., Docket No. 50-341, License No. NPF-43
Mr. Jack M. Davis, Senior Vice President and Chief Nuclear Officer,
Detroit Edison Company, Fermi 2--210 NOC, 6400 North Dixie Highway,
Newport, MI 48166
Fort Calhoun Station
Omaha Public Power District, Docket No. 50-285, License No. DPR-40
Mr. David J. Bannister, Vice President and Chief Nuclear Officer, Omaha
Public Power District, 444 South 16th St. Mall, Omaha, NE 68102-2247
Grand Gulf Nuclear Station
Entergy Operations, Inc., Docket No. 50-416, License No. NPF-29
Mr. Michael Perito, Vice President, Operations, Entergy Operations,
Inc., Grand Gulf Nuclear Station, Unit 1, 7003 Bald Hill Road, Port
Gibson, MS 39150
H. B. Robinson Steam Electric Plant
Carolina Power & Light Co., Docket No. 50-261, License No. DPR-23
Mr. Robert J. Duncan II, Vice President, Carolina Power & Light
Company, 3581 West Entrance Road, Hartsville, SC 29550
Hope Creek Generating Station
PSEG Nuclear, LLC, Docket No. 50-354, License No. NPF-57
[[Page 16096]]
Mr. Thomas Joyce, President and Chief Nuclear Officer, PSEG Nuclear
LLC-N09, P. O. Box 236, Hancocks Bridge, NJ 08038
Indian Point Energy Center
Entergy Nuclear Operations, Inc., Docket Nos. 50-247 and 50-286,
License Nos. DPR-26 and DPR-64
Mr. John Ventosa, Vice President, Operations, Entergy Nuclear
Operations, Inc., Indian Point Energy Center, 450 Broadway, GSB, P.O.
Box 249, Buchanan, NY 10511-0249
James A. FitzPatrick Nuclear Power Plant
Entergy Nuclear Operations, Inc., Docket No. 50-333, License No. DPR-59
Mike Colomb, Vice President, Operations, Entergy Nuclear Operations,
Inc., James A. FitzPatrick Nuclear Power Plant, P.O. Box 110, Lycoming,
NY 13093
Joseph M. Farley Nuclear Plant
Southern Nuclear Operating Co., Docket Nos. 50-348 and 50-364, License
Nos. NPF-2 and NPF-8
Mr. Tom Lynch, Vice President--Farley, Southern Nuclear Operating
Company, Inc., Joseph M. Farley Nuclear Plant, 7388 North State Highway
95, Columbia, AL 36319
Kewaunee Power Station
Dominion Energy Kewaunee, Inc., Docket No. 50-305, License No. DPR-43
Mr. David A. Heacock, President and Chief Nuclear Officer, Dominion
Energy Kewaunee, Inc., Innsbrook Technical Center, 5000 Dominion
Boulevard, Glen Allen, VA 23060-6711
LaSalle County Station
Exelon Generation Co., LLC, Docket Nos. 50-373 and 50-374, License Nos.
NPF-11 and NPF-18
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
Limerick Generating Station
Exelon Generation Co., LLC, Docket Nos. 50-352 and 50-353, License Nos.
NPF-39 and NPF-85
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
Millstone Nuclear Power Station
Dominion Nuclear Connecticut, Inc., Docket Nos. 50-336 and 50-423,
License Nos. DPR-65 and NPF-49
Mr. David A. Heacock, President and Chief Nuclear Officer, Dominion
Nuclear Connecticut, Inc., Innsbrook Technical Center, 5000 Dominion
Boulevard, Glen Allen, VA 23060-6711
Monticello Nuclear Generating Plant
Northern States Power Company, Docket No. 50-263, License No. DPR-22
Mr. Timothy J. O'Connor, Site Vice President, Northern States Power
Company--Minnesota, Monticello Nuclear Generating Plant, 2807 West
County Road 75, Monticello, MN 55362-9637
Nine Mile Point Nuclear Station
Nine Mile Point Nuclear Station, LLC, Docket Nos. 50-220 and 50-410,
License Nos. DPR-63 and NPF-69
Mr. Ken Langdon, Vice President Nine Mile Point, Nine Mile Point
Nuclear Station, LLC, P. O. Box 63, Lycoming, NY 13093
North Anna Power Station
Virginia Electric & Power Co., Docket Nos. 50-338 and 50-339, License
Nos. NPF-4 and NPF-7
Mr. David A. Heacock, President and Chief Nuclear Officer, Dominion
Nuclear, Innsbrook Technical Center, 5000 Dominion Boulevard, Glen
Allen, VA 23060-6711
Oconee Nuclear Station
Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270 and 50-287,
License Nos. DPR-38, DPR-47 and DPR-55
Mr. Preston Gillespie, Site Vice President, Oconee Nuclear Station,
Duke Energy Carolinas, LLC, 7800 Rochester Highway, Seneca, SC 29672
Oyster Creek Nuclear Generating Station
Exelon Generation Co., LLC, Docket No. 50-219, License No. DPR-16
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
Palisades Nuclear Plant
Entergy Nuclear Operations, Inc., Docket No. 50-255, License No. DPR-20
Mr. Anthony J. Vitale, Site Vice President--Palisades, Entergy Nuclear
Operations, Inc., Palisades Nuclear Plant, 27780 Blue Star Memorial
Highway, Covert, MI 49043
Palo Verde Nuclear Generating Station
Arizona Public Service Company, Docket Nos. STN 50-528, STN 50-529 and
STN 50-530, License Nos. NPF-41, NPF-51 and NPF-74
Mr. Randall K. Edington, Executive Vice President Nuclear and Chief
Nuclear Officer, Arizona Public Service Co., P. O. Box 52034, MS 7602,
Phoenix, AZ 85072-2034
Peach Bottom Atomic Power Station
Exelon Generation Co., LLC, Docket Nos. 50-277 and 50-278, License Nos.
