Federal Register / Vol. 77, No. 53 / Monday, March 19, 2012 / Notices 16091 

1CP 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) 

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 HOLDERS OF CONSTRUCTION PERMITS IN ACTIVE OR DEFERRED STATUS.Docket Nos. (as shown in Attachment 1) License Nos. (as shown in 

Attachment 1) or Construction 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.’’ 

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 NearTerm 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, ‘‘NearTerm 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 NearTerm 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-designbasis 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 


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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-designbasis 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-designbasis 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 EFiling 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 

hearing.docket@nrc.gov, 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 NRCissued 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 ESubmittal 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 plugin 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/esubmittals.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/esubmittals.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/esubmittals.html, by email at 

MSHD.Resource@nrc.gov, or by a tollfree 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 firstclass 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 


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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 


emcdonald on DSK29S0YB1PROD with NOTICES
16096 Federal Register / Vol. 77, No. 53 / Monday, March 19, 2012 / Notices 

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 


emcdonald on DSK29S0YB1PROD with NOTICES
Federal Register / Vol. 77, No. 53 / Monday, March 19, 2012 / Notices 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 


emcdonald on DSK29S0YB1PROD with NOTICES
16098 Federal Register / Vol. 77, No. 53 / Monday, March 19, 2012 / Notices 

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-designbasis 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-designbasis 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-designbasis 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 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. (as shown in Attachment 1); 

License Nos. (as shown in Attachment 1); 

EA–12–050; [NRC–2012–0069] 

In the Matter of All Operating Boiling 

Water Reactor Licensees With Mark I 

and Mark II Containments; Order 

Modifying Licenses With Regard To 

Reliable Hardened Containment Vents 

(Effective Immediately) 

I 

The Licensees identified in 

Attachment 1 to this Order hold licenses 

issued by the U.S. Nuclear Regulatory 

Commission (NRC or Commission) 

authorizing operation 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.’’ Specifically, these Licensees 

operate boiling-water reactors (BWRs) 

with Mark I and Mark II containment 

designs. 

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, which 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. 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 


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