UNITED STATES 


NUCLEAR REGULATORY COMMISSION 


WASHINGTON, D.C. 20555·0001 

March 12,2012 

EA-12-049 

All Power Reactor Licensees and 

Holders of Construction Permits in 

Active or Deferred Status 

SUBJECT: 	 ISSUANCE OF ORDER TO MODIFY LICENSES WITH REGARD TO 

REQUIREMENTS FOR MITIGATION STRATEGIES FOR 

BEYOND-DESIGN-BASIS EXTERNAL EVENTS 

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Order that modifies the 

current license for your facility. The Order requires provisions for mitigation strategies for 

beyond-design-basis external events, and applies to all addressees listed in Attachment 1 to the 

enclosed Order. 

Following the earthquake and tsunami at the Fukushima Dai-ichi nuclear power plant in March 

2011, the NRC established a senior-level task force referred to as the Near-Term Task Force 

(NTTF). The NTTF conducted a systematic and methodical review of the NRC regulations and 

processes to determine if the agency should make safety improvements in light of the events in 

Japan. As a result of this review, the NTTF issued SECY-11-0093, "Near-Term Report and 

Recommendations for Agency Actions Following the Events in Japan," Agencywide Documents 

Access and Management System (ADAMS) Accession No. ML 11186A950. SECY-11-0124, 

"Recommended Actions to be Taken Without Delay from the Near-Term Task Force Report," 

ADAMS Accession No. ML 112911571 and SECY-11-0137, "Prioritization of Recommended 

Actions to be Taken in Response to Fukushima Lessons Learned," ADAMS Accession 

No.ML 11272A 111 were issued to establish the NRC staff's prioritization of the recommendations. 

Recommendation 4.2 concerning mitigation strategies was determined to be a high-priority 

action. This Order is based upon the NTTF recommendation. 

The events at Fukushima Dai-ichi highlight the possibility that extreme natural phenomena could 

challenge the prevention, mitigation and emergency preparedness defense-in-depth layers. At 

Fukushima, limitations in time and unpredictable conditions associated with the accident 

significantly challenged attempts by the responders to preclude core damage and containment 

failure. During the events in Fukushima, the challenges faced by the operators were beyond any 

faced previously at a commercial nuclear reactor. It was determined that additional 

requirements must be imposed to mitigate beyond-design-basis external events. These 

additional requirements impose guidance and strategies to 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 spent fuel pool affected all units at a site simultaneously. 

The NRC staff has determined that continued operation does not pose an imminent risk to public 

health and safety; however, the additional requirements outlined in this Order are necessary in 

light of insights gained from the events at Fukushima Dai-ichi. The requirements of this Order 

are immediately effective and are expected to remain in place until superseded by Order or rule. 
All Power Reactor Licensees and 

Holders of Construction Permits in 

Active or Deferred Status -2­

Pursuant to Section 223 of the Atomic Energy Act of 1954, as amended, any person who willfully 

violates, attempts to violate, or conspires to violate, any provision of this Order shall be subject to 

criminal prosecution as set forth in that section. Violation of this order may also subject the 

person to civil monetary penalty. 

The enclosed Order requires responses and actions within specified timeframes. Please contact 

your Licensing Project Manager or Mr. Steven Bloom, Mitigation Strategies Order Project 

Manager (301-415-2431), regarding any issues related to compliance with the requirements in 

the enclosed Order, or if you have other questions. 

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its 

enclosure will be made available electronically for public inspection in the NRC Public Document 

Room or from the NRC's document system (ADAMS), accessible from the NRC Web site at 

http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not 

include any personal privacy, proprietary, or safeguards information so that it can be made 

available to the public without redaction. The NRC also includes significant enforcement actions 

on its Web site at (http://www.nrc.gov/reading-rm/doc-collections/enforcementlactions/. The 

enclosed Order has been forwarded to the Office of the Federal Registerfor publication. 

Eric J. Leeds, Director 

Office f Nucl eactor Regulation 

Michael Johnson, Director 

Office of New Reactors 

Enclosure: 

Order (EA-12-049) 

cc: Listserv 
ORDER TO MODIFYING LICENSES WITH REGARD TO REQUIREMENTS FOR MITIGATION 


STRATEGIES FOR BEYOND-DESIGN-BASIS EXTERNAL EVENTS 


EA-12-049 


Enclosure 
7590-01-P 


UNITED STATES OF AMERICA 


NUCLEAR REGULATORY COMMISSION 


I n the Matter of ) 

) 

ALL POWER REACTOR ) Docket Nos. (as shown in Attachment 1) 

LICENSEES AND HOLDERS ) License Nos. (as shown in Attachment 1) or 

OF CONSTRUCTION PERMITS IN ) Construction Permit Nos. (as shown in 

ACTIVE OR DEFERRED STATUS ) Attachment 1) ) 

) 

) EA-12-049 

ORDER MODIFYING LICENSES 


WITH REGARD TO REQUIREMENTS FOR MITIGATION STRATEGIES 


FOR BEYON D·DESIGN·BASIS EXTERNAL EVENTS 


(EFFECTIVE IMMEDIATELY) 


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 andlor construction of nuclear power plants in accordance 

with the Atomic Energy Act of 1954, as amended, and Title 10 of the Code ofFederal 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. 