DPR-44 and DPR-56
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
Perry Nuclear Power Plant
First Energy Nuclear Operating Co., Docket No. 50-440, License No. NPF-
58
Mr. Vito A. Kaminskas, Site Vice President--Nuclear--Perry, FirstEnergy
Nuclear Operating Company, Perry Nuclear Power Plant, 10 Center Road,
A290, Perry, OH 44081
Pilgrim Nuclear Power Station Unit No. 1
Entergy Nuclear Operations, Inc., Docket No. 50-293, License No. DPR-35
Mr. Robert Smith, Vice President and Site Vice President, Entergy
Nuclear Operations, Inc., Pilgrim Nuclear Power Station, 600 Rocky Hill
Road, Plymouth, MA 02360-5508
Point Beach Nuclear Plant
NextEra Energy Point Beach, LLC, Docket Nos. 50-266 and 50-301, License
Nos. DPR-24 and DPR-27
Mr. Larry Meyer, Site Vice President, NextEra Energy Point Beach, LLC,
Point Beach Nuclear Plant, Units 1 & 2, 6610 Nuclear Road, Two Rivers,
WI 54241-9516
Prairie Island Nuclear Generating Plant
Northern States Power Co. Minnesota, Docket Nos. 50-282 and 50-306,
License Nos. DPR-42 and DPR-60
Mr. Mark A. Schimmel, Site Vice President, Northern States Power
Company--Minnesota, Prairie Island Nuclear Generating Plant, 1717
Wakonade Drive East, Welch, MN 55089-9642
Quad Cities Nuclear Power Station
Exelon Generation Co., LLC, Docket Nos. 50-254 and 50-265, License Nos.
DPR-29 and DPR-30
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
[[Page 16097]]
R.E. Ginna Nuclear Power Plant
R.E. Ginna Nuclear Power Plant, LLC, Docket No. 50-244, License No.
DPR-18
Mr. Joseph E. Pacher, Vice President, R.E. Ginna Nuclear Power Plant,
LLC, R.E. Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
River Bend Station
Entergy Operations, Inc., Docket No. 50-458, License No. NPF-47
Mr. Eric W. Olson, Vice President, Operations, Entergy Operations,
Inc., River Bend Station, 5485 U.S. Highway 61N, St. Francisville, LA
70775
Salem Nuclear Generating Station
PSEG Nuclear, LLC, Docket Nos. 50-272 and 50-311, License Nos. DPR-70
and DPR-75
Mr. Thomas Joyce, President and Chief Nuclear Officer, PSEG Nuclear
LLC--N09, P.O. Box 236, Hancocks Bridge, NJ 08038
San Onofre Nuclear Generating Station
Southern California Edison Co., Docket Nos. 50-361 and 50-362, License
Nos. NPF-10 and NPF-15
Mr. Peter T. Dietrich, Senior Vice President and Chief Nuclear Officer,
Southern California Edison Company, San Onofre Nuclear Generating
Station, P.O. Box 128, San Clemente, CA 92674-0128
Seabrook
NextEra Energy Seabrook, LLC, Docket No. 50-443, License No. NPF-86
Mr. Paul Freeman, Site Vice President, NextEra Energy Seabrook, LLC, c/
o Mr. Michael O'Keefe, NextEra Energy Seabrook, LLC, P.O. Box 300,
Seabrook, NH 03874
Sequoyah Nuclear Plant
Tennessee Valley Authority, Docket Nos. 50-327 and 50-328, License Nos.
DPR-77 and DPR-79
Mr. Preston D. Swafford, Chief Nuclear Officer and Executive Vice
President, Tennessee Valley Authority, 3R Lookout Place, 1101 Market
Street, Chattanooga, TN 37402-2801
Shearon Harris Nuclear Power Plant
Carolina Power & Light Co., Docket No. 50-400, License No. NPF-63
Mr. Christopher L. Burton, Vice President, Progress Energy Carolinas,
Inc., Shearon Harris Nuclear Power Plant, P.O. Box 165, Mail Zone 1,
New Hill, NC 27562-0165
South Texas Project
STP Nuclear Operating Co., Docket Nos. 50-498 and 50-499, License Nos.
NPF-76 and NPF-80
Mr. Edward D. Halpin, President, Chief Executive Officer and Chief
Nuclear Officer, STP Nuclear Operating Company, South Texas Project,
P.O. Box 289, Wadsworth, TX 77483
St. Lucie Plant
Florida Power & Light Co., Docket Nos. 50-335 and 50-389, License Nos.
DPR-67 and NPF-16
Mr. Mano Nazar, Executive Vice President and Chief Nuclear Officer,
NextEra Energy, 700 Universe Boulevard, P.O. Box 14000, Juno Beach, FL
33408-0420
Surry Power Station
Virginia Electric & Power Co., Docket Nos. 50-280 and 50-281, License
Nos. DPR-32 and DPR-371
Mr. David A. Heacock, President and Chief Nuclear Officer, Dominion
Nuclear, Innsbrook Technical Center, 5000 Dominion Boulevard, Glen
Allen, VA 23060-6711
Susquehanna Steam Electric Station
PPL Susquehanna, LLC, Docket Nos. 50-387 and 50-388, License Nos. NPF-
14 and NPF-22
Mr. Timothy S. Rausch, Senior Vice President and Chief Nuclear Officer,
PPL Susquehanna, LLC, 769 Salem Boulevard, NUCSB3, Berwick, PA 18603-
0467
Three Mile Island Nuclear Station, Unit 1
(* via corrected letter dated 3/13/12--ML12073A366) Exelon Generation
Co., LLC, Docket No. 50-289, License No. DPR-50
Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon
Nuclear, 4300 Winfield Road, Warrenville, IL 60555
Turkey Point
Florida Power & Light Co., Docket Nos. 50-250 and 50-251, License Nos.
DPR-31 and DPR-41
Mr. Mano Nazar, Executive Vice President and Chief Nuclear Officer,
NextEra Energy, 700 Universe Boulevard, P.O. Box 14000, Juno Beach, FL
33408-0420
Vermont Yankee Nuclear Power Station
Entergy Nuclear Operations, Inc., Docket No. 50-271, License No. DPR-28
Mr. Christopher J. Wamser, Site Vice President, Entergy Nuclear
Operations, Inc., Vermont Yankee Nuclear Power Station, 320 Governor
Hunt Road, Vernon, VT 05354
Virgil C. Summer Nuclear Station
South Carolina Electric & Gas Co., Docket No. 50-395, License No. NPF-
12
Mr. Thomas D. Gatlin, Vice President Nuclear Operations, South Carolina
Electric & Gas Company, Virgil C. Summer Nuclear Station, Post Office
Box 88, Mail Code 300, Jenkinsville, SC 29065
Vogtle Electric Generating Plant
Southern Nuclear Operating Co., Docket Nos. 50-424 and 50-425, License
Nos. NPF-68 and NPF-81
Mr. Tom E. Tynan, Vice President, Southern Nuclear Operating Company,
Inc., Vogtle Electric Generating Plant, 7821 River Road, Waynesboro, GA
30830
Vogtle Electric Generating Plant, Units 3 & 4
Southern Nuclear Operating Co., Docket Nos. 52-025 and 52-026, License
Nos. NPF-91 and NPF-92
Mr. B. L. Ivey, Vice President, Regulatory Affairs, Southern Nuclear
Operating Company, Inc., 40 Inverness Center Parkway, Bin B022,
Birmingham, AL 35242
Waterford Steam Electric Station
Entergy Operations, Inc., Docket No. 50-382, License No. NPF-38
Ms. Donna Jacobs, Vice President, Operations, Entergy Operations, Inc.,
Waterford Steam Electric Station, Unit 3, 17265 River Road, Killona, LA
70057-0751
Watts Bar Nuclear Plant, Unit 1
Tennessee Valley Authority, Docket No. 50-390, License No. NPF-90
Mr. Preston D. Swafford, Chief Nuclear Officer and Executive Vice
President, Tennessee Valley Authority, 3R Lookout Place, 1101 Market
Street, Chattanooga, TN 37402-2801
Watts Bar Nuclear Plant, Unit 2
Tennessee Valley Authority, Docket No. 50-391, Construction Permit No.