) 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) 
- 2 ­

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," 
- 3 ­

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. ML 11353A008). 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 ill 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 
- 4 -


Fukushima Dai-ichi leads the staff to conclude that additional requirements must be imposed on 

Licensees or CP holders to increase the 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 (lSG) 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 
- 5 ­

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.S.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-de sign-basis external events, the 
- 6 ­

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 
- 7 


(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, 161 i, 1610, 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 

requirement is set forth in the CPo 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 
- 8 ­

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 
- 9 ­

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 finallSG, 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, 8.2, 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. 
- 10 ­

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. 
- 11 ­

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 bye-mail at 

hearing.docket@nrc.gov, or by telephone at (301) 415-1677, to request (1) a digitallD certificate, 

which allows thsparticipant (or its counselor 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 counselor representative, already holds an NRC-issued digitallD 

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 digitallD certificate is available on NRC's public Web site 

at http://www.nrc.gov/site-he/p/e-submitta/slapp/v-certificates.htm/. System requirements for 

accessing the E-Submittal server are detailed in NRC's "Guidance for Electronic Submission," 

which is avail~ble on the agency's public Web site at 

http://www.nrc.gov/site-he/p/esubmitta/s.htm/. 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-he/plesubmitta/s.html. 

Once a participant has obtained a digitallD certificate and a docket has been created, the 

participant can then submit a request for hearing or petition for leave to intervene. Submissions 
- 12 ­

should be in Portable Document Format (PDF) in accordance with NRC guidance available on the 

NRC public Web site at http://www.nrc.qov/site-helpie-submitta/s.html.Afiling 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 e-mail notice confirming receipt of the document. The 

E-Filing system also distributes an e-mail 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 counselor 

representative) must apply for and receive a digitallD 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.qov/site-he/P/e-submitta/s.html.by e-mail at 

MSHD.Resource@nrc.gov, 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, 
- 13 -


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://ehd.nrc.qov/EHD Proceeding/home. asp, 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). 
- 14 ­

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 

~/~ 

eactor Regulation 

Eric J. Leeds, Director 

Office f Nuclear 

Michael R. ohnson, Director 

Office of New Reactors 

Dated this 12th day of March 2012 
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 

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 

Attachment 1 
-2­

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 
-3­

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 
-4­

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 
-5­

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 
-6­

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 
-7­

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 

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 
-8­

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 
-9­

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 
-10­

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 
-11­

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 
-12­

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 

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 

RE. Ginna Nuclear Power Plant, LLC 

RE. 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 61 N 

st. Francisville, LA 70775 
-13­

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 
-14­

Shearon Harris Nuclear Power Plant 

Carolina Power & Light Co. 

Docket No. 50-400 

License No. NPF-63 

Mr. Chri~opherL. 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-37 

Mr. David A. Heacock 

President and Chief Nuclear Officer 

Dominion Nuclear 

Innsbrook Technical Center 

5000 Dominion Boulevard 

Glen Allen, VA 23060-6711 
-15­

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 

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 1\10. 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 
-16­

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 
-17­

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 

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. Box411 

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. 

Attachment 2 
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 AP1 000 design referenced therein. 

The AP1 000 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 AP1 000 

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 Vogt/e 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. 

Attachment 3 
All Power Reactor Licensees and 

Holders of Construction Permits in 

Active or Deferred Status -2­

Pursuant to Section 223 of the Atomic Energy Act of 1954, as amended, any person who willfully 

violates, attempts to violate, or conspires to violate, any provision of this Order shall be subject to 

criminal prosecution as set forth in that section. Violation of this order may also subject the 

person to civil monetary penalty. 

The enclosed Order requires responses and actions within specified timeframes. Please contact 

your Licensing Project Manager or Mr. Steven Bloom, Mitigation Strategies Order Project 

Manager (301-415-2431), regarding any issues related to compliance with the requirements in 

the enclosed Order, or if you have other questions. 

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its 

enclosure will be made available electronically for public inspection in the NRC Public Document 

Room or from the NRC's document system (ADAMS), accessible from the NRC Web site at 

http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not 

include any personal privacy, proprietary, or safeguards information so that it can be made 

available to the public without redaction. The NRC also includes significant enforcement actions 

on its Web site at (http://www.nrc.gov/reading-rm/doc-collections/enforcementlactions/. The 

enclosed Order has been forwarded to the Office of the Federal Registerfor publication. 

Sincerely, 

Eric J. Leeds, Director 

Office of Nuclear Reactor Regulation 

Michael R. Johnson, Director 

Office of New Reactors 

Enclosure: 


Order (EA-12-049) 


cc: Listserv 

Distribution: See next page 

ADAMS Accession No.: ML 12054A736 *e-mail concurrence 

OFFICE 

NAME 

DATE 

OFFICE 

NAME 

DATE 

PM: NRR/JLO 

SBloom 

03/12/2012 

0: JLO* 

OSkeen 

03/11/2012 

LA: NRR/JLO 

SRohrer 

03/12/2012 

00: OE* 

RZimmerman 

(NHilton for) 

03/09/2012 

QTE* 

JOoughterty 

02/05/2012 

00: NRO 

MJohnson 

03/12/2012 

BC: NRR/JLO 

RPascarelli 

03/11/2012 

00: NRR 

ELeeds 

03/12/2012 

OGC* 

CSafford 

03/10/2012 

OFFICIAL RECORD COPY