CPPR No. 092
Mr. Michael D. Skaggs, Senior Vice President, Nuclear Generation
Development and Construction, Tennessee Valley Authority, 6A Lookout
Place, 1101 Market Street, Chattanooga, TN 37402-2801
William B. McGuire Nuclear Station
Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, License Nos.
NPF-9 and NPF-17
Mr. Regis T. Repko, Vice President, Duke Energy Carolinas, LLC, McGuire
Nuclear Site, 12700 Hagers Ferry Road, Huntersville, NC 28078
[[Page 16098]]
Wolf Creek Generating Station
Wolf Creek Nuclear Operating Corp., Docket No. 50-482, License No. NPF-
42
Mr. Matthew W. Sunseri, President and Chief Executive Officer, Wolf
Creek Nuclear Operating Corporation, P.O. Box 411, Burlington, KS 66839
Requirements for Mitigation Strategies for Beyond-Design-Basis External
Events at Operating Reactor Sites and Construction Permit Holders
This Order requires a three-phase approach for mitigating beyond-
design-basis external events. The initial phase requires the use of
installed equipment and resources to maintain or restore core cooling,
containment and spent fuel pool (SFP) cooling capabilities. The
transition phase requires providing sufficient, portable, onsite
equipment and consumables to maintain or restore these functions until
they can be accomplished with resources brought from off site. The
final phase requires obtaining sufficient offsite resources to sustain
those functions indefinitely.
(1) Licensees or construction permit (CP) holders shall develop,
implement, and maintain guidance and strategies to maintain or restore
core cooling, containment and SFP cooling capabilities following a
beyond-design-basis external event.
(2) These strategies must be capable of mitigating a simultaneous
loss of all alternating current (ac) power and loss of normal access to
the ultimate heat sink and have adequate capacity to address challenges
to core cooling, containment, and SFP cooling capabilities at all units
on a site subject to this Order.
(3) Licensees or CP holders must provide reasonable protection for
the associated equipment from external events. Such protection must
demonstrate that there is adequate capacity to address challenges to
core cooling, containment, and SFP cooling capabilities at all units on
a site subject to this Order.
(4) Licensees or CP holders must be capable of implementing the
strategies in all modes.
(5) Full compliance shall include procedures, guidance, training,
and acquisition, staging, or installing of equipment needed for the
strategies.
Requirements for Mitigation Strategies for Beyond-Design-Basis External
Events at Col Holder Reactor Sites (VOGTLE Units 3 and 4)
Attachment 2 to this order for Part 50 licensees requires a phased
approach for mitigating beyond-design-basis external events. The
initial phase requires the use of installed equipment and resources to
maintain or restore core cooling, containment and spent fuel pool (SFP)
cooling capabilities. The transition phase requires providing
sufficient, portable, onsite equipment and consumables to maintain or
restore these functions until they can be accomplished with resources
brought from off site. The final phase requires obtaining sufficient
offsite resources to sustain those functions indefinitely.
The design bases of Vogtle Units 3 and 4 includes passive design
features that provide core, containment and SFP cooling capability for
72 hours, without reliance on alternating current (ac) power. These
features do not rely on access to any external water sources since the
containment vessel and the passive containment cooling system serve as
the safety-related ultimate heat sink. The NRC staff reviewed these
design features prior to issuance of the combined licenses for these
facilities and certification of the AP1000 design referenced therein.
The AP1000 design also includes equipment to maintain required safety
functions in the long term (beyond 72 hours to 7 days) including
capability to replenish water supplies. Connections are provided for
generators and pumping equipment that can be brought to the site to
back up the installed equipment. The staff concluded in its final
safety evaluation report for the AP1000 design that the installed
equipment (and alternatively, the use of transportable equipment) is
capable of supporting extended operation of the passive safety systems
to maintain required safety functions in the long term. As such, this
Order requires Vogtle Units 3 and 4 to address the following
requirements relative to the final phase.
(1) Licensees shall develop, implement, and maintain guidance and
strategies to maintain or restore core cooling, containment and SFP
cooling capabilities following a beyond-design-basis external event.
(2) These strategies must be capable of mitigating a simultaneous
loss of all ac power and loss of normal access to the normal heat sink
and have adequate capacity to address challenges to core cooling,
containment, and SFP cooling capabilities at all units on a site
subject to this Order.
(3) Licensees must provide reasonable protection for the associated
equipment from external events. Such protection must demonstrate that
there is adequate capacity to address challenges to core cooling,
containment, and SFP cooling capabilities at all units on a site
subject to this Order.
(4) Licensees must be capable of implementing the strategies in all
modes.
(5) Full compliance shall include procedures, guidance, training,
and acquisition, staging, or installing of equipment needed for the
strategies.
[FR Doc. 2012-6547 Filed 3-16-12; 8:45 am]
BILLING CODE 7590-01-P